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Sample records for characterizing low-level radioactive

  1. IGRIS for characterizing low-level radioactive waste

    Energy Technology Data Exchange (ETDEWEB)

    Peters, C.W. [Nuclear Diagnostic Systems, Springfield, VA (United States); Swanson, P.J. [Concord Associates, Knoxville, TN (United States)

    1993-03-01

    A recently developed neutron diagnostic probe system has the potential to noninvasively characterize low-level radioactive waste in bulk soil samples, containers such as 55-gallon barrels, and in pipes, valves, etc. The probe interrogates the target with a low-intensity beam of 14-MeV neutrons produced from the deuterium-tritium reaction in a specially designed sealed-tube neutron-generator (STNG) that incorporates an alpha detector to detect the alpha particle associated with each neutron. These neutrons interact with the nuclei in the target to produce inelastic-, capture-, and decay-gamma rays that are detected by gamma-ray detectors. Time-of-flight methods are used to separate the inelastic-gamma rays from other gamma rays and to determine the origin of each inelastic-gamma ray in three dimensions through Inelastic-Gamma Ray Imaging and Spectroscopy (IGRIS). The capture-gamma ray spectrum is measured simultaneously with the IGRIS measurements. The decay-gamma ray spectrum is measured with the STNG turned off. Laboratory proof-of-concept measurements were used to design prototype systems for Bulk Soil Assay, Barrel Inspection, and Decontamination and Decommissioning and to predict their minimum detectable levels for heavy toxic metals (As, Hg, Cr, Zn, Pb, Ni, and Cd), uranium and transuranics, gamma-ray emitters, and elements such as chlorine, which is found in PCBs and other pollutants. These systems are expected to be complementary and synergistic with other technologies used to characterize low-level radioactive waste.

  2. Characterization of Class A low-level radioactive waste 1986--1990

    International Nuclear Information System (INIS)

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

  3. Characterization of Class A low-level radioactive waste 1986--1990

    International Nuclear Information System (INIS)

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

  4. Importance of geologic characterization of potential low-level radioactive waste disposal sites

    Science.gov (United States)

    Weibel, C.P.; Berg, R.C.

    1991-01-01

    Using the example of the Geff Alternative Site in Wayne County, Illinois, for the disposal of low-level radioactive waste, this paper demonstrates, from a policy and public opinion perspective, the importance of accurately determining site stratigraphy. Complete and accurate characterization of geologic materials and determination of site stratigraphy at potential low-level waste disposal sites provides the frame-work for subsequent hydrologic and geochemical investigations. Proper geologic characterization is critical to determine the long-term site stability and the extent of interactions of groundwater between the site and its surroundings. Failure to adequately characterize site stratigraphy can lead to the incorrect evaluation of the geology of a site, which in turn may result in a lack of public confidence. A potential problem of lack of public confidence was alleviated as a result of the resolution and proper definition of the Geff Alternative Site stratigraphy. The integrity of the investigation was not questioned and public perception was not compromised. ?? 1991 Springer-Verlag New York Inc.

  5. Site characterization field manual for near surface geologic disposal of low-level radioactive waste

    International Nuclear Information System (INIS)

    This field manual has been developed to aid states and regions to do a detailed characterization of a proposed near-surface low-level waste disposal site. The field manual is directed at planners, staff personnel and experts in one discipline to acquaint them with the requirements of other disciplines involved in site characterization. While it can provide a good review, it is not designed to tell experts how to do their job within their own discipline

  6. Characterization and assessment for the Weldon Spring Quarry low-level radioactive waste storage site

    International Nuclear Information System (INIS)

    The Weldon Spring Quarry is located approximately 4 miles from the Weldon Spring Chemical Plant and 20 miles west of St. Louis. Originally a limestone and sand quarry, the 9 acre site was later used for the disposal of TNT-contaminated soils during the 1940's and the disposal of low-level radioactive waste during the 1960's. The most important potential hazards posed by the quarry are contamination of groundwater, radiation exposure and contamination of trespassers, and contamination of surface waters. The potential for groundwater contamination was identified at an early date by the US Department of Energy (DOE) as the most important of these potential hazards. Particular concern exists for the future of the municipal well field located between the quarry and the Missouri River. At the present time the well field supplies drinking water for the area from Weldon Spring up to and including parts of the city of St. Charles. Chapters are devoted to geology, waste inventory, hydrology, investigations of radionuclide migration from the quarry, numerical modeling of engineering options, and raffinate pits. 40 references, 182 figures, 49 tables, 7 appendixes

  7. Controlling low-level radioactive waste

    International Nuclear Information System (INIS)

    This series of information sheets describes at a popular level the sources of low-level radioactive wastes, their associated hazards, methods of storage, transportation and disposal, and the Canadian regulations that cover low-level wastes

  8. Characterization of Class A low-level radioactive waste 1986--1990. Volume 2: Main report -- Part A

    Energy Technology Data Exchange (ETDEWEB)

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

    1994-01-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1994-01-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1994-01-01

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

  11. Characterization of Class A low-level radioactive waste 1986--1990. Volume 6: Appendices G--J

    Energy Technology Data Exchange (ETDEWEB)

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

    1994-01-01

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

  12. Microbiological treatment of low level radioactive waste

    International Nuclear Information System (INIS)

    This report summarises the work of an experimental programme investigating the anaerobic digestion of low-level radioactive wastes. The project focused on the selection of the optimum bioreactor design to achieve 95% removal or stabilisation of the biodegradable portion of low-level radioactive wastes. Performance data was obtained for the bioreactors and process scale-up factors for the construction of a full-scale reactor were considered. (author)

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

    Energy Technology Data Exchange (ETDEWEB)

    1994-09-01

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

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

    International Nuclear Information System (INIS)

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

  15. Processing system for low level radioactive waste

    International Nuclear Information System (INIS)

    Low level radioactive wastes are successively charged into a container while sliding a partition plate such that the wastes are kept substantially in a fully charged state in the direction of the height. Radiation rays from the low level radioactive wastes contained in the container are measured by a radiation dose measuring means constituted so as to be slidable together with the partition plate. Further, the weight of the low level radioactive wastes in the container is measured by the weight measuring means, and the radioactivity concentration per unit container is calculated by a calculation means based on the result of the measurement. Accordingly, the optimum storage period and the radioactivity level can be estimated on every containers. Further, since the measuring vessel is used also as a storage vessel, long time measurement can be conducted by measuring the radioactivity for the wastes successively to enable exact evaluation. Accordingly, it is possible to save the labors for processing operation and save the storage facility. (T.M.)

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

    International Nuclear Information System (INIS)

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1996-03-01

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

  18. Low-level radioactive waste disposal facility closure

    International Nuclear Information System (INIS)

    Part I of this report describes and evaluates potential impacts associated with changes in environmental conditions on a low-level radioactive waste disposal site over a long period of time. Ecological processes are discussed and baselines are established consistent with their potential for causing a significant impact to low-level radioactive waste facility. A variety of factors that might disrupt or act on long-term predictions are evaluated including biological, chemical, and physical phenomena of both natural and anthropogenic origin. These factors are then applied to six existing, yet very different, low-level radioactive waste sites. A summary and recommendations for future site characterization and monitoring activities is given for application to potential and existing sites. Part II of this report contains guidance on the design and implementation of a performance monitoring program for low-level radioactive waste disposal facilities. A monitoring programs is described that will assess whether engineered barriers surrounding the waste are effectively isolating the waste and will continue to isolate the waste by remaining structurally stable. Monitoring techniques and instruments are discussed relative to their ability to measure (a) parameters directly related to water movement though engineered barriers, (b) parameters directly related to the structural stability of engineered barriers, and (c) parameters that characterize external or internal conditions that may cause physical changes leading to enhanced water movement or compromises in stability. Data interpretation leading to decisions concerning facility closure is discussed. 120 refs., 12 figs., 17 tabs

  19. Low-level radioactive waste disposal facility closure

    Energy Technology Data Exchange (ETDEWEB)

    White, G.J.; Ferns, T.W.; Otis, M.D.; Marts, S.T.; DeHaan, M.S.; Schwaller, R.G.; White, G.J. (EG and G Idaho, Inc., Idaho Falls, ID (USA))

    1990-11-01

    Part I of this report describes and evaluates potential impacts associated with changes in environmental conditions on a low-level radioactive waste disposal site over a long period of time. Ecological processes are discussed and baselines are established consistent with their potential for causing a significant impact to low-level radioactive waste facility. A variety of factors that might disrupt or act on long-term predictions are evaluated including biological, chemical, and physical phenomena of both natural and anthropogenic origin. These factors are then applied to six existing, yet very different, low-level radioactive waste sites. A summary and recommendations for future site characterization and monitoring activities is given for application to potential and existing sites. Part II of this report contains guidance on the design and implementation of a performance monitoring program for low-level radioactive waste disposal facilities. A monitoring programs is described that will assess whether engineered barriers surrounding the waste are effectively isolating the waste and will continue to isolate the waste by remaining structurally stable. Monitoring techniques and instruments are discussed relative to their ability to measure (a) parameters directly related to water movement though engineered barriers, (b) parameters directly related to the structural stability of engineered barriers, and (c) parameters that characterize external or internal conditions that may cause physical changes leading to enhanced water movement or compromises in stability. Data interpretation leading to decisions concerning facility closure is discussed. 120 refs., 12 figs., 17 tabs.

  20. Issue briefs on low-level radioactive wastes

    International Nuclear Information System (INIS)

    This report contains 4 Issue Briefs on low-level radioactive wastes. They are entitled: Handling, Packaging, and Transportation, Economics of LLW Management, Public Participation and Siting, and Low Level Waste Management

  1. Understanding low-level radioactive waste. National Low-Level Radioactive Waste Management Program

    International Nuclear Information System (INIS)

    Chapters are devoted to: background and policymaking for low-level waste management; commercial low-level waste generation; Department of Energy low-level waste generation; low-level waste treatment; packaging and transportation; commercial low-level waste disposal; Department of Energy low-level waste disposal; Department of Energy low-level waste management program; and laws and regulations

  2. Directions in low-level radioactive waste management: A brief history of commercial low-level radioactive waste disposal

    Energy Technology Data Exchange (ETDEWEB)

    1994-08-01

    This report presents a history of commercial low-level radioactive waste disposal in the United States, with emphasis on the history of six commercially operated low-level radioactive waste disposal facilities. The report includes a brief description of important steps that have been taken during the last decade to ensure the safe disposal of low-level radioactive waste in the 1990s and beyond. These steps include the issuance of comprehensive State and Federal regulations governing the disposal of low-level radioactive waste, and the enactment of Federal laws making States responsible for the disposal of such waste generated within their borders.

  3. Directions in low-level radioactive waste management: A brief history of commercial low-level radioactive waste disposal

    International Nuclear Information System (INIS)

    This report presents a history of commercial low-level radioactive waste disposal in the United States, with emphasis on the history of six commercially operated low-level radioactive waste disposal facilities. The report includes a brief description of important steps that have been taken during the last decade to ensure the safe disposal of low-level radioactive waste in the 1990s and beyond. These steps include the issuance of comprehensive State and Federal regulations governing the disposal of low-level radioactive waste, and the enactment of Federal laws making States responsible for the disposal of such waste generated within their borders

  4. Directions in low-level radioactive waste management: A brief history of commercial low-level radioactive waste disposal

    International Nuclear Information System (INIS)

    This report presents a history of commercial low-level radioactive waste management in the United States, with emphasis on the history of six commercially operated low-level radioactive waste disposal facilities. The report includes a brief description of important steps that have been taken during the 1980s to ensure the safe disposal of low-level waste in the 1990s and beyond. These steps include the issuance of Title 10 Code of Federal Regulations Part 61, Licensing Requirements for the Land Disposal of Radioactive Waste, the Low-Level Radioactive Waste Policy Act of 1980, the Low-Level Radioactive Waste Policy Amendments Act of 1985, and steps taken by states and regional compacts to establish additional disposal sites. 42 refs., 13 figs., 1 tab

  5. Assessment of low levels of radioactive contamination

    International Nuclear Information System (INIS)

    This report describes a general methodology for the verification and clearance of sites contaminated with radioactive materials; general expressions for the risk or health detriment are derived. Techniques are developed, using Bayesian decision theory, to optimize the resources allocated to a site monitoring procedure, and to construct the probability distribution of the spatial distribution of specific activity within a site. A technique is also developed to determine the probability that a localized source of specified characteristics will not be detected by the monitoring procedure employed. The application of these techniques is illustrated by means of simple examples. This report confirms that a very large number of measurements are needed if a source of localized activity is to be detected with a high probability, and demonstrates how prior information about past radiological practices might be used to increase the probability of detection. Proposals are made for a programme of research to determine whether or not representative sites can be verified using current measuring techniques. (author)

  6. Low-level radioactive waste regulation: Science, politics and fear

    International Nuclear Information System (INIS)

    An inevitable consequence of the use of radioactive materials is the generation of radioactive wastes and the public policy debate over how they will be managed. In 1980, Congress shifted responsibility for the disposal of low-level radioactive wastes from the federal government to the states. This act represented a sharp departure from more than 30 years of virtually absolute federal control over radioactive materials. Though this plan had the enthusiastic support of the states in 1980, it now appears to have been at best a chimera. Radioactive waste management has become an increasingly complicated and controversial issue for society in recent years. This book discusses only low-level wastes, however, because Congress decided for political reasons to treat them differently than high-level wastes. The book is based in part on three symposia sponsored by the division of Chemistry and the Law of the American Chemical Society. Each chapter is derived in full or in part from presentations made at these meetings, and includes: (1) Low-level radioactive wastes in the nuclear power industry; (2) Low-level radiation cancer risk assessment and government regulation to protect public health; and (3) Low-level radioactive waste: can new disposal sites be found

  7. Managing low-level radioactive waste in Massachusetts. Final report

    International Nuclear Information System (INIS)

    As one of the country's largest generators of low-level radioactive waste, Massachusetts has begun independently seeking solutions to the questions surrounding low-level waste management issues. The Massachusetts Department of Public Health, Radiation Control Program, obtained funding from the U.S. Department ofEnergy through EG and G, Idaho, Inc. to develop a low-level waste management strategy for the Commonwealth. The Working Group was made up of individuals from various waste generating industries, environmental and public interest groups, medical and academic institutions, and affected state agencies. This final report document contains the following staff project reports: Proposed Low-Level Radioactive Waste Management Plan for The Commonwealth of Massachusetts, February 1983 and Low-Level Radioactive Waste Management in Massachusetts - Actions to be Considered for Implementation in 1984-1986, December 1983. These two staff reports represent the completion of the Massachusetts Low-Level Radioactive Waste Management Project. The first report provides some of the background material to the issues and some of the alternative courses of action which can be considered by state policy-makers. The second report provides the next phase in the process by delineating specific steps which may be taken before 1986 in order to address the low-level waste problem, and the estimated amount of time needed to complete each step

  8. Low-level radioactive waste disposal in the United States

    International Nuclear Information System (INIS)

    Two national systems comprise the low-level radioactive waste management system in the United States of America. The U.S. Nuclear Regulatory Commission regulates low-level radioactive waste produced in the public sector (commercial waste), and the U.S. Department of Energy manages low-level radioactive waste produced by government-sponsored programs. The primary distinction between the two national systems is the source of regulatory control. This paper discusses two issues critical to the success of each system: the site selection process used by the commercial low-level waste disposal system, and the evaluation process used to determine configuration of the DOE waste management system. The two national systems take different approaches to reach the same goals, which are increased social responsibility, protection of public health and safety, and protection of the environment

  9. Field demonstration of improved shallow land burial practices for low-level radioactive solid wastes: preliminary site characterization and progress report

    International Nuclear Information System (INIS)

    A 5-year field demonstration (ETF) of improved shallow land burial practices for low-level radioactive solid wastes in a humid environment evaluates the use of a trench liner and grout as alternate trench treatments for improving shallow land burial site performance in the humid East. The ETF is located within the Copper Creek thrust block of the Valley and Ridge Province of east Tennessee and is underlain by strata of the Middle to Late Cambrian Conasauga Group. The Maryville Limestone formation, which is composed of ribbon-bedded and interclastic limestones and dark grey shales and mudstones, comprises the bedrock immediately beneath the site. The bedrock and residuum structure are characterized by anticlinal folds with numerous joints and fractures, some of which are filled with calcite. Seismic and electrical resistivity geophysical methods were useful in characterizing the thickness of residuum and presence of structural features. Soils are illitic and range from podzolic to lithosols to alluvial in the vicinity of the ETF, but the original soil solum was removed in 1975 when the mixed hardwood forest was cleared and the site was planted in grasses. The remaining residuum consists of acidic soil aggregate and extensively weathered siltstone and sandstone which exhibit the original rock structure. Mean annual precipitation at the site is 1500 mm, although during the initial study period (10-1-80 to 9-30-81) the annual total was 939 mm. Runoff was estimated to be about 50% of the precipitation total, based on observations at two Parshall flumes installed at the site. Storm runoff is quite responsive to rainfall, and the lag time between peak rainfall and runoff is less than 15 min during winter storms. Tracer studies of the ground-water system, suggest that ground-water flow has two distinct components, one associated with fracture flow and the other with intergranular flow

  10. Shallow land burial of low-level radioactive waste

    International Nuclear Information System (INIS)

    The performance objectives included in regulations for disposal of low-level radioactive waste (10 CFR 61 for commercial waste and DOE Order 5820.2 for defense waste) are generic principles that generate technical requirements which must be factored into each phase of the development and operation of a shallow land burial facility. These phases include a determination of the quantity and characteristics of the waste, selection of a site and appropriate facility design, use of sound operating practices, and closure of the facility. The collective experience concerning shallow land burial operations has shown that achievement of the performance objectives (specifically, waste isolation and radionuclide containment) requires a systems approach, factoring into consideration the interrelationships of the phases of facility development and operation and their overall impact on performance. This report presents the technical requirements and procedures for the development and operation of a shallow land burial facility for low-level radioactive waste. The systems approach is embodied in the presentation. The report is not intended to be an instruction manual; rather, emphasis is placed on understanding the technical requirements and knowing what information and analysis are needed for making informed choices to meet them. A framework is developed for using the desired site characteristics to locate potentially suitable sites. The scope of efforts necessary for characterizing a site is then described and the range of techniques available for site characterization is identified. Given the natural features of a site, design options for achieving the performance objectives are discussed, as are the operating practices, which must be compatible with the design. Site closure is presented as functioning to preserve the containment and isolation provided at earlier stages of the development and operation of the facility

  11. ASSESSMENT OF RADIOACTIVE AND NON-RADIOACTIVE CONTAMINANTS FOUND IN LOW LEVEL RADIOACTIVE WASTE STREAMS

    Energy Technology Data Exchange (ETDEWEB)

    R.H. Little, P.R. Maul, J.S.S. Penfoldag

    2003-02-27

    This paper describes and presents the findings from two studies undertaken for the European Commission to assess the long-term impact upon the environment and human health of non-radioactive contaminants found in various low level radioactive waste streams. The initial study investigated the application of safety assessment approaches developed for radioactive contaminants to the assessment of nonradioactive contaminants in low level radioactive waste. It demonstrated how disposal limits could be derived for a range of non-radioactive contaminants and generic disposal facilities. The follow-up study used the same approach but undertook more detailed, disposal system specific calculations, assessing the impacts of both the non-radioactive and radioactive contaminants. The calculations undertaken indicated that it is prudent to consider non-radioactive, as well as radioactive contaminants, when assessing the impacts of low level radioactive waste disposal. For some waste streams with relatively low concentrations of radionuclides, the potential post-closure disposal impacts from non-radioactive contaminants can be comparable with the potential radiological impacts. For such waste streams there is therefore an added incentive to explore options for recycling the materials involved wherever possible.

  12. USDOE activities in low-level radioactive waste treatment

    International Nuclear Information System (INIS)

    This paper describes current research, development and demonstration (R, D and D) programs sponsored by the US Department of Energy in the area of low-level radioactive waste treatment. The US Department of Energy Low-Level Radioactive Waste Management Program is directed toward a coordinated program covering the period from low-level radioactive waste generation through the decommissioning of the disposal site. This paper addresses the treatment portion of the program. The development efforts include: mechanical methods for metal and compactible waste volume reduction; incineration of trash or other combustibles through the use of controlled air, cyclone, or molten glass furnaces; ultrafiltration, reverse osmosis, biological or chemical destruction of nitrates; adsorption treatment of low-concentration aqueous waste streams; combustion of organic liquids; and smelting of metal wastes to reduce their volume and conserve our natural resources. (author)

  13. Radiation Protection Research: Low-level Radioactivity Measurements

    Energy Technology Data Exchange (ETDEWEB)

    Hurtgen, C

    2000-07-01

    The objectives of the research performed in the area of low-level radioactivity measurements are (1) to maintain and develop techniques for the measurement of low-level environmental and biological samples, (2) to measure these samples by means of low-background counters (liquid scintillators, proportional counters, ZnS counters, alpha spectrometry), (3) to support and advice the nuclear and non-nuclear industry in matters concerning radioactive contamination and/or low-level radioactivity measurements; (4) to maintain the quality assurance system according to the EN45001 standard; and (5) to assess the internal dose from occupational intakes of radionuclides of workers of the nuclear industry. Progress and achievements in these areas in 1999 are reported. Particular emphasis is SCK-CEN's contribution to the EULEP-EURADOS Action Group on 'Derivation of parameter values for application in the new model of the human respiratory tract for occupational exposure'.

  14. Low-level radioactive waste management in Canada

    International Nuclear Information System (INIS)

    In Canada, all low-level radioactive wastes are presently stored. The wastes are classified into two major categories, that is, historic wastes for which the original generator/producer can no longer be held responsible and for which the federal government has assumed residual management responsibility, and ongoing wastes, which are the responsibility of the present waste producers. This paper will present the approach being taken for the management of each class of waste and will also briefly discuss the community-based, cooperative and consultative approach being used to find sites for the long-term management/disposal of historic low-level radioactive wastes

  15. Low-level radioactive material information management system. Final report

    International Nuclear Information System (INIS)

    The Southern States Energy Board (SSEB) has designed and tested a monitoring system for reporting and tracking the movement of low-level radioactive waste from generator through transporter or broker to disposal site. This demonstration project has been an attempt to show the feasibility of a system with wider regional and national scope. In conjunction with the development of this closed-loop system, a low-level waste generators' survey has been conducted in 10 pilot states to collect, analyze and present low-level waste data for state management purposes. These states are Alabama, Florida, Georgia, Maryland, Mississippi, North Carolina, South Carolina, Tennessee, Texas, and Virginia

  16. Low-level radioactive waste project. Final report

    International Nuclear Information System (INIS)

    This report summarizes work of the US Conference of Mayors project, Local Government Review of Approaches to Management of Low-Level Radioactive Wastes. The work covered the time between April 1, 1981 and September 30, 1982, and was carried out in two phases. The objective of the first phase was to have local government officials review DOE's proposed low-level radioactive waste management program strategy document. Towards this end, the Conference was to organize meetings to obtain such review, to convey information to local representatives on policy and technical issues associated with low-level waste management, and to provide EG and G Idaho, Inc. (EG and G), the operator of DOE's Idaho Operations Office, with reports on those meetings. Because of the compression of time, funds remained unspent at the end of the first phase. After discussion, both the Conference and EG and G agreed it would be mutually beneficial to re-allocate funds within categories of the original budget, and to extend the project. The purpose of the extention was to permit follow-up to issues and suggestions raised at the Strategy Review Meetings. These included the need to monitor the on-going process of implementing the Low-Level Radioactive Policy Act, and to provide more mayors with information about the issues of low-level radioative waste disposal. As agreed, the tasks under this extension have involved preparation of three information packets for mayors, and briefings for staff of other local government associations

  17. Illinois perspective on low level radioactive waste disposal

    International Nuclear Information System (INIS)

    Illinois is a big generator of low level radioactive waste. It has had extensive experience with controversial waste disposal and storage facilities. This experience makes it difficult for the public and political leaders in Illinois to support the establishment of new disposal facilities in the state. Yet, with extensive debates and discussions concerning the Low Level Waste Policy Act of 1980 and the proposed Midwest Compact, political leaders and the public are facing up to the fact that they must be responsible for the disposal of the low level radioactive waste generated in the state. The Governor and many political leaders from Illinois support the regional approach and believe it can be an innovative and progressive way for the state to deal with the range of low level waste management and disposal problems. A version of the Midwest Interstate Low Level Waste Compact has become Illinois law, but it has significant differences from the one adopted by five other states. Like other states in the midwest and northeast, Illinois is opposed to Congressional consent of the four pending compacts before the remaining two compacts, the northeast and midwest are sent to Washington and interregional agreements are negotiated between the sited and non-sited regions. A new national system must be established before access to existing commercial disposal becomes restricted

  18. Low-level radioactive waste research program plan

    International Nuclear Information System (INIS)

    The Waste Management Branch, Division of Engineering, Office of Nuclear Regulatory Research, has developed a strategy for conducting research on issues of concern to the US Nuclear Regulatory Commission (NRC) in its efforts to ensure safe disposal of low-level radioactive waste (LLW). The resulting LLW research program plan provides an integrated framework for planning the LLW research program to ensure that the program and its products are responsive and timely for use in NRC's LLW regulatory program. The plan discusses technical and scientific issues and uncertainties associated with the disposal of LLW, presents programmatic goals and objectives for resolving them, establishes a long-term strategy for conducting the confirmatory and investigative research needed to meet these goals and objectives, and includes schedules and milestones for completing the research. Areas identified for investigation include waste form and other material concerns, failure mechanisms and radionuclide releases, engineered barrier performance, site characterization and monitoring, and performance assessment. The plan proposes projects that (1) analyze and test actual LLW and solidified LLW under laboratory and field conditions to determine leach rates and radionuclide releases, (2) examine the short- and long-term performance of concrete-enhanced LLW burial structures and high-integrity containers, and (3) attempt to predict water movement and contaminant transport through low permeability saturated media and unsaturated porous media. 4 figs., 3 tabs

  19. Treatment of low-level radioactive waste using Volcanic ash

    International Nuclear Information System (INIS)

    The effective application of volcanic ash, an indigenous adsorptive material abundant in the Mt. Pinatubo area, in the removal of radioiodine from radioactive waste streams was demonstrated. Factors such as availability, low cost and comparative retention capacity with respect to activated charcoal make volcanic ash an attractive alternative in the conditioning of radioactive waste containing radioiodine. Chemical precipitation was employed in the treatment of low level aqueous waste containing 137Cs. It was shown that there exists an optimum concentration of ferric ion that promotes maximum precipitation of caesium. It was further demonstrated that complete removal of caesium can be achieved with the addition of nickel hexacyanoferrate. (author). 5 refs, 3 figs

  20. A robotic inspector for low-level radioactive waste

    International Nuclear Information System (INIS)

    The Department of Energy has low-level radioactive waste stored in warehouses at several facilities. Weekly visual inspections are required. A mobile robot inspection system, ARIES (Autonomous Robotic Inspection Experimental System), has been developed to survey and inspect the stored drums. The robot will travel through the three-foot wide aisles of drums stacked four high and perform a visual inspection, normally performed by a human operator, making decisions about the condition of the drums and maintaining a database of pertinent information about each drum. This mobile robot system will improve the quality of inspection, generate required reports, and relieve human operators from low-level radioactive exposure. 4 refs., 3 figs

  1. Siting the North Carolina Low-Level Radioactive Waste Facility

    Energy Technology Data Exchange (ETDEWEB)

    Walker, C.K.; MacMillan, J.H. [N.C. Low-Level Radioactive Waste Management Authority, Raleigh, NC (United States)

    1994-12-31

    On December 8, 1993, the North Carolina Low-Level Radioactive Waste Management Authority selected a site in Wake County as the preferred site for the North Carolina low-level radioactive waste disposal facility. This facility will replace the Southeast Compact`s current facility in Barnwell, South Carolina. Five days later, the Authority`s contractors, Chem-Nuclear Systems, Inc., filed a license application for the facility. These two actions culminated six years of work by the Authority and constitute the achievement of a major milestone in the project. Work leading up to this point included field studies, facility design, performance assessment calculations, and a variety of public outreach activities. Pending regulatory approval of the license application, North Carolina is scheduled to open the Southeast Compact`s second LLRW disposal facility in January 1996.

  2. Low-level radioactive waste management by states and compacts

    International Nuclear Information System (INIS)

    The Low-Level Radioactive Waste Policy Amendments Act of 1985 (the Act) provided 7 years of interim access to the disposal sites operating in Nevada, South Carolina, and Washington, Today, nearly 5 years later, we are beginning to speculate on the status of States and Compacts at the end of interim access, which is scheduled by law for January 1, 1993. In theory, by then, our job of developing a new regionally based, national low-level waste disposal system should be completed. Upon examining the evidence of progress so far, I conclude that as a Nation, we have a long way to go. An acceleration of efforts may help to put us back on schedule, but it does not look promising. The purpose of this paper it to summarize the current status of low-level waste management nationwide, and to reflect on the difficult challenges the lie ahead in developing an effective nationwide system for the next few years

  3. Low-level radioactive waste management: an economic assessment

    International Nuclear Information System (INIS)

    This paper has presented an overview of the economics of low-level radioactive waste disposal. It is hoped that this paper will assist the states in their efforts to determine their approach to the management of low-level wastes. Although the economies of scale realized by a larger facility are emphasized, the conclusion is that every state and region must examine its need for low-level waste disposal services and consider the interrelated factors that affect the volume of waste to be disposed, including waste reduction techniques, interim storage for not a single recommended capacity for a facility, but an acknowledgement of contingencies. In theory, per cubic foot disposal costs decrease as facility size increases. But theory does not preclude a state from constructing its own site, or a region generating small volumes of waste from building a shared facility. All factors should be weighed before a site is chosen and its size is determined

  4. Commercial low-level radioactive waste disposal in the US

    Energy Technology Data Exchange (ETDEWEB)

    Smith, P.

    1995-10-01

    Why are 11 states attempting to develop new low-level radioactive waste disposal facilities? Why is only on disposal facility accepting waste nationally? What is the future of waste disposal? These questions are representative of those being asked throughout the country. This paper attempts to answer these questions in terms of where we are, how we got there, and where we might be going.

  5. Commercial low-level radioactive waste disposal in the US

    International Nuclear Information System (INIS)

    Why are 11 states attempting to develop new low-level radioactive waste disposal facilities? Why is only on disposal facility accepting waste nationally? What is the future of waste disposal? These questions are representative of those being asked throughout the country. This paper attempts to answer these questions in terms of where we are, how we got there, and where we might be going

  6. Low-level radioactive waste technology: a selected, annotated bibliography

    Energy Technology Data Exchange (ETDEWEB)

    Fore, C.S.; Vaughan, N.D.; Hyder, L.K.

    1980-10-01

    This annotated bibliography of 447 references contains scientific, technical, economic, and regulatory information relevant to low-level radioactive waste technology. The bibliography focuses on environmental transport, disposal site, and waste treatment studies. The publication covers both domestic and foreign literature for the period 1952 to 1979. Major chapters selected are Chemical and Physical Aspects; Container Design and Performance; Disposal Site; Environmental Transport; General Studies and Reviews; Geology, Hydrology and Site Resources; Regulatory and Economic Aspects; Transportation Technology; Waste Production; and Waste Treatment. Specialized data fields have been incorporated into the data file to improve the ease and accuracy of locating pertinent references. Specific radionuclides for which data are presented are listed in the Measured Radionuclides field, and specific parameters which affect the migration of these radionuclides are presented in the Measured Parameters field. In addition, each document referenced in this bibliography has been assigned a relevance number to facilitate sorting the documents according to their pertinence to low-level radioactive waste technology. The documents are rated 1, 2, 3, or 4, with 1 indicating direct applicability to low-level radioactive waste technology and 4 indicating that a considerable amount of interpretation is required for the information presented to be applied. The references within each chapter are arranged alphabetically by leading author, corporate affiliation, or title of the document. Indexes are provide for (1) author(s), (2) keywords, (3) subject category, (4) title, (5) geographic location, (6) measured parameters, (7) measured radionuclides, and (8) publication description.

  7. Low-level radioactive waste technology: a selected, annotated bibliography

    International Nuclear Information System (INIS)

    This annotated bibliography of 447 references contains scientific, technical, economic, and regulatory information relevant to low-level radioactive waste technology. The bibliography focuses on environmental transport, disposal site, and waste treatment studies. The publication covers both domestic and foreign literature for the period 1952 to 1979. Major chapters selected are Chemical and Physical Aspects; Container Design and Performance; Disposal Site; Environmental Transport; General Studies and Reviews; Geology, Hydrology and Site Resources; Regulatory and Economic Aspects; Transportation Technology; Waste Production; and Waste Treatment. Specialized data fields have been incorporated into the data file to improve the ease and accuracy of locating pertinent references. Specific radionuclides for which data are presented are listed in the Measured Radionuclides field, and specific parameters which affect the migration of these radionuclides are presented in the Measured Parameters field. In addition, each document referenced in this bibliography has been assigned a relevance number to facilitate sorting the documents according to their pertinence to low-level radioactive waste technology. The documents are rated 1, 2, 3, or 4, with 1 indicating direct applicability to low-level radioactive waste technology and 4 indicating that a considerable amount of interpretation is required for the information presented to be applied. The references within each chapter are arranged alphabetically by leading author, corporate affiliation, or title of the document. Indexes are provide for (1) author(s), (2) keywords, (3) subject category, (4) title, (5) geographic location, (6) measured parameters, (7) measured radionuclides, and (8) publication description

  8. Status of low-level radioactive waste management in Korea

    Energy Technology Data Exchange (ETDEWEB)

    Lee, K.J. [Korea Advanced Inst. of Science and Technology, Taejon (Korea, Republic of). Dept. of Nuclear Engineering

    1993-03-01

    The Republic of Korea has accomplished dramatic economic growth over the past three decades; demand for electricity has rapidly grown more than 15% per year. Since the first nuclear power plant, Kori-1 [587 MWe, pressurized water reactor (PWR)], went into commercial operation in 1978, the nuclear power program has continuously expanded and played a key role in meeting the national electricity demand. Nowadays, Korea has nine nuclear power plants [eight PWRs and one Canadian natural uranium reactor (CANDU)] in operation with total generating capacity of 7,616 MWe. The nuclear share of total electrical capacity is about 36%; however, about 50% of actual electricity production is provided by these nine nuclear power plants. In addition, two PWRs are under construction, five units (three CANDUs and two PWRs) are under design, and three more CANDUs and eight more PWRs are planned to be completed by 2006. With this ambitious nuclear program, the total nuclear generating capacity will reach about 23,000 MWe and the nuclear share will be about 40% of the total generating capacity in the year 2006. In order to expand the nuclear power program this ambitiously, enormous amounts of work still have to be done. One major area is radioactive waste management. This paper reviews the status of low-level radioactive waste management in Korea. First, the current and future generation of low-level radioactive wastes are estimated. Also included are the status and plan for the construction of a repository for low-level radioactive wastes, which is one of the hot issues in Korea. Then, the nuclear regulatory system is briefly mentioned. Finally, the research and development activities for LLW management are briefly discussed.

  9. Disposal of low-level and mixed low-level radioactive waste during 1990

    Energy Technology Data Exchange (ETDEWEB)

    1993-08-01

    Isotopic inventories and other data are presented for low-level radioactive waste (LLW) and mixed LLW disposed (and occasionally stored) during calendar year 1990 at commercial disposal facilities and Department of Energy (DOE) sites. Detailed isotopic information is presented for the three commercial disposal facilities located near Barnwell, SC, Richland, WA, and Beatty, NV. Less information is presented for the Envirocare disposal facility located near Clive, UT, and for LLW stored during 1990 at the West Valley site. DOE disposal information is included for the Savannah River Site (including the saltstone facility), Nevada Test Site, Los Alamos National Laboratory, Idaho National Engineering Laboratory, Hanford Site, Y-12 Site, and Oak Ridge National Laboratory. Summary information is presented about stored DOE LLW. Suggestions are made about improving LLW disposal data.

  10. Environmental monitoring of low-level radioactive waste disposal facility

    International Nuclear Information System (INIS)

    This branch technical position (BTP) paper on the environmental monitoring program for a low-level radioactive waste disposal facility provides general guidance on what is required by Section 61.53 of Title 10 of the Code of Federal Regulations (10 CFR) of applicants submitting a license application for such a facility. In general, the environmental monitoring program consists of three phases: preoperational, operational, and postoperational. Each phase of the monitoring program should be designed to fulfill the specific objectives defined in the BTP paper. During the preoperational phase, the objectives of the program are to provide site characterization information, to demonstrate site suitability and acceptability, to obtain background or baseline information, and to provide a record for public information. During the operational phase, the emphasis on measurement shifts. Monitoring data are obtained to provide early warning of releases and to document compliance with regulations, the dose limits of 10 CFR Part 61, or applicable standards of the US Environmental Protection Agency. Data are also used to update important pathway parameters to improve predictions of site performance and to provide a record of performance for public information. The postoperational environmental monitoring program emphasizes measurements to demonstrate compliance with the site-closure requirements and continued compliance with the performance objective in regard to the release of radionuclides to the environment. The data are used to support evaluation of long-term effects on the general public and for public information. Guidance is also provided in the BTP paper on the choice of which constituents to measure, setting action levels, relating measurements to appropriate actions in a corrective action plan, and quality assurance

  11. Low-level radioactive waste research program plant

    International Nuclear Information System (INIS)

    The Office of Nuclear Regulatory Research, has developed a strategy for conducting research on issues of concern to the U.S. Nuclear Regulatory Commission (NRC) in its efforts to ensure safe disposal of low-level radioactive waste (LLW). The program plan has been published in NUREG-1380, and provides an integrated framework to ensure that the program and its products are responsive and timely. The plan addresses technical and scientific issues and uncertainties associated with the disposal of LLW, presents goals and ways for achieving them, establishes a long-term strategy for the confirmatory and investigative research needed and includes schedules and milestones for completion. Areas for investigation include waste form and other material concerns, failure mechanisms and radionuclide releases, engineered barrier performance, site characterization and monitoring, and performance assessment. The plan includes projects that (1) analyze and test actual LLW and solidified LLW under laboratory and field conditions to determine leach rates and radionuclide releases, (2) examine the radiological and chemical characteristics of decommissioning waste from Nuclear power stations, (3) examine the short- and long-term performance of concrete-enhanced LLW burial structures and high-integrity containers, (4) investigate the long term effectiveness of disposal unit covers in controlling water infiltration into disposal units, (5) examine the information needed at time of closure for predicting future facility performance, (6) attempt to develop a predictive model of the rate of radionuclide release at the boundary of waste disposal units, (7) examine radionuclide transport behavior, pathways, uptake, and transfer coefficients of radionuclide releases from LLW disposal facilities, and (8) attempt to predict water movement and contaminant transport through low permeability saturated media and unsaturated porous media. 1 fig

  12. Managing low-level radioactive wastes: a proposed approach

    International Nuclear Information System (INIS)

    In 1978, President Carter established the Interagency Review Group on Nuclear Waste Management (IRG) to review the nation's plans and progress in managing radioactive wastes. In its final report, issued in March 1979, the group recommended that the Department of Energy (DOE) assume responsibility for developing a national plan for the management of low-level wastes. Toward this end, DOE directed that a strategy be developed to guide federal and state officials in resolving issues critical to the safe management of low-level wastes. EG and G Idaho, Inc. was selected as the lead contractor for the Low-Level Waste Management Program and was given responsibility for developing the strategy. A 25 member task force was formed which included individuals from federal agencies, states, industry, universities, and public interest groups. The task force identified nineteen broad issues covering the generation, treatment, packaging, transportation, and disposal of low-level wastes. Alternatives for the resolution of each issue were proposed and recommendations were made which, taken together, form the draft strategy. These recommendations are summarized in this document

  13. Issues in the management of low-level radioactive wastes

    International Nuclear Information System (INIS)

    All industry finds itself today enmeshed in a morass of regulation, political apathy and public antagonism when it comes to hazardous industrial waste. Our industry is a world-class leader on all three fronts. There are no disposal facilities in Canada for radioactive wastes and the prognosis for the future is bleak. As the industry gets older, more and more facilities will be closed and require decommissioning. New facilities require plans for the long-term management of their wastes. Indeed, one major public issue with the nuclear industry is the fate of the wastes produced. In looking at the situation in which we find ourselves today with respect to the long-term management of naturally-occurring low-level radioactive wastes, one must wonder where we are going in the future, and whether indeed is an end in sight

  14. Incineration of Low Level Radioactive Vegetation for Waste Volume Reduction

    International Nuclear Information System (INIS)

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

  15. Management of low-level radioactive wastes around the world

    International Nuclear Information System (INIS)

    This paper reviews the status of various practices used throughout the world for managing low-level radioactive wastes. Most of the information in this review was obtained through the DOE-sponsored International Program Support Office (IPSO) activities at Pacific Northwest Laboratory (PNL) at Richland, Washington. The objective of IPSO is to collect, evaluate, and disseminate information on international waste management and nuclear fuel cycle activities. The center's sources of information vary widely and include the proceedings of international symposia, papers presented at technical society meetings, published topical reports, foreign trip reports, and the news media. Periodically, the information is published in topical reports. Much of the information contained in this report was presented at the Fifth Annual Participants' Information Meeting sponsored by DOE's Low-Level Waste Management Program Office at Denver, Colorado, in September of 1983. Subsequent to that presentation, the information has been updated, particularly with information provided by Dr. P. Colombo of Brookhaven National Laboratory who corresponded with low-level waste management specialists in many countries. The practices reviewed in this paper generally represent actual operations. However, major R and D activities, along with future plans, are also discussed. 98 refs., 6 tabls

  16. Management of low-level radioactive wastes around the world

    Energy Technology Data Exchange (ETDEWEB)

    Lakey, L.T.; Harmon, K.M.; Colombo, P.

    1985-04-01

    This paper reviews the status of various practices used throughout the world for managing low-level radioactive wastes. Most of the information in this review was obtained through the DOE-sponsored International Program Support Office (IPSO) activities at Pacific Northwest Laboratory (PNL) at Richland, Washington. The objective of IPSO is to collect, evaluate, and disseminate information on international waste management and nuclear fuel cycle activities. The center's sources of information vary widely and include the proceedings of international symposia, papers presented at technical society meetings, published topical reports, foreign trip reports, and the news media. Periodically, the information is published in topical reports. Much of the information contained in this report was presented at the Fifth Annual Participants' Information Meeting sponsored by DOE's Low-Level Waste Management Program Office at Denver, Colorado, in September of 1983. Subsequent to that presentation, the information has been updated, particularly with information provided by Dr. P. Colombo of Brookhaven National Laboratory who corresponded with low-level waste management specialists in many countries. The practices reviewed in this paper generally represent actual operations. However, major R and D activities, along with future plans, are also discussed. 98 refs., 6 tabls.

  17. Cement encapsulation of low-level radioactive slurries of complex chemistry

    International Nuclear Information System (INIS)

    Investigations have been carried out to solidify in cement a low-level radioactive waste of complex chemistry which should be produced in a new plant designed to process radioactive effluents from CEA Cadarache Research Center. Direct cementation comes up against a major problem: a very long setting time of cement due to strong inhibition by borates from the waste. A two-stage process, including a chemical treatment prior to immobilization, has been elaborated and the resulted material characterized. (authors)

  18. Cement encapsulation of low-level radioactive slurries of complex chemistry

    Energy Technology Data Exchange (ETDEWEB)

    Cau Dit Coumes, C. [CEA/Cadarache, Dept. d' Entreposage et de Stockage des Dechets (DESD), 13 - Saint-Paul-lez-Durance (France)

    2000-07-01

    Investigations have been carried out to solidify in cement a low-level radioactive waste of complex chemistry which should be produced in a new plant designed to process radioactive effluents from CEA Cadarache Research Center. Direct cementation comes up against a major problem: a very long setting time of cement due to strong inhibition by borates from the waste. A two-stage process, including a chemical treatment prior to immobilization, has been elaborated and the resulted material characterized. (authors)

  19. Thirteenth annual U.S. DOE low-level radioactive waste management conference: Proceedings

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1991-12-31

    The 40 papers in this document comprise the proceedings of the Department of Energy`s Thirteenth Annual Low-Level Radioactive Waste Management Conference that was held in Atlanta, Georgia, on November 19--21, 1991. General subjects addressed during the conference included: disposal facility design; greater-than-class C low-level waste; public acceptance considerations; waste certification; site characterization; performance assessment; licensing and documentation; emerging low-level waste technologies; waste minimization; mixed waste; tracking and transportation; storage; and regulatory changes. Papers have been processed separately for inclusion on the data base.

  20. Risk-based financial assurance for low-level radioactive waste disposal facilities

    International Nuclear Information System (INIS)

    The paper presents a risk assessment to characterize the potential for liability costs associated with a facility for disposal of low-level radioactive waste (LLRW). Potential liability costs are grouped into two categories: corrective action costs (e.g., for cleanup of property and the environment) and third-party compensation costs (e.g., for bodily injury and property damage)

  1. AECL experience with low-level radioactive waste technologies

    International Nuclear Information System (INIS)

    Atomic Energy of Canada Limited (AECL), as the Canadian government agency responsible for research and development of peaceful uses of nuclear energy, has had experience in handling a wide variety of radioactive wastes for over 40 years. Low-level radioactive waste (LLRW) is generated in Canada from nuclear fuel manufacturers and nuclear power facilities, from medical and industrial uses of radioisotopes and from research facilities. The technologies with which AECL has strength lie in the areas of processing, storage, disposal and safety assessment of LLRW. While compaction and incineration are the predominant methods practised for solid wastes, purification techniques and volume reduction methods are used for liquid wastes. The methods for processing continue to be developed to improve and increase the efficiency of operation and to accommodate the transition from storage of the waste to disposal. Site-specific studies and planning for a LLRW disposal repository to replace current storage facilities are well underway with in-service operation to begin in 1991. The waste will be disposed of in an intrusion-resistant underground structure designed to have a service life of over 500 years. Beyond this period of time the radioactivity in the waste will have decayed to innocuous levels. Safety assessments of LLRW disposal are performed with the aid of a series of interconnected mathematical models developed at Chalk River specifically to predict the movement of radionuclides through and away from the repository after its closure and the subsequent health effects of the released radionuclides on the public. The various technologies for dealing with radioactive wastes from their creation to disposal will be discussed. 14 refs

  2. Disposal of low-level radioactive waste at Drigg

    International Nuclear Information System (INIS)

    In 1985-86 an inquiry into the disposal of radioactive waste in the United Kingdom was conducted. In 1985, the low-level waste [LLW] site at Drigg which is owned and operated by British Nuclear Fuels plc [BNFL] was visited. A series of trenches dug into glacial clay about eight metres deep into which a miscellany of rubbish-some in drums, some raw-was tipped, with a rough and ready check on total daily radioactivity of the material and no attempt at analysis of content was seen. When filled, the trench was covered over with soil; and water accumulating in it was allowed to run off into the Drigg stream and eventually into the Irish Sea. If the monitoring of the stream one day revealed a high level of radioactivity nothing could have been done about it, since pinpointing the offending waste would be impossible. Recommendations as set out in Appendix I to the present Report, were made. The recommendations were accepted virtually in their entirety. Drigg was re-visited in June 1989. In place of the open clay trenches, carefully-engineered concrete bunkers to receive metal containers were found. Sampling equipment has been installed on-site and all waste arriving at Drigg from non-Sellafield sources is placed in an approved container, which is carefully labelled and its ultimate destination carefully recorded. Insofar as the old trenches are concerned, these have been isolated by the construction of a groundwater cut-off wall designed to prevent lateral movement of contaminants from the trenches. Significant reductions had been achieved by BNFL for radioactive emissions from the site as a whole. Large sums have been spent on achieving this. Discharges of alpha and beta radiation are now around one per cent of the peak discharges of the 1970s and monitoring of shellfish has confirmed that this has been carried forward into a reduced exposure for the public. (author)

  3. Disposal of low-level radioactive waste at Drigg

    International Nuclear Information System (INIS)

    In 1985-86 an inquiry was conducted into the disposal of radioactive waste in the United Kingdom. In April 1985, during that inquiry, the low-level waste (LLW) site at Drigg which is owned and operated by British Nuclear Fuels plc (BNFL) was visited. A series of trenches dug into glacial clay about eight metres deep contained a miscellany of rubbish - some in drums, some raw - with but a rough and ready check on total daily radioactivity of the material and no attempt at analysis of content. When filled, the trench was covered over with soil; and water accumulating in it was allowed to run off into the Drigg stream and eventually into the Irish Sea. If the monitoring of the stream one day revealed a high level of radioactivity nothing could have been done about it, since pinpointing the offending waste would be impossible. Recommendations as set out in Appendix I to the present Report, were made. Recommendations were accepted virtually in their entirety; measures would be taken to meet criticisms of what was seen. Drigg was revisited in June 1989. The solid waste encapsulation plant (EP1) which is currently nearing completion at Sellafield was also seen. Carefully-engineered concrete bunkers to receive metal containers replaced open clay trenches. Sampling equipment has been installed on-site and all waste arriving at Drigg from non-Sellefield sources is placed in an approved container, which is carefully labelled and its ultimate destination carefully recorded. Insofar as the old trenches are concerned, these have been isolated by the construction of a groundwater cut-off wall designed to prevent lateral movement of contaminants from the trenches. Significant reductions have been achieved by BNFL for radioactive emissions from the site as a whole. Large sums have been spent on achieving this. (author)

  4. Low-level radioactive waste technology: a selected, annotated bibliography

    International Nuclear Information System (INIS)

    This annotated bibliography of 416 references represents the third in a series to be published by the Hazardous Materials Information Center containing scientific, technical, economic, and regulatory information relevant to low-level radioactive waste technology. The bibliography focuses on disposal site, environmental transport, and waste treatment studies as well as general reviews on the subject. The publication covers both domestic and foreign literature for the period 1951 to 1981. Major chapters selected are Chemical and Physical Aspects; Container Design and Performance; Disposal Site; Environmental Transport; General Studies and Reviews; Geology, Hydrology, and Site Resources; Regulatory and Economic Aspects; Social Aspects; Transportation Technology; Waste Production; and Waste Treatment. Entries in each of the chapters are further classified as a field study, laboratory study, theoretical study, or general overview involving one or more of these research areas

  5. Soil gas surveying at low-level radioactive waste sites

    Energy Technology Data Exchange (ETDEWEB)

    Crockett, A.B.; Moor, K.S.; Hull, L.C. [EG and G Idaho Inc., Idaho Falls, ID (United States). Idaho National Engineering Lab.

    1989-11-01

    Soil gas sampling is a useful screening technique for determining whether volatile organic compounds are present at low-level radioactive waste burial sites. The technique was used at several DOE sites during the DOE Environmental Survey to determine the presence and extent of volatile organic compound contamination. The advantages of the soil gas sampling are that near real time data can be obtained, no excavation is required, safety concerns are relatively minor, costs are relatively low, and large amounts of data can be obtained rapidly on the contaminants that may pose the greatest threat to groundwater resources. The disadvantages are that the data are difficult to interpret and relate to soil concentrations and environmental standards. This paper discusses the experiences of INEL sampling and analysis personnel, the advantages and disadvantages of the technique, and makes recommendations for improving the sampling and analytical procedures.

  6. Low-level radioactive waste minimization for health care institutions

    International Nuclear Information System (INIS)

    In recent years medical waste has been the subject of considerable public and governmental attention. This has been, in part, due to the media's attraction to unfortunate instances of environmental pollution caused by hazardous and medical wastes. While a considerable amount of information is currently available on the treatment and disposal practices for hazardous wastes, a shortfall of information exists on the subject of medical wastes. Such wastes are generated by various health care institutions. Medical waste is a wide and all encompassing term which refers to a variety of wastes. This presentation addresses medical low-level (LLW) radioactive waste; its generation, recovery and handling. The development of generic waste minimization models and greater use of alternative technologies are part of the discussion

  7. 78 FR 59729 - Final Comparative Environmental Evaluation of Alternatives for Handling Low-Level Radioactive...

    Science.gov (United States)

    2013-09-27

    ... COMMISSION Final Comparative Environmental Evaluation of Alternatives for Handling Low-Level Radioactive... the Final Comparative Environmental Evaluation of Alternatives for Handling Low-Level Radioactive Waste Spent Ion Exchange Resins from Commercial Nuclear Power Reactors (Final Report). ADDRESSES:...

  8. 1992 annual report on low-level radioactive waste management progress

    International Nuclear Information System (INIS)

    This report summarizes the progress States and compact regions made during 1992 in establishing new low-level radioactive waste disposal facilities. It also provides summary information on the volume of low-level radioactive waste received for disposal in 1992 by commercially operated low-level radioactive waste disposal facilities. This report is in response to section 7 (b) of the Low-Level Radioactive Waste Policy Act

  9. Commercial low-level radioactive waste transportation liability and radiological risk

    International Nuclear Information System (INIS)

    This report was prepared for States, compact regions, and other interested parties to address two subjects related to transporting low-level radioactive waste to disposal facilities. One is the potential liabilities associated with low-level radioactive waste transportation from the perspective of States as hosts to low-level radioactive waste disposal facilities. The other is the radiological risks of low-level radioactive waste transportation for drivers, the public, and disposal facility workers

  10. Low-level radioactive waste transportation safety history

    International Nuclear Information System (INIS)

    The Radioactive Materials Incident Report (RMIR) database was developed fin 1981 at the Transportation Technology Center of Sandia National Laboratories to support its research and development activities for the US department of Energy (DOE). This database contains information about radioactive material (RAM) transportation incidents that have occurred in the US since 1971. These data were drawn from the US Department of Transportation's (DOT) Hazardous Materials Incident Report system, from Nuclear Regulatory Commission (NRC) files, and from various agencies including state radiological control offices. Support for the RMIR data base is funded by the US DOE National Transportation Program (NTP). Transportation events in RMIR are classified in one of the following ways: as a transportation accident, as a handling accident, or as a reported incident. This presentation will provide definitions for these classifications and give examples of each. The primary objective of this presentation is to provide information on nuclear materials transportation accident/incident events involving low-level waste (LLW) that have occurred in the US for the period 1971 through 1996. Among the areas to be examined are: transportation accidents by mode, package response during accidents, and an examination of accidents where release of contents has occurred. Where information is available, accident and incident history and package response for LLW packages in transportation accidents will be described

  11. Overview of management of low level radioactive wastes in Canada

    International Nuclear Information System (INIS)

    In Canada, the programme for the management of low level radioactive wastes is one of continued reliance on interim storage methods while putting in place the policies, regulations and technologies for the transition to permanent disposal which should begin early in the 1990s. The Canadian regulatory authority has issued a policy statement on the objectives, requirements and guidelines for the disposal of radioactive wastes and has proposed a basis for the identification of a de minimis category. The regulations impose a maximum annual risk of 10-6 and are directed at minimizing the burden placed on future generations as well as protecting human health and the environment. Several conceptual and site specific repositories have been designed and evaluated by the major producers in Canada. Proposals for the disposal of uranium contaminated wastes, which comprise the majority of the existing inventory, encountered strong public opposition to suggested sites. This led to the formation of a federal task force which has recommended a community driven siting process. Little opposition has been evident, however, to the operation of most of the existing storage sites for the wastes continuing to arise from the nuclear industry. Processing and storage techniques are being further developed to improve their efficiency. Also, funding for the construction of the first prototype disposal vault has been committed. (author). 22 refs, 1 tab

  12. Low-level radioactive wastes in subsurface soils

    International Nuclear Information System (INIS)

    Low-level radioactive wastes will continue to be buried in shallow-land waste disposal sites. Several of the burial sites have been closed because of the problems that developed as a result of poor site characteristics, types of waste buried, and a number of other environmental factors. Some of the problems encountered can be traced to the activities of microorganisms. These include microbial degradation of waste forms resulting in trench cover subsidence, production of radioactive gases, and production of microbial metabolites capable of complexation, solubilization, and bioaccumulation of radionuclides. Improvements in disposal technology are being developed to minimize these problems. These include waste segregation, waste pretreatment, incineration, and solidification. Microorganisms are also known to enhance and inhibit the movement of metals. Little is known about the role of autotrophic microbial transformations of radionuclides. Such microbial processes may be significant in light of improved disposal procedures, which may result in reductions in the organic content of the waste disposed of at shallow-land sites. 102 references, 5 figures, 19 tables

  13. Microbial degradation of low-level radioactive waste

    International Nuclear Information System (INIS)

    The Nuclear Regulatory Commission stipulates that disposed low-level radioactive waste (LLW) be stabilized. Because of apparent ease of use and normal structural integrity, cement has been widely used as a binder to solidify LLW. However, the resulting waste forms are sometimes susceptible to failure due to the actions of waste constituents, stress, and environment. This report reviews laboratory efforts that are being developed to address the effects of microbiologically influenced chemical attack on cement-solidified LLW. Groups of microorganisms are being employed that are capable of metabolically converting organic and inorganic substrates into organic and mineral acids. Such acids aggressively react with cement and can ultimately lead to structural failure. Results on the application of mechanisms inherent in microbially influenced degradation of cement-based material are the focus of this report. Sufficient data-validated evidence of the potential for microbially influenced deterioration of cement-solidified LLW has been developed during the course of this study. These data support the continued development of appropriate tests necessary to determine the resistance of cement-solidified LLW to microbially induced degradation that could impact the stability of the waste form. They also justify the continued effort of enumeration of the conditions necessary to support the microbiological growth and population expansion

  14. Selected radionuclides important to low-level radioactive waste management

    International Nuclear Information System (INIS)

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

  15. Selected radionuclides important to low-level radioactive waste management

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-11-01

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

  16. Technical issues in licensing low-level radioactive waste facilities

    Energy Technology Data Exchange (ETDEWEB)

    Junkert, R. [California Dept. of Health Services, CA (United States)

    1993-03-01

    The California Department of Health Service spent two years in the review of an application for a low-level radioactive waste disposal facility in California. During this review period a variety of technical issues had to be evaluated and resolved. One of the first issues was the applicability and use of NRC guidance documents for the development of LLW disposal facilities. Other technical issues that required intensive evaluations included surface water hydrology, seismic investigation, field and numerical analysis of the unsaturated zone, including a water infiltration test. Source term verification became an issue because of one specific isotope that comprised more than 90% of the curies projected for disposal during the operational period. The use of trench liners and the proposed monitoring of the unsaturated zone were reviewed by a highly select panel of experts to provide guidance on the need for liners and to ensure that the monitoring system was capable of monitoring sufficient representative areas for radionuclides in the soil, soil gas, and soil moisture. Finally, concerns about the quality of the preoperational environmental monitoring program, including data, sample collection procedures, laboratory analysis, data review and interpretation and duration of monitoring caused a significant delay in completing the licensing review.

  17. Extended storage of low-level radioactive waste: an update

    International Nuclear Information System (INIS)

    If a state or regional compact does not have adequate disposal capacity for low-level radioactive waste (LLRW), then extended storage of certain LLRW may be necessary. The Nuclear Regulatory Commission (NRC) has contracted with Brookhaven National Laboratory to address the technical issues of extended storage. The dual objectives of this study are (1) to provide practical technical assessments for NRC to consider in evaluating specific proposals for extended storage and (2) to help ensure adequate consideration by NRC, Agreement States, and licensees of potential problems that may arise from existing or proposed extended storage practices. The circumstances under which extended storage of LLRW would most likely result in problems during or after the extended storage period are considered and possible mitigative measures to minimize these problems are discussed. These potential problem areas include: (1) the degradation of carbon steel and polyethylene containers during storage and the subsequent need for repackaging (resulting in increased occupational exposure), (2) the generation of hazardous gases during storage, and (3) biodegradative processes in LLRW

  18. Surface encapsulation process for managing low-level radioactive wastes

    International Nuclear Information System (INIS)

    Current processes for low-level radioactive waste (LLRW) stabilization involve mixing contaminants with a fixative such as cement, asphalt, polyethylene, or vinyl monomers, and subsequently curing the mixtures in containers. These methods give rise to processing difficulties and yield products lacking performance to assure long-term LLRW immobilization. Mixing of LLRW into fixatives is impeded by viscous media and the curing reaction is inhibited by LLRW constituents. Product performance is affected by corrosion of the containers which ultimately expose the cured mixtures to environmental stresses. This process, termed the ''Surface Encapsulation Process,'' circumvents these problems. A thermosetting fixative is employed that mixes readily with LLRW and is highly insensitive to inhibition in curing. The agglomerated mixtures are further stabilized by encapsulation with seamless jackets of corrosion resistant plastic, such as polyethylene. In laboratory-scale investigations, feasibility of the technique was demonstrated for managing a broad spectrum of LLRW simulants including ion-exchange resins, beads, and glasses, and sodium salts. Products tested to date meet all relevant NRC and DOT regulations governing waste fixation. The high waste loadings of the products, use of commodity resins, and processing simplicity indicated our process would provide high performance LLRW stabilization at costs that are competitive to those for processes employing state-of-the-art fixatives. An economic analysis based on managing LLRW generated by commercial power plants (≅1,000 MeW) substantiates the competitive process costs advantages

  19. Life-Cycle Cost Study for a Low-Level Radioactive Waste Disposal Facility in Texas

    International Nuclear Information System (INIS)

    This report documents the life-cycle cost estimates for a proposed low-level radioactive waste disposal facility near Sierra Blanca, Texas. The work was requested by the Texas Low-Level Radioactive Waste Disposal Authority and performed by the National Low-Level Waste Management Program with the assistance of Rogers and Associates Engineering Corporation

  20. Cover technology demonstration for low-level radioactive sites

    International Nuclear Information System (INIS)

    The performance of a shallow land burial site in isolating low-level radioactive and mixed waste is strongly influenced by the behavior of the precipitation falling on the site. Predicting the long-term integrity of a cover design requires a knowledge of the water balance dynamics, and the use of predictive models. The multiplicity of factors operating on a site in the years post-closure (precipitation intensity and duration, soil conditions, vegetation seasonality and variability) have made it extremely difficult to predict the effects of natural precipitation with accuracy. Preliminary results are presented on a three-year field demonstration at Los Alamos National Laboratory to evaluate the influence of different waste trench cap designs on water balance under natural precipitation. Erosion plots having two different vegetative covers (shrubs and grasses) and with either gravel-mulched or unmulched soil surface treatments have been established on three different soil profiles on an inactive waste site. Total runoff and soil loss from each plot are measured biweekly while plant canopy cover is measured seasonally. Preliminary results from the first year show that the application of a gravel mulch reduced runoff by 73 to 90%. Total soil loss was reduced by 83 to 93% by the mulch treatment. On unmulched plots, grass cover reduced both runoff and soil loss by about 50% compared to the shrub plots. Soil moisture reduction during the growing season was more pronounced on the shrub plots. This indicates that a more complex vegetative cover provides greater soil moisture storage capacity for winter precipitation than the usual grass cover

  1. Microbial degradation of low-level radioactive waste. Final report

    International Nuclear Information System (INIS)

    The Nuclear Regulatory Commission stipulates in 10 CFR 61 that disposed low-level radioactive waste (LLW) be stabilized. To provide guidance to disposal vendors and nuclear station waste generators for implementing those requirements, the NRC developed the Technical Position on Waste Form, Revision 1. That document details a specified set of recommended testing procedures and criteria, including several tests for determining the biodegradation properties of waste forms. Information has been presented by a number of researchers, which indicated that those tests may be inappropriate for examining microbial degradation of cement-solidified LLW. Cement has been widely used to solidify LLW; however, the resulting waste forms are sometimes susceptible to failure due to the actions of waste constituents, stress, and environment. The purpose of this research program was to develop modified microbial degradation test procedures that would be more appropriate than the existing procedures for evaluation of the effects of microbiologically influenced chemical attack on cement-solidified LLW. The procedures that have been developed in this work are presented and discussed. Groups of microorganisms indigenous to LLW disposal sites were employed that can metabolically convert organic and inorganic substrates into organic and mineral acids. Such acids aggressively react with cement and can ultimately lead to structural failure. Results on the application of mechanisms inherent in microbially influenced degradation of cement-based material are the focus of this final report. Data-validated evidence of the potential for microbially influenced deterioration of cement-solidified LLW and subsequent release of radionuclides developed during this study are presented

  2. Geohydrologic aspects for siting and design of low-level radioactive-waste disposal

    Science.gov (United States)

    Bedinger, M.S.

    1989-01-01

    The objective for siting and design of low-level radioactive-waste repository sites is to isolate the waste from the biosphere until the waste no longer poses an unacceptable hazard as a result of radioactive decay. Low-level radioactive waste commonly is isolated at shallow depths with various engineered features to stabilize the waste and to reduce its dissolution and transport by ground water. The unsaturated zone generally is preferred for isolating the waste. Low-level radioactive waste may need to be isolated for 300 to 500 years. Maintenance and monitoring of the repository site are required by Federal regulations for only the first 100 years. Therefore, geohydrology of the repository site needs to provide natural isolation of the waste for the hazardous period following maintenance of the site. Engineering design of the repository needs to be compatible with the natural geohydrologic conditions at the site. Studies at existing commercial and Federal waste-disposal sites provide information on the problems encountered and the basis for establishing siting guidelines for improved isolation of radioactive waste, engineering design of repository structures, and surveillance needs to assess the effectiveness of the repositories and to provide early warning of problems that may require remedial action. Climate directly affects the hydrology of a site and probably is the most important single factor that affects the suitability of a site for shallow-land burial of low-level radioactive waste. Humid and subhumid regions are not well suited for shallow isolation of low-level radioactive waste in the unsaturated zone; arid regions with zero to small infiltration from precipitation, great depths to the water table, and long flow paths to natural discharge areas are naturally well suited to isolation of the waste. The unsaturated zone is preferred for isolation of low-level radioactive waste. The guiding rationale is to minimize contact of water with the waste and to

  3. UTILIZATION OF RISK-BASED METHODOLOGY AND NON-DESTRUCTIVE ASSAY TECHNOLOGIES TO CHARACTERIZE AND DISPOSITION LEGACY LOW-LEVEL RADIOACTIVE WASTE

    Energy Technology Data Exchange (ETDEWEB)

    Wolf, J

    2004-12-03

    A scaled risk and technology based disposition path was developed to characterize and certify Lawrence Livermore National Laboratory (LLNL) legacy waste (LW) for disposal at Envirocare of Utah and the Nevada Test Site (NTS). A combination of LLNL and commercially provided non-destructive assay (NDA) techniques were utilized to characterize waste and facilitate the safe, efficient and cost-effective characterization and disposition of 490 cubic meters of LW in Fiscal Year (FY) 2004. The approach and technologies described in this paper are adaptable to most waste characterization programs and will be utilized to meet future project milestones.

  4. Greater-than-class C low-level waste characterization

    International Nuclear Information System (INIS)

    In 1985, Public Law 99-240 (Low-Level Radioactive Waste Policy Amendments Act of 1985) made the Department of Energy (DOE) responsible for the disposal of greater-than-Class C low-level radioactive waste (GTCC LLW). DOE strategies for storage and disposal of GTCC LLW required characterization of volumes, radionuclide activities, and waste forms. Data from existing literature, disposal records, and original research were used to estimate characteristics, project volumes, and determine radionuclide activities to the years 2035 and 2055. Twenty-year life extensions for 70% of the operating nuclear reactors were assumed to calculate the GTCC LLW available in 2055. The following categories of GTCC LLW were addressed: (1) nuclear utilities waste, (2) potential sealed sources GTCC LLW, (3) DOE-held potential GTCC LLW, and (4) other generator waste. It was determined that the largest volume of these wastes, approximately 57%, is generated by nuclear utilities. The other-generator-waste category contributes approximately 10% of the total GTCC LLW volume projected to the year 2035. DOE-held potential GTCC LLW accounts for nearly 33% of all waste projected to the year 2035. Potential sealed sources GTCC LLW is less than 0.2% of the total projected volume. The base case total projected volume of GTCC LLW for all categories was 3,250 m3. This was substantially less than previous estimates

  5. Greater-than-Class C low-level waste characterization

    Energy Technology Data Exchange (ETDEWEB)

    Piscitella, R.R. [EG and G Idaho, Inc., Idaho Falls, ID (United States). Idaho National Engineering Lab.

    1991-12-31

    In 1985, Public Law 99-240 (Low-Level Radioactive Waste Policy Amendments Act of 1985) made the Department of Energy (DOE) responsible for the disposal of greater-than-Class C low-level radioactive waste (GTCC LLW). DOE strategies for storage and disposal of GTCC LLW required characterization of volumes, radionuclide activities, and waste forms. Data from existing literature, disposal records, and original research were used to estimate characteristics, project volumes, and determine radionuclide activities to the years 2035 and 2055. Twenty-year life extensions for 70% of the operating nuclear reactors were assumed to calculate the GTCC LLW available in 2055. The following categories of GTCC LLW were addressed: Nuclear Utilities Waste; Potential Sealed Sources GTCC LLW; DOE-Held Potential GTCC LLW; and Other Generator Waste. It was determined that the largest volume of these wastes, approximately 57%, is generated by nuclear utilities. The Other Generator Waste category contributes approximately 10% of the total GTCC LLW volume projected to the year 2035. DOE-Held Potential GTCC LLW accounts for nearly 33% of all waste projected to the year 2035. Potential Sealed Sources GTCC LLW is less than 0.2% of the total projected volume. The base case total projected volume of GTCC LLW for all categories was 3,250 cubic meters. This was substantially less than previous estimates.

  6. LOWRAD 96. Methods and applications of low-level radioactivity measurements. Proceedings

    International Nuclear Information System (INIS)

    The newest developments in the field of low-level radioactivity measurements and new applications for existing and low-level measuring facilities are presented. The contributions mostly were devoted to basic physical aspects and applications of low-level counting. Papers on chemical separation and preparation techniques and on low-level radiation dose determinations were also presented. (DG)

  7. LOWRAD 96. Methods and applications of low-level radioactivity measurements. Proceedings

    Energy Technology Data Exchange (ETDEWEB)

    Fietz, J. [ed.] [Forschungszentrum Rossendorf e.V. (FZR), Dresden (Germany)

    1997-03-01

    The newest developments in the field of low-level radioactivity measurements and new applications for existing and low-level measuring facilities are presented. The contributions mostly were devoted to basic physical aspects and applications of low-level counting. Papers on chemical separation and preparation techniques and on low-level radiation dose determinations were also presented. (DG)

  8. Alternatives To The Burial Of Low-Level Radioactive Waste

    International Nuclear Information System (INIS)

    have been fully dismantled. Proven techniques and equipment are available to dismantle nuclear facilities safely. Most parts of a nuclear power plants do not become radioactive or are contaminated at very low levels and most metal can be recycled. There are obvious environmental benefits to the decontamination, recycle and reuse of materials. The benefits come primarily from the reduction of waste and eliminating the need to obtain fresh materials for the new product. The benefits of recycling in other industries are well recognized. Not having a waste management option can sometimes delay decommissioning of nuclear facilities. Therefore, the availability of a recycling route for the waste may accelerate decommissioning progress. With improving prospects for building new nuclear power plants, the industry would likely use the option if significant amounts of waste materials could be recycled economically. There is little consistency in national approaches to recycling radioactive waste. Many options for recycling allow for the release of materials into the public domain (after decontamination to allowable levels). There is not uniform endorsement of this practice from country to country and some stakeholders do not agree with this type of material release (often reduced to as unconditional release). There is a large amount of material that can have conditional release within the industry that assures consistent endorsement by stakeholders. This material includes: concrete, lead, carbon and stainless steel, and graphite. More work needs to be done to ensure consistency in regulation from country to country. The IAEA is working to this end

  9. 1989 Annual report on low-level radioactive waste management progress

    International Nuclear Information System (INIS)

    This report summarizes the progress during 1989 of states and compacts in establishing new low-level radioactive waste disposal facilities. It also provides summary information on the volume of low-level waste received for disposal in 1989 by commercially operated low-level waste disposal facilities. This report is in response to Section 7(b) of Title I of Public Law 99--240, the Low-Level Radioactive Waste Policy Amendments Act of 1985. 2 figs., 5 tabs

  10. Status of the North Carolina/Southeast Compact low-level radioactive waste disposal project

    Energy Technology Data Exchange (ETDEWEB)

    Walker, C.K. [North Carolina Low-Level Radioactive Waste Management Authority, NC (United States)

    1993-03-01

    The Southeast Compact is a sited region for low-level radioactive waste because of the current facility at Barnwell, South Carolina. North Carolina has been designated as the next host state for the compact, and the North Carolina Low-Level Radioactive Waste Management Authority is the agency charged with developing the new facility. Chem-Nuclear Systems, Inc., has been selected by the Authority as its primary site development and operations contractor. This paper will describe the progress currently being made toward the successful opening of the facility in January 1996. The areas to be addressed include site characterization, performance assessment, facility design, public outreach, litigation, finances, and the continued operation of the Barnwell facility.

  11. 1996 annual report on low-level radioactive waste management progress. Report to Congress

    International Nuclear Information System (INIS)

    This report is prepared in response to the Low-Level Radioactive Waste Policy Act (the Act), Public Law 96-573, 1980, as amended by the Low-Level Radioactive Waste Policy Amendments Act of 1985, Public Law 99-240. The report summarizes the activities during calendar year 1996 related to the establishment of new disposal facilities for commercially-generated low-level radioactive waste. The report emphasizes significant issues and events that have affected progress in developing new disposal facilities, and also includes an introduction that provides background information and perspective on US policy for low-level radioactive waste disposal

  12. Mixed Low-Level Radioactive Waste (MLLW) Primer

    Energy Technology Data Exchange (ETDEWEB)

    W. E. Schwinkendorf

    1999-04-01

    This document presents a general overview of mixed low-level waste, including the regulatory definitions and drivers, the manner in which the various kinds of mixed waste are regulated, and a discussion of the waste treatment options.

  13. Managing low-level radioactive wastes: a proposed approach

    International Nuclear Information System (INIS)

    This document is a consensus report of the Low-Level Waste Strategy Task Force. It covers system-wide issues; generation, treatment, and packaging; transportation; and disposal. Recommendations are made

  14. Managing low-level radioactive wastes: a proposed approach

    Energy Technology Data Exchange (ETDEWEB)

    1980-08-01

    This document is a consensus report of the Low-Level Waste Strategy Task Force. It covers system-wide issues; generation, treatment, and packaging; transportation; and disposal. Recommendations are made. (DLC)

  15. Mixed Low-Level Radioactive Waste (MLLW) Primer

    International Nuclear Information System (INIS)

    This document presents a general overview of mixed low-level waste, including the regulatory definitions and drivers, the manner in which the various kinds of mixed waste are regulated, and a discussion of the waste treatment options

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

    International Nuclear Information System (INIS)

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

  17. Planner's guide to low-level radioactive waste disposal. Planning Advisory Service report number 369

    International Nuclear Information System (INIS)

    Chapters are devoted to the basics of waste generation and management, transport of low-level radioactive wastes, treatment and disposal of low-level radioactive wastes, proposed siting standards for disposal facilities, state initiatives for waste management, and local government participation. Five appendices are included: definitions; summary of code and federal regulations for the transport of radioactive materials; DOT routing rules for radioactive materials (excerpt); proposed NRC site selection criteria; waste distribution by state; available films; and annotated bibliography

  18. Low-level radioactive waste treatment systems in northern Europe

    International Nuclear Information System (INIS)

    In the United States, the use of low-level waste (LLW) treatment systems by low level waste generators can be expected to expand with increasing costs for disposal and continuing uncertainty over the availability of disposal space. This development increases the need for performance information and operational data and has prompted the US Department of Energy to commission several compilations of LLW systems experience. The present paper summarizes some of the know-how from Northern Europe where the incentive for LLW treatment and volume reduction is very high since deposition space has not been available for many years. 65 refs., 10 figs., 4 tabs

  19. Soil characterization methods for unsaturated low-level waste sites

    Energy Technology Data Exchange (ETDEWEB)

    Wierenga, P.J.; Young, M.H. (Arizona Univ., Tucson, AZ (United States). Dept. of Soil and Water Science); Gee, G.W.; Kincaid, C.T. (Pacific Northwest Lab., Richland, WA (United States)); Hills, R.G. (New Mexico State Univ., Las Cruces, NM (United States). Dept. of Mechanical Engineering); Nicholson, T.J.; Cady, R.E. (Nuclear Regulatory Commission, Washington, DC (United States))

    1993-01-01

    To support a license application for the disposal of low-level radioactive waste (LLW), applicants must characterize the unsaturated zone and demonstrate that waste will not migrate from the facility boundary. This document provides a strategy for developing this characterization plan. It describes principles of contaminant flow and transport, site characterization and monitoring strategies, and data management. It also discusses methods and practices that are currently used to monitor properties and conditions in the soil profile, how these properties influence water and waste migration, and why they are important to the license application. The methods part of the document is divided into sections on laboratory and field-based properties, then further subdivided into the description of methods for determining 18 physical, flow, and transport properties. Because of the availability of detailed procedures in many texts and journal articles, the reader is often directed for details to the available literature. References are made to experiments performed at the Las Cruces Trench site, New Mexico, that support LLW site characterization activities. A major contribution from the Las Cruces study is the experience gained in handling data sets for site characterization and the subsequent use of these data sets in modeling studies.

  20. Soil characterization methods for unsaturated low-level waste sites

    International Nuclear Information System (INIS)

    To support a license application for the disposal of low-level radioactive waste (LLW), applicants must characterize the unsaturated zone and demonstrate that waste will not migrate from the facility boundary. This document provides a strategy for developing this characterization plan. It describes principles of contaminant flow and transport, site characterization and monitoring strategies, and data management. It also discusses methods and practices that are currently used to monitor properties and conditions in the soil profile, how these properties influence water and waste migration, and why they are important to the license application. The methods part of the document is divided into sections on laboratory and field-based properties, then further subdivided into the description of methods for determining 18 physical, flow, and transport properties. Because of the availability of detailed procedures in many texts and journal articles, the reader is often directed for details to the available literature. References are made to experiments performed at the Las Cruces Trench site, New Mexico, that support LLW site characterization activities. A major contribution from the Las Cruces study is the experience gained in handling data sets for site characterization and the subsequent use of these data sets in modeling studies

  1. (Low-level waste disposal facility siting and site characterization)

    Energy Technology Data Exchange (ETDEWEB)

    Mezga, L.J.; Ketelle, R.H.; Pin, F.G.; Van Hoesen, S.D.

    1985-10-25

    A US team consisting of representatives of Oak Ridge National Laboratory (ORNL), Savannah River Plant (SRP), Savannah river Laboratory (SRL), and the Department of Energy Office of Defense Waste and Byproducts Management participated in the fourth meeting held under the US/French Radioactive Waste Management Agreement between the US Department of Energy and the Commissariat a l'Energie Atomique. This meeting, held at Agence Nationale pour les Gestion des Dechets Radioactifs' (ANDRA's) Headquarters in Paris, was a detailed, technical topical workshop focusing on Low-Level Waste Disposal Facility Siting and Site Characterization.'' The meeting also included a visit to the Centre de la Manche waste management facility operated by ANDRA to discuss and observe the French approach to low-level waste management. The final day of the meeting was spent at the offices of Societe Generale pour les Techniques Nouvelles (SGN) discussing potential areas of future cooperation and exchange. 20 figs.

  2. 18th U.S. Department of Energy Low-Level Radioactive Waste Management Conference. Program

    International Nuclear Information System (INIS)

    This conference explored the latest developments in low-level radioactive waste management through presentations from professionals in both the public and the private sectors and special guests. The conference included two continuing education seminars, a workshop, exhibits, and a tour of Envirocare of Utah, Inc., one of America's three commercial low-level radioactive waste depositories

  3. 77 FR 58416 - Comparative Environmental Evaluation of Alternatives for Handling Low-Level Radioactive Waste...

    Science.gov (United States)

    2012-09-20

    ... COMMISSION Comparative Environmental Evaluation of Alternatives for Handling Low-Level Radioactive Waste... Environmental Evaluation of Alternatives for Handling Low-Level Radioactive Waste Spent Ion Exchange Resins from Commercial Nuclear Power Reactors. DATES: Please submit comments by January 18, 2013. Comments received...

  4. 18th U.S. Department of Energy Low-Level Radioactive Waste Management Conference. Program

    Energy Technology Data Exchange (ETDEWEB)

    None

    1997-05-20

    This conference explored the latest developments in low-level radioactive waste management through presentations from professionals in both the public and the private sectors and special guests. The conference included two continuing education seminars, a workshop, exhibits, and a tour of Envirocare of Utah, Inc., one of America's three commercial low-level radioactive waste depositories.

  5. Directions in low-level radioactive waste management. The siting process: establishing a low-level waste-disposal facility

    Energy Technology Data Exchange (ETDEWEB)

    1982-11-01

    The siting of a low-level radioactive waste disposal facility encompasses many interrelated activities and, therefore, is inherently complex. The purpose of this publication is to assist state policymakers in understanding the nature of the siting process. Initial discussion focuses on the primary activities that require coordination during a siting effort. Available options for determining site development, licensing, regulating, and operating responsibilities are then considered. Additionally, the document calls attention to technical services available from federal agencies to assist states in the siting process; responsibilities of such agencies are also explained. The appendices include a conceptual plan for scheduling siting activities and an explanation of the process for acquiring agreement state status. An agreement state takes responsibility for licensing and regulating a low-level waste facility within its borders.

  6. Radioactivity partitioning in incinerators for miscellaneous low-level wastes

    International Nuclear Information System (INIS)

    Her Majesty's Inspectorate of Pollution (HMIP) authorises the use of hospital, university and Local Authority incinerators for the disposal of solid radioactive wastes. At present these authorisations are calculated on ''worst case'' assumptions, this report aims to review the experimental data on radioactivity partitioning in these incinerators, in order to improve the accuracy of HMIP predictions. The types of radionuclides used in medicine were presented and it is noted there is no literature on the composition of university waste. The different types of incinerators are detailed, with diagrams. Major differences in design are apparent, particularly the offgas cleaning equipment in nuclear incinerators which hinders comparisons with institutional incinerators. A comprehensive literature review revealed 17 references on institutional radioactive waste incineration, 11 of these contained data sets. The partitioning experiments were described and show a wide range of methodology from incinerating guinea pigs to filter papers. In general, only ash composition data were presented, with no details of emissions or plating out in the incinerator. Thus the data sets were incomplete, often with a poor degree of accuracy. The data sets contained information on 40 elements; those were compared and general trends were apparent such as the absence of H-3, C-14 and I-125 in the ash in contrast to the high retention of Sc-46. Large differences between data sets were noted for P-32, Sr-85 and Sn-113 and within one experiment for S-35. (author)

  7. Quality assurance guidance for low-level radioactive waste disposal facility: Final report

    International Nuclear Information System (INIS)

    This document provides guidance to an applicant on meeting the quality control (QC) requirements for a low-level waste (LLW) disposal facility. The QC requirements are the basis for developing of a quality assurance (QA) program and for the guidance provided herein. The criteria are basic to any QA program. The document specifically establishes QA guidance for the design, construction, and operation of those structures, systems, components, as well as, for site characterization activities necessary to meet the performance objectives and to limit exposure to our release of radioactivity. 7 refs

  8. Review of available options for low level radioactive waste disposal

    International Nuclear Information System (INIS)

    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. Fifteenth annual U.S. Department of Energy low-level radioactive waste management conference: Agenda and abstracts

    International Nuclear Information System (INIS)

    The goal of the conference was to give the opportunity to identify and discuss low-level radioactive waste management issues, share lessons learned, and hear about some of the latest advances in technology. Abstracts of the presentations are arranged into the following topical sections: (1) Performance Management Track: Performance assessment perspectives; Site characterization; Modeling and performance assessment; and Remediation; (2) Technical Track: Strategic planning; Tools and options; Characterization and validation; Treatment updates; Technology development; and Storage; (3) Institutional Track: Orders and regulatory issues; Waste management options; Legal, economic, and social issues; Public involvement; Siting process; and Low-level radioactive waste policy amendment acts

  10. Fifteenth annual U.S. Department of Energy low-level radioactive waste management conference: Agenda and abstracts

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1993-12-31

    The goal of the conference was to give the opportunity to identify and discuss low-level radioactive waste management issues, share lessons learned, and hear about some of the latest advances in technology. Abstracts of the presentations are arranged into the following topical sections: (1) Performance Management Track: Performance assessment perspectives; Site characterization; Modeling and performance assessment; and Remediation; (2) Technical Track: Strategic planning; Tools and options; Characterization and validation; Treatment updates; Technology development; and Storage; (3) Institutional Track: Orders and regulatory issues; Waste management options; Legal, economic, and social issues; Public involvement; Siting process; and Low-level radioactive waste policy amendment acts.

  11. Kansas State Briefing Book on low-level radioactive waste management

    International Nuclear Information System (INIS)

    The Kansas State Briefing Book is one of a series of state briefing books on low-level radioactive waste management practices. It has been prepared to assist state and federal agency officials in planning for safe low-level radioactive waste disposal. The report contains a profile of low-level radioactive waste generators in Kansas. The profile is the result of a survey of radioactive material licensees in Kansas. The briefing book also contains a comprehensive assessment of low-level radioactive waste management issues and concerns as defined by all major interested parties including industry, government, the media, and interest groups. The assessment was developed through personal communications with representatives of interested parties, and through a review of media sources. Lastly, the briefing book provides demographic and socioeconomic data and a discussion of relevant government agencies and activities, all of which may affect waste management practices in Kansas

  12. Rhode Island State Briefing Book on low-level radioactive-waste management

    Energy Technology Data Exchange (ETDEWEB)

    1981-07-01

    The Rhode Island State Briefing Book is one of a series of state briefing books on low-level radioactive waste management practices. It has been prepared to assist state and federal agency officials in planning for safe low-level radioactive waste disposal. The report contains a profile of low-level radioactive waste generators in Rhode Island. The profile is the result of a survey of radioactive material licensees in Rhode Island. The briefing book also contains a comprehensive assessment of low-level radioactive waste management issues and concerns as defined by all major interested parties including industry, government, the media, and interest groups. The assessment was developed through personal communications with representatives of interested parties, and through a review of media sources. Lastly, the briefing book provides demographic and socioeconomic data and a discussion of relevant government agencies and activities, all of which may affect waste management practices in Rhode Island.

  13. Maine State Briefing Book on low-level radioactive waste management

    Energy Technology Data Exchange (ETDEWEB)

    1981-08-01

    The Maine State Briefing Book is one of a series of state briefing books on low-level radioactive waste management practices. It has been prepared to assist state and Federal agency officials in planning for safe low-level radioactive waste disposal. The report contains a profile of low-level radioactive waste generators in Maine. The profile is the result of a survey of radioactive material licensees in Maine. The briefing book also contains a comprehensive assessment of low-level radioactive waste management issues and concerns as defined by all major interested partices including industry, government, the media, and interest groups. The assessment was developed through personal communications with representatives of interested parties, and through a review of media sources. Lastly, the briefing book provides demographic and socioeconomic data and a discussion of relevant goverment agencies and activities, all of which may impact management practices in Maine.

  14. Rhode Island State Briefing Book on low-level radioactive-waste management

    International Nuclear Information System (INIS)

    The Rhode Island State Briefing Book is one of a series of state briefing books on low-level radioactive waste management practices. It has been prepared to assist state and federal agency officials in planning for safe low-level radioactive waste disposal. The report contains a profile of low-level radioactive waste generators in Rhode Island. The profile is the result of a survey of radioactive material licensees in Rhode Island. The briefing book also contains a comprehensive assessment of low-level radioactive waste management issues and concerns as defined by all major interested parties including industry, government, the media, and interest groups. The assessment was developed through personal communications with representatives of interested parties, and through a review of media sources. Lastly, the briefing book provides demographic and socioeconomic data and a discussion of relevant government agencies and activities, all of which may affect waste management practices in Rhode Island

  15. Determination of 90Sr in low-level radioactive wastes using extraction chromatography and LSC

    International Nuclear Information System (INIS)

    A procedure for the determination of 90Sr in low-level radioactive wastes is presented in this work. It is a part of a methodology developed for the sequential radiochemical separation of radionuclides in low-level radioactive wastes. These radionuclides comprises the actinides and 55Fe, 63Ni and 90Sr, classified as difficult-to-measure (DTM) radionuclides in the radioactive waste characterization, because they cannot be measured by direct measurements, like gamma spectrometry. A variety of methods have been reported in the literature, based on precipitation, liquid-liquid extraction and ion exchange. In this work, the separation was carried out using precipitation and extraction chromatography using the Sr Resin (Eichrom). This resin is strontium-selective, the extractant is a crown ether-derivative immobilized on an inert polymeric support. The 90Sr eluted from column was measured by LSC. The counting was carried out within 5 hours of the start of yttrium ingrowth to minimize interferences from 90Y. The counting efficiency was calculated by using a 90Sr standard solution purified by the specific resin. The chemical yield of the procedure was determined gravimetrically by the addition of a stable Sr carrier. Optimum conditions for the pretreatment, separation and LSC setting were determined using simulated samples. This procedure showed to be rapid and achieved a good chemical recovery, with an average of 84 %, and a detection limit of 0.6 Bq L-1. (author)

  16. Microbial transformation of low-level radioactive waste

    Energy Technology Data Exchange (ETDEWEB)

    Francis, A.J.

    1980-06-01

    Microorganisms play a significant role in the transformation of the radioactive waste and waste forms disposed of at shallow-land burial sites. Microbial degradation products of organic wastes may influence the transport of buried radionuclides by leaching, solubilization, and formation of organoradionuclide complexes. The ability of indigenous microflora of the radioactive waste to degrade the organic compounds under aerobic and anaerobic conditions was examined. Leachate samples were extracted with methylene chloried and analyzed for organic compounds by gas chromatography and mass spectrometry. In general, several of the organic compounds in the leachates were degraded under aerobic conditions. Under anaerobic conditions, the degradation of the organics was very slow, and changes in concentrations of several acidic compounds were observed. Several low-molecular-weight organic acids are formed by breakdown of complex organic materials and are further metabolized by microorganisms; hence these compounds are in a dynamic state, being both synthesized and destroyed. Tributyl phosphate, a compound used in the extraction of metal ions from solutions of reactor products, was not degraded under anaerobic conditions.

  17. Microbial transformation of low-level radioactive waste

    International Nuclear Information System (INIS)

    Microorganisms play a significant role in the transformation of the radioactive waste and waste forms disposed of at shallow-land burial sites. Microbial degradation products of organic wastes may influence the transport of buried radionuclides by leaching, solubilization, and formation of organoradionuclide complexes. The ability of indigenous microflora of the radioactive waste to degrade the organic compounds under aerobic and anaerobic conditions was examined. Leachate samples were extracted with methylene chloried and analyzed for organic compounds by gas chromatography and mass spectrometry. In general, several of the organic compounds in the leachates were degraded under aerobic conditions. Under anaerobic conditions, the degradation of the organics was very slow, and changes in concentrations of several acidic compounds were observed. Several low-molecular-weight organic acids are formed by breakdown of complex organic materials and are further metabolized by microorganisms; hence these compounds are in a dynamic state, being both synthesized and destroyed. Tributyl phosphate, a compound used in the extraction of metal ions from solutions of reactor products, was not degraded under anaerobic conditions

  18. Conventional incinerator redesign for the incineration of low level radioactive solid wastes

    International Nuclear Information System (INIS)

    From several years ago have been detected some problems with the storage of low level radioactive solids wastes, they are occasioned growth in volume and weight, one of most effective treatment for its reduction, the incineration has been. In the work was designed an incinerator of low level radioactive solid wastes, the characteristics, range of temperatures, that operate and the excess of air in order to get a near incineration at 100 %; thickness of refractory material in the combustion chamber, materials and forms of installation, the balances of mass, energy and radioactive material necessary for the design of the auxiliary peripheral equipment is discussed. In theory the incineration is a viable option for the treatment of low level radioactive solid wastes, upon getting an approximate reduction to 95 % of the wastes introduced to the incinerator in the Department of Radioactive Wastes of the National Institute of Nuclear Research, avoiding the dispersion of combustion gases and radioactive material at the environment. (Author)

  19. Communicating Risk to a Concerned Public in Historic Low-Level Radioactive Waste (LLRW) Projects

    International Nuclear Information System (INIS)

    The Low-Level Radioactive Waste Management Office (LLRWMO) was established in 1982 to carry out federal government responsibility for historic low-level radioactive waste across Canada. Funded through Natural Resources Canada (NRCan) and administered by Atomic Energy of Canada Limited (AECL), the LLRWMO has conducted waste characterization, delineation and remediation projects in British Columbia, the Northwest Territories, Alberta and Ontario. Most (95%) of the historic low-level radioactive wastes for which the LLRWMO assumes responsibility are located in and around Port Hope, Ontario, the site of the refining operations of the former federal Crown Corporation, Eldorado Nuclear. Additional contamination is connected to the transportation of the ore along a route extending from Port Radium on Great Bear Lake (Northwest Territories) to Port Hope, a Lake Ontario community of 16,000 in south/central Ontario. This paper will focus on the successful strategies employed by the LLRWMO over the past 25 years to find solutions to the problems posed by the historic waste. Risks associated with each project must be defined prior to initiating any communication plan. Using this approach, the LLRWMO has addressed socio-economic, health and well being and environmental risks through strategies that embrace proactive communications and full public involvement. Recognizing the diversity of the Canadian communities affected by the historic waste, the LLRWMO has tailored its consultation programs both to the type of solutions proposed and to the character of the communities (i.e. urban, First Nation, rural etc.). In Port Hope, community solutions are being realized through a Legal Agreement negotiated by the affected communities and the federal government in 2000 and an intensive Environmental Assessment process under the Canadian Environmental Assessment Act, which is expected to reach completion early in 2007. (authors)

  20. Massachusetts State Briefing Book for low-level radioactive waste management

    Energy Technology Data Exchange (ETDEWEB)

    1981-03-12

    The Massachusetts State Briefing Book is one of a series of State briefing books on low-level radioactive waste management practices. It has been prepared to assist State and Federal agency officials in planning for safe low-level radioactive waste disposal. The report contains a profile of low-level radioactive waste generators in Massachusetts. The profile is the result of a survey of NRC licensees in Massachusetts. The briefing book also contains a comprehensive assessment of low-level radioactive waste management issues and concerns as defined by all major interested parties including industry, government, the media, and interest groups. The assessment was developed through personal communications with representatives of interested parties, and through a review of media sources. Lastly, the briefing book provides demographic and socioeconomic data and a discussion of relevant government agencies and activities, all of which may impact waste management practices in Massachusetts.

  1. Tennessee State Briefing Book for low-level radioactive-waste management

    International Nuclear Information System (INIS)

    The Tennessee State Briefing Book is one of a series of State briefing books on low-level radioactive waste management practices. It has been prepared to assist State and Federal Agency officials in planning for safe low-level radioactive waste disposal. The report contains a profile of low-level radioactive waste generators in Tennessee. The profile is the result of a survey of NRC licensees in Tennessee. The briefing book also contains a comprehensive assessment of low-level radioactive waste management issues and concerns as defined by all major interested parties including industry, government, the media, and interest groups. The assessment was developed through personal communications with representatives of interested parties, and through a review of media sources. Lastly, the briefing book provides demographic and socioeconomic data and a discussion of relevant government agencies and activities, all of which may impact waste management practices in Tennessee

  2. Mississippi State Briefing Book for low-level radioactive waste management

    International Nuclear Information System (INIS)

    The Mississippi State Briefing Book is one of a series of state briefing books on low-level radioactive waste management practices. It has been prepared to assist state an federal agency officials in planning for safe low-level radioactive waste disposal. The report contains a profile of low-level radioactive waste generators in Mississippi. The profile is the result of a survey of NRC licensees in Mississippi. The briefing book also contains a comprehensive assessment of low-level radioactive waste management issues and concerns as defined by all major interested parties including industry, government, the media, and interest groups. The assessment was developed through personal communications with representatives of interested parties, and through a review of media sources. Lastly, the briefing book provides demographic and socioeconomic data and a discussion of relevant government agencies and activities, all of which may impact waste management practices in Mississippi

  3. Oklahoma State Briefing Book for low-level radioactive waste management

    International Nuclear Information System (INIS)

    The Oklahoma State Briefing Book is one of a series of state briefing books on low-level radioactive waste management practices. It has been prepared to assist state and federal agency officials in planning for safe low-level radioactive waste disposal. The report contains a profile of low-level radioactive waste generators in Oklahoma. The profile is the result of a survey of NRC licensees in Oklahoma. The briefing book also contains a comprehensive assessment of low-level radioactive waste management issues and concerns as defined by all major interested parties including industry, government, the media, and interest groups. The assessment was developed through personal communications with representatives of interested parties, and through a review of media sources. Lastly, the briefing book provides demographic and socioeconomic data and a discussion of relevant government agencies and activities, all of which may impact waste management practices in Oklahoma

  4. Georgia State Briefing Book for low-level radioactive waste management

    International Nuclear Information System (INIS)

    The Georgia State Briefing Book is one of a series of state briefing books on low-level radioactive waste management practices. It has been prepared to assist state and federal agency officials in planning for safe low-level radioactive waste disposal. This report contains a profile of low-level radioactive waste generators in Georgia. The profile is the result of a survey of NRC licensees in Georgia. The briefing book also contains a comprehensive assessment of low-level radioactive waste management issues and concerns as defined by all major interested parties including industry, government, the media, and interest groups. The assessment was developed through personal communications with representatives of interested parties, and through a review of media sources. Lastly, the briefing book provides demographic and socioeconomic data and a discussion of relevant government agencies and activities, all of which may impact waste management practices in Georgia

  5. Virginia State Briefing Book for low-level radioactive-waste management

    International Nuclear Information System (INIS)

    The Virginia State Briefing Book is one of a series of state briefing books on low-level radioactive waste management practices. It has been prepared to assist state and federal agency officials in planning for safe low-level radioactive waste disposal. The report contains a profile of low-level radioactive waste generators in Virginia. The profile is the result of a survey of NRC licensees in Virginia. The briefing book also contains a comprehensive assessment of low-level radioactive waste management issues and concerns as defined by all major interested parties including industry, government, the media, and interest groups. The assessment was developed through personal communications with representatives of interested parties, and through a review of media sources. Lastly, the briefing book provides demographic and socioeconomic data and a discussion of relevant government agencies and activities, all of which may impact waste management practices in Virginia

  6. Oklahoma State Briefing Book for low-level radioactive waste management

    International Nuclear Information System (INIS)

    The Oklahoma State Briefing Book is one of a series of state briefing books on low-level radioactive waste management practices. It has been prepared to assist state and federal agency officials in planning for safe low-level radioactive waste disposal. The report contains a profile of low-level radioactive waste generators in Oklahoma. The profile is the result of a survey of NRC licensees in Oklahoma. The briefing book also contains a comprehensive assessment of low-level radioactive waste management issues and concerns as defined by all major interested parties including industry, government, the media, and interest groups. The assessment was developed through personal cmmunications with representatives of interested parties, and through a review of media sources. Lastly, the briefing book provides demographic and socioeconomic data and a discussion of relevant government agencies and activities, all of which may impact waste management practices in Oklahoma

  7. Ohio State Briefing Book for low-level radioactive waste management

    International Nuclear Information System (INIS)

    The Ohio State Briefing Book is one of a series of state briefing books on low-level radioactive waste management practices. It has been prepared to assist state and federal agency officials in planning for safe low-level radioactive waste disposal. The report contains a profile of low-level radioactive waste generators in Ohio. The profile is the result of a survey of NRC licensees in Ohio. The briefing book also contains a comprehensive assessment of low-level radioactive waste management issues and concerns as defined by all major interested parties including industry, government, the media, and interest groups. The assessment was developed through personal communications with representatives of interested parties, and through a review of media sources. Lastly, the briefing book provides demographic and socioeconomic data and a discussion of relevant government agencies and activities, all of which may impact waste management practices in Ohio

  8. Wyoming State Briefing Book for low-level radioactive waste management

    Energy Technology Data Exchange (ETDEWEB)

    1981-10-01

    The Wyoming State Briefing Book is one of a series of state briefing books on low-level radioactive waste management practices. It has been prepared to assist state and federal agency officials in planning for safe low-level radioactive waste disposal. The report contains a profile of low-level radioactive waste generators in Wyoming. The profile is the result of a survey of NRC licensees in Wyoming. The briefing book also contains a comprehensive assessment of low-level radioactive waste management issues and concerns as defined by all major interested parties including industry, government, the media, and interest groups. The assessment was developed through personal communications with representatives of interested parties, and through a review of media sources. Lastly, the briefing book provides demographic and socioeconomic data and a discussion of relevant government agencies and activities, all of which may impact waste management practices in Wyoming.

  9. Utah State Briefing Book for low-level radioactive waste management

    Energy Technology Data Exchange (ETDEWEB)

    1981-10-01

    The Utah State Briefing Book is one of a series of state briefing books on low-level radioactive waste management practices. It has been prepared to assist state and federal agency officials in planning for safe low-level radioactive waste disposal. The report contains a profile of low-level radioactive waste generators in Utah. The profile is the result of a survey of NRC licensees in Utah. The briefing book also contains a comprehensive assessment of low-level radioactive waste management issues and concerns as defined by all major interested parties including industry, government, the media, and interest groups. The assessment was developed through personal communications with representatives of interested parties, and through a review of media sources. Lastly, the briefing book provides demographic and socioeconomic data and a discussion of relevant government agencies and activities, all of which may impact waste management practices in Utah.

  10. Tennessee State Briefing Book for low-level radioactive waste management

    Energy Technology Data Exchange (ETDEWEB)

    1981-08-01

    The Tennessee State Briefing Book is one of a series of state briefing books on low-level radioactive waste management practices. It has been prepared to assist state and federal agency officials in planning for safe low-level radioactive waste disposal. The report contains a profile of low-level radioactive waste generators in Tennessee. The profile is the result of a survey of NRC licensees in Tennessee. The briefing book also contains a comprehensive assessment of low-level radioactive waste management issues and concerns as defined by all major interested parties including industry, government, the media, and interest groups. The assessment was developed through personal communications with representatives of interested parties, and through a review of media sources. Lastly, the briefing book provides demographic and socioeconomic data and a discussion of relevant government agencies and activities, all of which may impact waste management practices in Tennessee.

  11. Kentucky State Briefing Book for low-level radioactive waste management

    Energy Technology Data Exchange (ETDEWEB)

    1981-08-01

    The Kentucky State Briefing Book is one of a series of State briefing books on low-level radioactive waste management practices. It has been prepared to assist State and Federal agency officials in planning for safe low-level radioactive waste disposal. The report contains a profile of low-level radioactive waste generators in Kentucky. The profile is the result of a survey of NRC licensees in Kentucky. The briefing book also contains a comprehensive assessment of low-level radioactive waste management issues and concerns as defined by all major interested parties including industry, government, the media, and interest groups. The assessment was developed through personal communications with representatives of interested parties, and through a review of media sources. Lastly, the briefing book provides demographic and socioeconomic data and a discussion of relevant government agencies and activities, all of which may impact waste management practices in Kentucky.

  12. Pennsylvania State Briefing Book for low-level radioactive waste management

    Energy Technology Data Exchange (ETDEWEB)

    1981-04-01

    The Pennsylvania State Briefing Book is one of a series of state briefing books on low-level radioactive waste management practices. It has been prepared to assist state and federal agency officials in planning for safe low-level radioactive waste disposal. The report contains a profile of low-level radioactive waste generators in Pennsylvania. The profile is the result of a survey of NRC licensees in Pennsylvania. The briefing book also contains a comprehensive assessment of low-level radioactive waste management issues and concerns as defined by all major interested parties including industry, government, the media, and interest groups. The assessment was developed through personal communications with representatives of interested parties, and through a review of media sources. Lastly, the briefing book provides demographic and socioeconomic data and a discussion of relevant government agencies and activities, all of which may impact waste management practices in Pennsylvania.

  13. Hawaii State briefing book for low-level radioactive waste management

    International Nuclear Information System (INIS)

    The Hawaii State Briefing Book is one of a series of state briefing books on low-level radioactive waste management practices. It has been prepared to assist state and federal agency officials in planning for safe low-level radioactive waste disposal. The report contains a profile of low-level radioactive waste generators in Hawaii. The profile is the result of a survey of NRC licensees in Hawaii. The briefing book also contains a comprehensive assessment of low-level radioactive waste management issues and concerns as defined by all major interested parties including industry, government, the media, and interest groups. The assessment was developed through personal communications with representatives of interested parties, and through a review of media sources. Lastly, the briefing book provides demographic and socioeconomic data and a discussion of relevant government agencies and activities, all of which may impact waste management practices in Hawaii

  14. Connecticut State Briefing Book for low-level radioactive-waste management

    International Nuclear Information System (INIS)

    The Connecticut State Briefing Book is one of a series of state briefing books on low-level radioactive waste management practices. It has been prepared to assist state and federal agency officials in planning for safe low-level radioactive waste disposal. The report contains a profile of low-level radioactive waste generators in Connecticut. The profile is the result of a survey of Nuclear Regulatory Commission licensees in Connecticut. The briefing book also contains a comprehensive assessment of low-level radioactive waste management issues and concerns as defined by all major interested parties including industry, government, the media, and interest groups. The assessment was developed through personal communications with representatives of interested parties, and through a review of media sources. Lastly, the briefing book provides demographic and socioeconomic data and a discussion of relevant government agencies and activities, all of which may affect waste management practices in Connecticut

  15. Arkansas State Briefing Book for low-level radioactive waste management

    International Nuclear Information System (INIS)

    The Arkansas State Briefing Book is one of a series of state briefing books on low-level radioactive waste management practices. It has been prepared to assist state and federal agency officials in planning for safe low-level radioactive waste disposal. This report contains a profile of low-level radioactive waste generators in Arkansas. The profile is the result of a survey of NRC licensees in Arkansas. The briefing book also contains a comprehensive assessment of low-level radioactive waste management issues and concerns as defined by all major interested parties including industry, government, the media, and interest groups. The assessment was developed through personal communications with representatives of interested parties, and through a review of media sources. Lastly, the briefing book provides demographic and socioeconomic data and a discussion of relevant government agencies and activities, all of which may impact waste management practices in Arkansas

  16. Tennessee State Briefing Book for low-level radioactive waste management

    International Nuclear Information System (INIS)

    The Tennessee State Briefing Book is one of a series of state briefing books on low-level radioactive waste management practices. It has been prepared to assist state and federal agency officials in planning for safe low-level radioactive waste disposal. The report contains a profile of low-level radioactive waste generators in Tennessee. The profile is the result of a survey of NRC licensees in Tennessee. The briefing book also contains a comprehensive assessment of low-level radioactive waste management issues and concerns as defined by all major interested parties including industry, government, the media, and interest groups. The assessment was developed through personal communications with representatives of interested parties, and through a review of media sources. Lastly, the briefing book provides demographic and socioeconomic data and a discussion of relevant government agencies and activities, all of which may impact waste management practices in Tennessee

  17. Delaware State Briefing Book on low-level radioactive-waste management

    International Nuclear Information System (INIS)

    The Delaware State Briefing Book is one of a series of state briefing books on low-level radioactive waste management practices. It has been prepared to assist state and federal agency officials in planning for safe low-level radioactive waste disposal. The report contains a profile of low-level radioactive waste generators in Delaware. The profile is the result of a survey of NRC licensees in Delaware. The briefing book also contains a comprehensive assessment of low-level radioactive waste management issues and concerns as defined by all major interested parties including industry, government, the media, and interest groups. The assessment was developed through personal communications with representatives of interested parties and through a review of media sources. Lastly, the briefing book provides demographic and socioeconomic data and a discussion of relevant government agencies and activities, all of which may impact waste management practices in Delaware

  18. Kentucky State Briefing Book for low-level radioactive waste management

    International Nuclear Information System (INIS)

    The Kentucky State Briefing Book is one of a series of State briefing books on low-level radioactive waste management practices. It has been prepared to assist State and Federal agency officials in planning for safe low-level radioactive waste disposal. The report contains a profile of low-level radioactive waste generators in Kentucky. The profile is the result of a survey of NRC licensees in Kentucky. The briefing book also contains a comprehensive assessment of low-level radioactive waste management issues and concerns as defined by all major interested parties including industry, government, the media, and interest groups. The assessment was developed through personal communications with representatives of interested parties, and through a review of media sources. Lastly, the briefing book provides demographic and socioeconomic data and a discussion of relevant government agencies and activities, all of which may impact waste management practices in Kentucky

  19. North Dakota State Briefing Book for low-level radioactive waste management

    International Nuclear Information System (INIS)

    The North Dakota State Briefing Book is one of a series of state briefing books on low-level radioactive waste management practices. It has been prepared to assist state and federal agency officials in planning for safe low-level radioactive waste disposal. The report contains a profile of low-level radioactive waste generators in North Dakota. The profile is the result of a survey of NRC licensees in North Dakota. The briefing book also contains a comprehensive assessment of low-level radioactive waste management issues and concerns as defined by all major interested parties including industry, government, the media, and interest groups. The assessment was developed through personal communications with representatives of interested parties, and through a review of media sources. Lastly, the briefing book provides demographic and socioeconomic data and a discussion of relevant government agencies and activities, all of which may impact waste management practices in North Dakota

  20. Connecticut State Briefing Book for low-level radioactive-waste management

    Energy Technology Data Exchange (ETDEWEB)

    None

    1981-06-01

    The Connecticut State Briefing Book is one of a series of state briefing books on low-level radioactive waste management practices. It has been prepared to assist state and federal agency officials in planning for safe low-level radioactive waste disposal. The report contains a profile of low-level radioactive waste generators in Connecticut. The profile is the result of a survey of Nuclear Regulatory Commission licensees in Connecticut. The briefing book also contains a comprehensive assessment of low-level radioactive waste management issues and concerns as defined by all major interested parties including industry, government, the media, and interest groups. The assessment was developed through personal communications with representatives of interested parties, and through a review of media sources. Lastly, the briefing book provides demographic and socioeconomic data and a discussion of relevant government agencies and activities, all of which may affect waste management practices in Connecticut.

  1. California State Briefing Book for low-level radioactive-waste management

    International Nuclear Information System (INIS)

    The California State Briefing Book is one of a series of state briefing books on low-level radioactive waste management practices. It has been prepared to assist state and federal agency officials in planning for safe low-level radioactive waste disposal. The report contains a profile of low-level radioactive waste generators in California. The profile is the result of a survey of NRC licensees in California. The briefing book also contains a comprehensive assessment of low-level radioactive waste management issues and concerns as defined by all major interested parties including industry, government, the media, and interest groups. The assessment was developed through personal communications with representatives of interested parties, and through a review of media sources. Lastly, the briefing book provides demographic and socioeconomic data and a discussion of relevant government agencies and activities, all of which may impact waste management practices in California

  2. South Carolina State Briefing Book for low-level radioactive waste management

    International Nuclear Information System (INIS)

    The South Carolina State Briefing Book is one of a series of state briefing books on low-level radioactive waste management practices. It has been prepared to assist state and federal agency officials in planning for safe low-level radioactive waste disposal. The report contains a profile of low-level radioactive waste generators in South Carolina. The profile is the result of a survey of NRC licensees in South Carolina. The briefing book also contains a comprehensive assessment of low-level radioactive waste management issues and concerns as definied by all major interested parties including industry, government, the media, and interest groups. The assessment was developed through personal communications with representatives of interested parties, and through a review of media sources. Lastly, the briefing book provides demographic and socioeconomic data and a discussion of relevant government agencies and activities, all of which may impact waste management practices in South Carolina

  3. South Dakota State Briefing Book for low-level radioactive waste management

    International Nuclear Information System (INIS)

    The South Dakota State Briefing Book is one of a series of state briefing books on low-level radioactive waste management practices. It has been prepared to assist state and federal agency officials in planning for safe low-level radioactive waste disposal. The report contains a profile of low-level radioactive waste generators in South Dakota. The profile is the result of a survey of NRC licensees in South Dakota. The briefing book also contains a comprehensive assessment of low-level radioactive waste management issues and concerns as defined by all major interested parties including industry, government, the media, and interest groups. The assessment was developed through personal communications with representatives of interested parties, and through a review of media sources. Lastly, the briefing book provides demographic and socioeconomic data and a discussion of relevant government agencies and activities, all of which may impact waste management practices in South Dakota

  4. North Carolina State Briefing Book for low-level radioactive waste management

    International Nuclear Information System (INIS)

    The North Carolina State Briefing Book is one of a series of state briefing books on low-level radioactive waste management practices. It has been prepared to assist state and federal agency officials in planning for safe low-level radioactive waste disposal. The report contains a profile of low-level radioactive waste generators in North Carolina. The profile is the result of a survey of NRC licensees in North Carolina. The briefing book also contains a comprehensive assessment of low-level radioactive waste management issues and concerns as defined by all major interested parties including industry, government, the media, and interest groups. The assessment was developed through personal communications with representatives of interested parties, and through a review of media sources. Lastly, the briefing book provides demographic and socioeconomic data and a discussion of relevant government agencies and activities, all of which may impact waste management practices in North Carolina

  5. Illinois State Briefing Book for low-level radioactive waste management

    International Nuclear Information System (INIS)

    The Illinois State Briefing Book is one of a series of state briefing books on low-level radioactive waste management practices. It has been prepared to assist state and federal agency officials in planning for safe low-level radioactive waste disposal. The report contains a profile of low-level radioactive waste generators in Illinois. The profile is the result of a survey of NRC licensees in Illinois. The briefing book also contains a comprehensive assessment of low-level radioactive waste management issues and concerns as defined by all major interested parties. The assessment was developed through personal communications with representatives of interested parties, and through a review of media sources. Lastly, the briefing book provides demographic and socioeconomic data and a discussion of relevant government agencies and activities, all of which may impact waste management practices in Illinois

  6. Oregon State Briefing Book for low-level radioactive waste management

    International Nuclear Information System (INIS)

    The Oregon State Briefing Book is one of a series of state briefing books on low-level radioactive waste management practices. It has been prepared to assist state and federal agency officials in planning for safe low-level radioactive waste disposal. The report contains a profile of low-level radioactive waste generators in Oregon. The profile is a result of a survey of NRC licensees in Oregon. The briefing book also contains a comprehensive assessment of low-level radioactive waste management issues and concerns as defined by all major interested parties including industry, government, the media, and interest groups. The assessment was developed through personal communications with representatives of interested parties, and through a review of media sources. Lastly, the briefing book provides demographic and socioeconomic data and a discussion of relevant government agencies and activities, all of which may impact waste management practices in Oregon

  7. Indiana State Briefing Book for low-level radioactive-waste management

    International Nuclear Information System (INIS)

    The Indiana State Briefing Book is one of a series of state briefing books on low-level radioactive waste management practices. It has been prepared to assist state and federal agency officials in planning for safe low-level radioactive waste disposal. The report contains a profile of low-level radioactive waste generators in Indiana. The profile is the result of a survey of NRC licensees in Indiana. The briefing book also contains a comprehensive assessment of low-level radioactive waste management issues and concerns as defined by all major interested parties including industry, government, the media, and interest groups. The assessment was developed through personal communications with representatives of interested parties, and through a review of media sources. Lastly, the briefing book provides demographic and socioeconomic data and a discussion of relevant government agencies and activities, all of which may impact waste management practices in Indiana

  8. Louisiana State Briefing Book for low-level radioactive waste management

    International Nuclear Information System (INIS)

    The Louisiana State Briefing Book is one of a series of state briefing books on low-level radioactive waste management practices. It has been prepared to assist state and federal agency officials in planning for safe low-level radioactive waste disposal. The report contains a profile of low-level radioactive waste generators in Louisiana. The profile is a result of a survey of NRC licensees in Louisiana. The briefing book also contains a comprehensive assessment of low-level radioactive waste management issues and concerns as defined by all major interested parties including industry, government, the media, and interest groups. The assessment was developed through personal communications with representatives of interested parties, and through a review of media sources. Lastly, the briefing book provides demographic and socioeconomic data and a discussion of relevant government agencies and activities, all of which may impact waste management practices in Louisiana

  9. Colorado State Briefing Book for low-level radioactive-waste management

    International Nuclear Information System (INIS)

    The Colorado State Briefing Book is one of a series of state briefing books on low-level radioactive waste management practices. It has been prepared to assist state and federal agency officials in planning for safe low-level radioactive waste disposal. The report contains a profile of low-level radioactive waste generators in Colorado. The profile is the result of a survey of NRC licensees in Colorado. The briefing book also contains a comprehensive assessment of low-level radioactive waste management issues and concerns as defined by all major interested parties including industry, government, the media, and interest groups. The assessment was developed through personal communications with representatives of interested parties, and through a review of media sources. Lastly, the briefing book provides demographic and socioeconomic data and a discussion of relevant government agencies and activities, all of which may impact waste management practices in Colorado

  10. Wisconsin State Briefing Book for low-level radioactive waste management

    Energy Technology Data Exchange (ETDEWEB)

    1980-11-01

    The Wisconsin State Briefing Book is one of a series of state briefing books on low-level radioactive waste management practices. It has been prepared to assist state and federal agency officials in planning for safe low-level radioactive waste disposal. The report contains a profile of low-level radioactive waste generators in Wisconsin. The profile is the result of a survey of NRC licensees in Wisconsin. The briefing book also contains a comprehensive assessment of low-level radioactive waste management issues and concerns as defined by all major interested parties including industry, government, the media, and interest groups. The assessment was developed through personal communications with representatives of interested parties, and through a review of media sources. Lastly, the briefing book provides demographic and socioeconomic data and a discussion of relevant government agencies and activities, all of which may impact waste management practices in Wisconsin.

  11. New York State Briefing Book for low-level radioactive-waste management

    International Nuclear Information System (INIS)

    The New York State Briefing Book is one of a series of state briefing books on low-level radioactive waste management practices. It has been prepared to assist state and federal agency officials in planning for safe low-level radioactive waste disposal. The report contains a profile of low-level radioactive waste generators in New York. The profile is the result of a survey of NRC licensees in New York. The briefing book also contains a comprehensive assessment of low-level radioactive waste management issues and concerns as defined by all major interested parties including industry, government, the media, and interest groups. The assessment was developed through personal communications with representatives of interested parties, and through a review of media sources. Lastly, the briefing book provides demographic and socioeconomic data and a discussion of relevant government agencies and activities, all of which may impact waste management practices in New York

  12. Utah State Briefing Book for low-level radioactive waste management

    International Nuclear Information System (INIS)

    The Utah State Briefing Book is one of a series of state briefing books on low-level radioactive waste management practices. It has been prepared to assist state and federal agency officials in planning for safe low-level radioactive waste disposal. The report contains a profile of low-level radioactive waste generators in Utah. The profile is the result of a survey of NRC licensees in Utah. The briefing book also contains a comprehensive assessment of low-level radioactive waste management issues and concerns as defined by all major interested parties including industry, government, the media, and interest groups. The assessment was developed through personal communications with representatives of interested parties, and through a review of media sources. Lastly, the briefing book provides demographic and socioeconomic data and a discussion of relevant government agencies and activities, all of which may impact waste management practices in Utah

  13. Massachusetts State Briefing Book for low-level radioactive waste management

    International Nuclear Information System (INIS)

    The Massachusetts State Briefing Book is one of a series of State briefing books on low-level radioactive waste management practices. It has been prepared to assist State and Federal agency officials in planning for safe low-level radioactive waste disposal. The report contains a profile of low-level radioactive waste generators in Massachusetts. The profile is the result of a survey of NRC licensees in Massachusetts. The briefing book also contains a comprehensive assessment of low-level radioactive waste management issues and concerns as defined by all major interested parties including industry, government, the media, and interest groups. The assessment was developed through personal communications with representatives of interested parties, and through a review of media sources. Lastly, the briefing book provides demographic and socioeconomic data and a discussion of relevant government agencies and activities, all of which may impact waste management practices in Massachusetts

  14. Minnesota State Briefing Book on low-level radioactive waste management

    International Nuclear Information System (INIS)

    The Minnesota State Briefing Book is one of a series of state briefing books on low-level radioactive waste management practices. It has been prepared to assist state and federal agency officials in planning for safe low-level radioactive waste disposal. The report contains a profile of low-level radioactive waste generators in Minnesota. The profile is the result of a survey of Nuclear Regulatory Commission licensees in Minnesota conducted by the Minnesota Department of Health. The briefing book also contains a comprehensive assessment of low-level radioactive waste management issues and concerns as defined by all major interested parties including industry, government, the media, and interest groups. The assessment was developed through personal communications with representatives of interested parties, and through a review of media sources. Lastly, the briefing book provides demographic and socioeconomic data and a discussion of relevant government agencies and activities, all of which may affect waste management practices in Minnesota

  15. Iowa State Briefing Book for low-level radioactive waste management

    International Nuclear Information System (INIS)

    The Iowa State Briefing Book is one of a series of state briefing books on low-level radioactive waste management practices. It has been prepared to assist state and federal agency officials in planning for safe low-level radioactive waste disposal. This report contains a profile of low-level radioactive waste generators in Iowa. The profile is the result of a survey of NRC licensees in Iowa. The briefing book also contains a comprehensive assessment of low-level radioactive waste management issues and concerns as defined by all major interested parties including industry, government, the media, and interest groups. The assessment was developed through personal communications with representatives of interested parties, and through a review of media sources. Lastly, the briefing book provides demographic and socioeconomic data and a discussion of relevant government agencies and activities, all of which may impact waste management practices in Iowa

  16. Vermont State Briefing Book on low-level radioactive waste management

    Energy Technology Data Exchange (ETDEWEB)

    1981-07-01

    The Vermont State Briefing Book is one of a series of state briefing books on low-level radioactive waste management practices. It has been prepared to assist state and federal agency officials in planning for safe low-level radioactive waste disposal. The report contains a profile of low-level radioactive waste generators in Vermont. The profile is the result of a survey of Nuclear Regulatory Commission licensees in Vermont. The briefing book also contains a comprehensive assessment of low-level radioactive waste management issues and concerns as defined by all major interested parties including industry, government, the media, and interest groups. The assessment was developed through personal communications with representatives of interested parties, and through a review of media sources. Lastly, the briefing book provides demographic and socioeconomic data and a discussion of relevant government agencies and activities, all of which may affect waste management practices in Vermont.

  17. Washington State Briefing Book for low-level radioactive waste management

    Energy Technology Data Exchange (ETDEWEB)

    1980-12-01

    The Washington State Briefing Book is one of a series of state briefing books on low-level radioactive waste management practices. It has been prepared to assist state and federal agency officials in planning for safe low-level radioactive waste disposal. The report contains a profile of low-level radioactive waste generators in Washington. The profile is the result of a survey of NRC licensees in Washington. The briefing book also contains a comprehensive assessment of low-level radioactive waste management issues and concerns as defined by all major interested parties including industry, government, the media, and interest groups. The assessment was developed through personal communications with representatives of interested parties, and through a review of media sources. Lastly, the briefing book provides demographic and socioeconomic data and a discussion of relevant government agencies and activities, all of which may impact waste management practices in Washington.

  18. North Dakota State Briefing Book for low-level radioactive waste management

    Energy Technology Data Exchange (ETDEWEB)

    None

    1981-10-01

    The North Dakota State Briefing Book is one of a series of state briefing books on low-level radioactive waste management practices. It has been prepared to assist state and federal agency officials in planning for safe low-level radioactive waste disposal. The report contains a profile of low-level radioactive waste generators in North Dakota. The profile is the result of a survey of NRC licensees in North Dakota. The briefing book also contains a comprehensive assessment of low-level radioactive waste management issues and concerns as defined by all major interested parties including industry, government, the media, and interest groups. The assessment was developed through personal communications with representatives of interested parties, and through a review of media sources. Lastly, the briefing book provides demographic and socioeconomic data and a discussion of relevant government agencies and activities, all of which may impact waste management practices in North Dakota.

  19. Washington State Briefing Book for low-level radioactive waste management

    International Nuclear Information System (INIS)

    The Washington State Briefing Book is one of a series of state briefing books on low-level radioactive waste management practices. It has been prepared to assist state and federal agency officials in planning for safe low-level radioactive waste disposal. The report contains a profile of low-level radioactive waste generators in Washington. The profile is the result of a survey of NRC licensees in Washington. The briefing book also contains a comprehensive assessment of low-level radioactive waste management issues and concerns as defined by all major interested parties including industry, government, the media, and interest groups. The assessment was developed through personal communications with representatives of interested parties, and through a review of media sources. Lastly, the briefing book provides demographic and socioeconomic data and a discussion of relevant government agencies and activities, all of which may impact waste management practices in Washington

  20. Vermont State Briefing Book on low-level radioactive waste management

    International Nuclear Information System (INIS)

    The Vermont State Briefing Book is one of a series of state briefing books on low-level radioactive waste management practices. It has been prepared to assist state and federal agency officials in planning for safe low-level radioactive waste disposal. The report contains a profile of low-level radioactive waste generators in Vermont. The profile is the result of a survey of Nuclear Regulatory Commission licensees in Vermont. The briefing book also contains a comprehensive assessment of low-level radioactive waste management issues and concerns as defined by all major interested parties including industry, government, the media, and interest groups. The assessment was developed through personal communications with representatives of interested parties, and through a review of media sources. Lastly, the briefing book provides demographic and socioeconomic data and a discussion of relevant government agencies and activities, all of which may affect waste management practices in Vermont

  1. Arizona State Briefing Book for low-level radioactive-waste management

    International Nuclear Information System (INIS)

    The Arizona State Briefing Book is one of a series of state briefing books on low-level radioactive waste management practices. It has been prepared to assist state and federal agency officials in planning for safe low-level radioactive waste disposal. The report contains a profile of low-level radioactive waste generators in Arizona. The profile is the result of a survey of NRC licensees in Arizona. The briefing book also contains a comprehensive assessment of low-level radioactive waste management issues and concerns as defined by all major interested parties including industry, government, the media, and interest groups. The assessment was developed through personal communications with representatives of interested parties, and through a review of media sources. Lastly, the briefing book provides demographic and socioeconomic data and a discussion of relevant government agencies and activities, all of which may impact waste management practices in Arizona

  2. New Mexico State Briefing Book for low-level radioactive waste management

    International Nuclear Information System (INIS)

    The New Mexico State Briefing Book is one of a series of state briefing books on low-level radioactive waste management practices. It has been prepared to assist state and federal agency officials in planning for safe low-level radioactive waste disposal. The report contains a profile of low-level radioactive waste generators in New Mexico. The profile is the result of a survey of NRC licensees in New Mexico. The briefing book also contains a comprehensive assessment of low-level radioactive waste management issues and concerns as defined by all major interested parties including industry, government, the media, and interest groups. The assessment was developed through personal communications with representatives of interested parties, and through a review of media sources. Lastly, the briefing book provides demographic and socioeconomic data and a discussion of relevant government agencies and activities, all of which may impact waste management practices in New Mexico

  3. North Carolina State Briefing Book for low-level radioactive waste management

    Energy Technology Data Exchange (ETDEWEB)

    1981-08-01

    The North Carolina State Briefing Book is one of a series of state briefing books on low-level radioactive waste management practices. It has been prepared to assist state and federal agency officials in planning for safe low-level radioactive waste disposal. The report contains a profile of low-level radioactive waste generators in North Carolina. The profile is the result of a survey of NRC licensees in North Carolina. The briefing book also contains a comprehensive assessment of low-level radioactive waste management issues and concerns as defined by all major interested parties including industry, government, the media, and interest groups. The assessment was developed through personal communications with representatives of interested parties, and through a review of media sources. Lastly, the briefing book provides demographic and socioeconomic data and a discussion of relevant government agencies and activities, all of which may impact waste management practices in North Carolina.

  4. Alabama State Briefing Book for low-level radioactive waste management

    International Nuclear Information System (INIS)

    The Alabama State Briefing Book is one of a series of state briefing books on low-level radioactive waste management practices. It has been prepared to assist state and federal agency officials in planning for safe low-level radioactive waste disposal. This report contains a profile of low-level radioactive waste generators in Alabama. The profile is the result of a survey of NRC licensees in Alabama. The briefing book also contains a comprehensive assessment of low-level radioactive waste management issues and concerns as defined by all major interested parties including industry, government, the media, and interest groups. The assessment was developed through personal communications with representatives of interested parties, and through a review of media sources. Lastly, the briefing book provides demographic and socioeconomic data and a discussion of relevant government agencies and activities, all of which may impact waste management practices in Alabama

  5. Pennsylvania State Briefing Book for low-level radioactive waste management

    International Nuclear Information System (INIS)

    The Pennsylvania State Briefing Book is one of a series of state briefing books on low-level radioactive waste management practices. It has been prepared to assist state and federal agency officials in planning for safe low-level radioactive waste disposal. The report contains a profile of low-level radioactive waste generators in Pennsylvania. The profile is the result of a survey of NRC licensees in Pennsylvania. The briefing book also contains a comprehensive assessment of low-level radioactive waste management issues and concerns as defined by all major interested parties including industry, government, the media, and interest groups. The assessment was developed through personal communications with representatives of interested parties, and through a review of media sources. Lastly, the briefing book provides demographic and socioeconomic data and a discussion of relevant government agencies and activities, all of which may impact waste management practices in Pennsylvania

  6. Arkansas State Briefing Book for low-level radioactive-waste management

    International Nuclear Information System (INIS)

    The Arkansas State Briefing Book is one of a series of state briefing books on low-level radioactive waste management practices. It has been prepared to assist state and federal agency officials in planning for safe low-level radioactive waste disposal. The report contains a profile of low-level radioactive waste generators in Arkansas. The profile is the result of a survey of NRC licensees in Arkansas. The briefing book also contains a comprehensive assessment of low-level radioactive waste management issues and concerns as defined by all major interested parties including industry, government, the media, and interest groups. The assessment was developed through personal communications with representatives of interested parties, and through a review of media sources. Lastly, the briefing book provides demographic and socioeconomic data and a discussion of relevant government agencies and activities, all of which may impact waste management practices in Arkansas

  7. New Jersey State Briefing Book for low-level radioactive waste management

    International Nuclear Information System (INIS)

    The New Jersey state Briefing Book is one of a series of State briefing books on low-level radioactive waste management practices. It has been prepared to assist state and federal agency officials in planning for safe low-level radioactive waste disposal. The report contains a profile of low-level radioactive waste generators in New Jersey. The profile is the result of a survey of NRC licensees in New Jersey. The briefing book also contains a comprehensive assessment of low-level radioactive waste management issues and concerns as defined by all major interested parties including industry, government, the media, and interest groups. The assessment was developed through personal communications with representatives of interested parties, and through a review of media sources. Lastly, the briefing book provides demographic and socioeconomic data and a discussion of relevant government agencies and activities, all of which may impact waste management practices in New Jersey

  8. New Jersey State Briefing Book for low-level radioactive waste management

    Energy Technology Data Exchange (ETDEWEB)

    1981-04-01

    The New Jersey state Briefing Book is one of a series of State briefing books on low-level radioactive waste management practices. It has been prepared to assist state and federal agency officials in planning for safe low-level radioactive waste disposal. The report contains a profile of low-level radioactive waste generators in New Jersey. The profile is the result of a survey of NRC licensees in New Jersey. The briefing book also contains a comprehensive assessment of low-level radioactive waste management issues and concerns as defined by all major interested parties including industry, government, the media, and interest groups. The assessment was developed through personal communications with representatives of interested parties, and through a review of media sources. Lastly, the briefing book provides demographic and socioeconomic data and a discussion of relevant government agencies and activities, all of which may impact waste management practices in New Jersey.

  9. Ohio State Briefing Book for low-level radioactive waste management

    Energy Technology Data Exchange (ETDEWEB)

    1981-04-01

    The Ohio State Briefing Book is one of a series of state briefing books on low-level radioactive waste management practices. It has been prepared to assist state and federal agency officials in planning for safe low-level radioactive waste disposal. The report contains a profile of low-level radioactive waste generators in Ohio. The profile is the result of a survey of NRC licensees in Ohio. The briefing book also contains a comprehensive assessment of low-level radioactive waste management issues and concerns as defined by all major interested parties including industry, government, the media, and interest groups. The assessment was developed through personal communications with representatives of interested parties, and through a review of media sources. Lastly, the briefing book provides demographic and socioeconomic data and a discussion of relevant government agencies and activities, all of which may impact waste management practices in Ohio.

  10. Wyoming State Briefing Book for low-level radioactive waste management

    International Nuclear Information System (INIS)

    The Wyoming State Briefing Book is one of a series of state briefing books on low-level radioactive waste management practices. It has been prepared to assist state and federal agency officials in planning for safe low-level radioactive waste disposal. The report contains a profile of low-level radioactive waste generators in Wyoming. The profile is the result of a survey of NRC licensees in Wyoming. The briefing book also contains a comprehensive assessment of low-level radioactive waste management issues and concerns as defined by all major interested parties including industry, government, the media, and interest groups. The assessment was developed through personal communications with representatives of interested parties, and through a review of media sources. Lastly, the briefing book provides demographic and socioeconomic data and a discussion of relevant government agencies and activities, all of which may impact waste management practices in Wyoming

  11. Michigan State Briefing Book for low-level radioactive waste management

    International Nuclear Information System (INIS)

    The Michigan State Briefing Book is one of a series of state briefing books on low-level radioactive waste management practices. It has been prepared to assist state and federal agency officials in planning for safe low-level radioactive waste disposal. The report contains a profile of low-level radioactive waste generators in Michigan. The profile is the result of a survey of NRC licensees in Michigan. The briefing book also contains a comprehensive assessment of low-level radioactive waste management issues and concerns as defined by all major interested parties including industry, government, the media, and interest groups. The assessment was developed through personal communications with representatives of interested parties, and through a review of media sources. Lastly, the discussion of relevant government agencies and activities, all of which may impact waste management practices in Michigan

  12. Puerto Rico State Briefing Book for low-level radioactive waste management

    Energy Technology Data Exchange (ETDEWEB)

    1981-10-01

    The Puerto Rico State Briefing Book is one of a series of state briefing books on low-level radioactive waste management practices. It has been prepared to assist state and federal agency officials in planning for safe low-level radioactive waste disposal. The report contains a profile of low-level radioactive waste generators in Puerto Rico. The profile is the result of a survey of NRC licensees in Puerto Rico. The briefing book also contains a comprehensive assessment of low-level radioactive waste management issues and concerns as defined by all major interested parties including industry, government, the media, and interest groups. The assessment was developed through personal communications with representatives of interested parties, and through a review of media sources. Lastly, the briefing book provides demographic and socioeconomic data and a discussion of relevant government agencies and activities, all of which may impact waste management practices in Puerto Rico.

  13. Mississippi State Briefing Book for low-level radioactive waste management

    Energy Technology Data Exchange (ETDEWEB)

    None

    1981-08-01

    The Mississippi State Briefing Book is one of a series of state briefing books on low-level radioactive waste management practices. It has been prepared to assist state an federal agency officials in planning for safe low-level radioactive waste disposal. The report contains a profile of low-level radioactive waste generators in Mississippi. The profile is the result of a survey of NRC licensees in Mississippi. The briefing book also contains a comprehensive assessment of low-level radioactive waste management issues and concerns as defined by all major interested parties including industry, government, the media, and interest groups. The assessment was developed through personal communications with representatives of interested parties, and through a review of media sources. Lastly, the briefing book provides demographic and socioeconomic data and a discussion of relevant government agencies and activities, all of which may impact waste management practices in Mississippi.

  14. Georgia State Briefing Book for low-level radioactive-waste management

    International Nuclear Information System (INIS)

    The Georgia State Briefing Book is one of a series of state briefing books on low-level radioactive waste management practices. It has been prepared to assist state and federal agency officials in planning for safe low-level radioactive waste disposal. The report contains a profile of low-level radioactive waste generators in Georgia. The profile is the result of a survey of NRC licensees in Georgia. The briefing book also contains a comprehensive assessment of low-level radioactive waste management issues and concerns as defined by all major interested parties including industry, government, the media, and interest groups. The assessment was developed through personal communications with representatives of interested parties, and through a review of media sources. Lastly, the briefing book provides demographic and socioeconomic data and a discussion of relevant government agencies and activities, all of which may impact waste management practices in Georgia

  15. Wisconsin State Briefing Book for low-level radioactive waste management

    International Nuclear Information System (INIS)

    The Wisconsin State Briefing Book is one of a series of state briefing books on low-level radioactive waste management practices. It has been prepared to assist state and federal agency officials in planning for safe low-level radioactive waste disposal. The report contains a profile of low-level radioactive waste generators in Wisconsin. The profile is the result of a survey of NRC licensees in Wisconsin. The briefing book also contains a comprehensive assessment of low-level radioactive waste management issues and concerns as defined by all major interested parties including industry, government, the media, and interest groups. The assessment was developed through personal communications with representatives of interested parties, and through a review of media sources. Lastly, the briefing book provides demographic and socioeconomic data and a discussion of relevant government agencies and activities, all of which may impact waste management practices in Wisconsin

  16. West Virginia State Briefing Book for low-level radioactive waste management

    International Nuclear Information System (INIS)

    The West Virginia State Briefing Book is one of a series of state briefing books on low-level radioactive waste management practices. It has been prepared to assist state and federal agency officials in planning for safe low-level radioactive waste disposal. The report contains a profile of low-level radioactive waste generators in West Virginia. The profile is the result of a survey of NRC licensees in West Virginia. The briefing book also contains a comprehensive assessment of low-level radioactive waste management issues and concerns as defined by all major interested parties including industry, government, the media, and interest groups. The assessment was developed through personal communications with representatives of interested parties, and through a review of media sources. Lastly, the briefing book provides demographic and socioeconomic data and a discussion of relevant government agencies and activities, all of which may impact waste management practices in West Virginia

  17. South Carolina State Briefing Book for low-level radioactive waste management

    Energy Technology Data Exchange (ETDEWEB)

    1981-08-01

    The South Carolina State Briefing Book is one of a series of state briefing books on low-level radioactive waste management practices. It has been prepared to assist state and federal agency officials in planning for safe low-level radioactive waste disposal. The report contains a profile of low-level radioactive waste generators in South Carolina. The profile is the result of a survey of NRC licensees in South Carolina. The briefing book also contains a comprehensive assessment of low-level radioactive waste management issues and concerns as definied by all major interested parties including industry, government, the media, and interest groups. The assessment was developed through personal communications with representatives of interested parties, and through a review of media sources. Lastly, the briefing book provides demographic and socioeconomic data and a discussion of relevant government agencies and activities, all of which may impact waste management practices in South Carolina.

  18. Puerto Rico State Briefing Book for low-level radioactive waste management

    International Nuclear Information System (INIS)

    The Puerto Rico State Briefing Book is one of a series of state briefing books on low-level radioactive waste management practices. It has been prepared to assist state and federal agency officials in planning for safe low-level radioactive waste disposal. The report contains a profile of low-level radioactive waste generators in Puerto Rico. The profile is the result of a survey of NRC licensees in Puerto Rico. The briefing book also contains a comprehensive assessment of low-level radioactive waste management issues and concerns as defined by all major interested parties including industry, government, the media, and interest groups. The assessment was developed through personal communications with representatives of interested parties, and through a review of media sources. Lastly, the briefing book provides demographic and socioeconomic data and a discussion of relevant government agencies and activities, all of which may impact waste management practices in Puerto Rico

  19. South Dakota State Briefing Book for low-level radioactive waste management

    Energy Technology Data Exchange (ETDEWEB)

    1981-10-01

    The South Dakota State Briefing Book is one of a series of state briefing books on low-level radioactive waste management practices. It has been prepared to assist state and federal agency officials in planning for safe low-level radioactive waste disposal. The report contains a profile of low-level radioactive waste generators in South Dakota. The profile is the result of a survey of NRC licensees in South Dakota. The briefing book also contains a comprehensive assessment of low-level radioactive waste management issues and concerns as defined by all major interested parties including industry, government, the media, and interest groups. The assessment was developed through personal communications with representatives of interested parties, and through a review of media sources. Lastly, the briefing book provides demographic and socioeconomic data and a discussion of relevant government agencies and activities, all of which may impact waste management practices in South Dakota.

  20. Idaho State Briefing Book for low-level radioactive-waste management

    International Nuclear Information System (INIS)

    The Idaho State Briefing Book is one of a series of state briefing books on low-level radioactive waste management practices. It has been prepared to assist state and federal agency officials in planning for safe low-level radioactive waste disposal. The report contains a profile of low-level radioactive waste generators in Idaho. The profile is the result of a survey of NRC licensees in Idaho. The briefing book also contains a comprehensive assessment of low-level radioactive waste management issues and concerns as defined by all major interested parties including industry, government, the media, and interest groups. The assessment was developed through personal communications with representatives of interested parties, and through a review of media sources. Lastly, the briefing book provides demographic and socioeconomic data and a discussion of relevant government agencies and activities, all of which may impact waste management practices in Idaho

  1. Oregon State Briefing Book for low-level radioactive waste management

    Energy Technology Data Exchange (ETDEWEB)

    1980-12-01

    The Oregon State Briefing Book is one of a series of state briefing books on low-level radioactive waste management practices. It has been prepared to assist state and federal agency officials in planning for safe low-level radioactive waste disposal. The report contains a profile of low-level radioactive waste generators in Oregon. The profile is a result of a survey of NRC licensees in Oregon. The briefing book also contains a comprehensive assessment of low-level radioactive waste management issues and concerns as defined by all major interested parties including industry, government, the media, and interest groups. The assessment was developed through personal communications with representatives of interested parties, and through a review of media sources. Lastly, the briefing book provides demographic and socioeconomic data and a discussion of relevant government agencies and activities, all of which may impact waste management practices in Oregon.

  2. Florida State Briefing Book for low-level radioactive waste management

    International Nuclear Information System (INIS)

    The Florida State Briefing Book is one of a series of State briefing books on low-level radioactive waste management practices. It has been prepared to assist State and Federal agency officials in planning for safe low-level radioactive waste disposal. The report contains a profile of low-level radioactive waste generators in Florida. The profile is the result of a survey of NRC licensees in Florida. The briefing book also contains a comprehensive assessment of low-level radioactive waste management issues and concerns as defined by all major interested parties including industry, government, the media, and interest groups. The assessment was developed through personal communications with representatives of interested parties, and through a review of media sources. Lastly, the briefing book provides demographic and socioeconomic data and a discussion of relevant government agencies and activities, all of which may impact waste management practices in Florida

  3. Florida State Briefing Book for low-level radioactive-waste management

    International Nuclear Information System (INIS)

    The Florida State Briefing Book is one of a series of state briefing books on low-level radioactive waste management practices. It has been prepared to assist state and federal agency officials in planning for safe low-level radioactive waste disposal. The report contains a profile of low-level radioactive waste generators in Florida. The profile is the result of a survey of NRC licensees in Florida. The briefing book also contains a comprehensive assessment of low-level radioactive waste management issues and concerns as defined by all major interested parties including industry, government, the media, and interest groups. The assessment was developed through personal communications with representatives of interested parties, and through a review of media sources. Lastly, the briefing book provides demographic and socioeconomic data and a discussion of relevant government agencies and activities, all of which may impact waste management practices in Florida

  4. Incineration of hazardous and low-level radioactive waste by a small generator. Final report

    International Nuclear Information System (INIS)

    The results from Arizona State University's study of the feasibility of a small generator incinerating low-level radioactive waste in a pathological incinerator are reported. The research included various aspects of environmental impact, public relations, cost versus benefit, and licensing procedures. Three years of work resulted in a license amendment authorizing the University to incinerate certain hazardous and low-level radioactive wastes. 13 references, 6 figures, 16 tables

  5. Use of compensation and incentives in siting low-level radioactive waste disposal facilities

    International Nuclear Information System (INIS)

    In discussing the use of compensation and incentives in siting low-level radioactive waste disposal facilities, chapters are devoted to: compensation and incentives in disposal facility siting (definitions and effects of compensation and incentives and siting decisions involving the use of compensation and incentives); the impacts of regional and state low-level radioactive waste facilities; the legal framework of compensation; and recommendations regarding the use of compensation

  6. Defining greater-than-class-C low-level radioactive waste

    International Nuclear Information System (INIS)

    The Low-Level Radioactive Waste Policy Amendments Act of 1985 (LLRWPAA) was signed by President Reagan on January 15, 1986. This act requires the federal government to be responsible for the disposal of greater-than-class-C low-level radioactive waste (LLRW) that is generated commercially by state agencies and by federal entities (other than waste generated by atomic weapons research, development, or testing, or by decommissioning of vessels of the nuclear navy). To plan for disposal, the federal government will require estimates of the volume of waste involved and characterization of this waste. A clear definition of greater-than-class-C LLRW is the first step in determining what wastes will be included in the waste to be received by the federal government. This definition will influence major policy decisions to be made for management of such waste. The purpose of this paper is to examine the existing information on greater-than-class-C LLRW in view of the current definition of such waste and potential changes in this definition - for example, an upper limit on the concentrations of radionuclides in LLRW. The paper identifies further information needs to develop a clear definition of such waste for use in federal planning for acceptance of responsibility for disposal of such waste

  7. Identification of technical problems encountered in the shallow land burial of low-level radioactive wastes

    Energy Technology Data Exchange (ETDEWEB)

    Jacobs, D.G.; Epler, J.S.; Rose, R.R.

    1980-03-01

    A review of problems encountered in the shallow land burial of low-level radioactive wastes has been made in support of the technical aspects of the National Low-Level Waste (LLW) Management Research and Development Program being administered by the Low-Level Waste Management Program Office, Oak Ridge National Laboratory. The operating histories of burial sites at six major DOE and five commercial facilities in the US have been examined and several major problems identified. The problems experienced st the sites have been grouped into general categories dealing with site development, waste characterization, operation, and performance evaluation. Based on this grouping of the problem, a number of major technical issues have been identified which should be incorporated into program plans for further research and development. For each technical issue a discussion is presented relating the issue to a particular problem, identifying some recent or current related research, and suggesting further work necessary for resolving the issue. Major technical issues which have been identified include the need for improved water management, further understanding of the effect of chemical and physical parameters on radionuclide migration, more comprehensive waste records, improved programs for performance monitoring and evaluation, development of better predictive capabilities, evaluation of space utilization, and improved management control.

  8. Identification of technical problems encountered in the shallow land burial of low-level radioactive wastes

    International Nuclear Information System (INIS)

    A review of problems encountered in the shallow land burial of low-level radioactive wastes has been made in support of the technical aspects of the National Low-Level Waste (LLW) Management Research and Development Program being administered by the Low-Level Waste Management Program Office, Oak Ridge National Laboratory. The operating histories of burial sites at six major DOE and five commercial facilities in the US have been examined and several major problems identified. The problems experienced st the sites have been grouped into general categories dealing with site development, waste characterization, operation, and performance evaluation. Based on this grouping of the problem, a number of major technical issues have been identified which should be incorporated into program plans for further research and development. For each technical issue a discussion is presented relating the issue to a particular problem, identifying some recent or current related research, and suggesting further work necessary for resolving the issue. Major technical issues which have been identified include the need for improved water management, further understanding of the effect of chemical and physical parameters on radionuclide migration, more comprehensive waste records, improved programs for performance monitoring and evaluation, development of better predictive capabilities, evaluation of space utilization, and improved management control

  9. Texas State Briefing Book for low-level radioactive waste management

    Energy Technology Data Exchange (ETDEWEB)

    1981-08-01

    The Texas State Briefing Book is one of a series of state briefing books on low-level radioactivee waste management practices. It has been prepared to assist state and federal agency officials in planning for safe low-level radioactive waste disposal. The report contains a profile of low-level radioactive waste generators in Texas. The profile is the result of a survey of NRC licensees in Texas. The briefing book also contains a comprehensive assessment of low-level radioactive waste management issues and concerns as defined by all major interested parties including industry, government, the media, and interest groups. The assessment was developed through personal communications with representatives of interested parties, and through a review of media sources. Lastly, the briefing book provides demographic and socioeconomic data and a discussion of relevant government agencies and activities, all of which may impact waste management practices in Texas.

  10. Texas State Briefing Book for low-level radioactive waste management

    International Nuclear Information System (INIS)

    The Texas State Briefing Book is one of a series of state briefing books on low-level radioactivee waste management practices. It has been prepared to assist state and federal agency officials in planning for safe low-level radioactive waste disposal. The report contains a profile of low-level radioactive waste generators in Texas. The profile is the result of a survey of NRC licensees in Texas. The briefing book also contains a comprehensive assessment of low-level radioactive waste management issues and concerns as defined by all major interested parties including industry, government, the media, and interest groups. The assessment was developed through personal communications with representatives of interested parties, and through a review of media sources. Lastly, the briefing book provides demographic and socioeconomic data and a discussion of relevant government agencies and activities, all of which may impact waste management practices in Texas

  11. On the computer system for the burial of low-level radioactive waste

    Energy Technology Data Exchange (ETDEWEB)

    Takahashi, Y.

    1994-12-31

    Rokkasho Low-Level Radioactive waste Disposal Center, which buries the low-level radioactive waste produced from nuclear power plants all over Japan, started operation in December, 1992. This report introduces the computer system developed for controlling a tremendous volume of waste disposal-related data which include that for the radioactive-waste containing drums to be buried regarding whether they can satisfy the technical standards for burial, that for the disposal operation such as the positions of drum placement within the facility, etc., that for the environmental monitoring around the disposal site, etc.

  12. Disposal of low-level radioactive waste. Impact on the medical profession

    International Nuclear Information System (INIS)

    During 1985, low-level radioactive waste disposal has become a critical concern. The issue has been forced by the threatened closure of the three commercial disposal sites. The medical community has used radioactive isotopes for decades in nuclear medicine, radiation therapy, radioimmunoassay, and biomedical research. Loss of disposal capacity for radioactive wastes generated by these activities, by the suppliers of radioisotopes, and by pharmaceutical companies will have a profound impact on the medical profession

  13. Opting for cooperation: A Canadian approach to siting a low-level radioactive waste management facility

    Energy Technology Data Exchange (ETDEWEB)

    Rennick, P.H. (Rennick and Associates, Burlington, Ontario (Canada))

    1991-01-01

    In 1986, an independent task force was established by the Canadian government to design and implement a cooperative siting process to seek a willing community for a low-level radioactive waste (LLRW) management facility. Throughout its work, the task force recognized that social and political issues involved in siting activities can be pivotal and are often more difficult to resolve than technical issues. Traditional facility siting problems were characterized by the task force. To address the siting issues, the cooperative process illustrated in the paper incorporates five principles and five safeguards. After 23 months, the time it took to implement and report on the first three phases of the cooperative process, three potential host communities have formally indicated a willingness to continue in the process. The three source communities (where the bulk of the LLRW is located) will also be involved in phase 4 to develop plans of action for cleanup of the material.

  14. New Hampshire State Briefing Book for low-level radioactive waste management

    International Nuclear Information System (INIS)

    The New Hampshire State Briefing Book is one of a series of state briefing books based on low-level radioactive waste management practices. It has been prepared to assist state and federal agency officials in planning for safe low-level radioactive waste generators in New Hampshire. The profile is the result of a survey of NRC licensees in New Hampshire. The briefing book also contains a comprehensive assessment of low-level radioactive waste management issues and concerns as defined by all major interested parties including industry, government, the media, and interest groups. The assessment was developed through personal communications with representatives of interested parties, and through a review of media sources. Lastly, the briefing book provides demographic and socioeconomic data and a discussion of relevant government agencies and activities, all of which may impact waste management practices in New Hampshire

  15. Alaska State Briefing Book for low-level radioactive waste management

    International Nuclear Information System (INIS)

    The Alaska State Briefing Book is one of a series of state briefing books on low-level radioactive waste management practices. It has been prepared to assist state and federal agency officials in planning for safe low-level radioactive waste generators in Alaska. The profile is the result of a survey of NRC licensees in Alaska. The briefing book also contains a comprehensive assessment of low-level radioactive waste management issues and concerns as defined by all major interested parties including industry, government, the media, and interest groups. The assessment was developed through personal communications with representatives of interested parties, and through a review of media sources. Lastly, the briefing book provides demographic and socioeconomic data and a discussion of relevant government agencies and activities, all of which may impact waste management practices in Alaska

  16. Extended storage of low-level radioactive waste: potential problem areas

    International Nuclear Information System (INIS)

    If a state or state compact does not have adequate disposal capacity for low-level radioactive waste (LLRW) by 1986 as required by the Low-Level Waste Policy Act, then extended storage of certain LLRW may be necessary. In this report, extended storage of LLRW is considered in order to determine for the Nuclear Regulatory Commission areas of concern and actions recommended to resolve these concerns. The focus is on the properties and performance of the waste form and waste container. Storage alternatives are considered in order to characterize the likely storage environments for these wastes. The areas of concern about extended storage of LLRW are grouped into two categories: (1) Performance of the waste form and/or container during storage, e.g., radiolytic gas generation, radiation-enhanced degradation of polymeric materials, and corrosion. (2) Effects of extended storage on the properties of the waste form and/or container that are important after storage (e.g., radiation-induced embrittlement of high-density polyethylene and the weakening of steel containers resulting from corrosion). A discussion is given of additional information and actions required to address these concerns

  17. Toward a national policy for managing low-level radioactive waste: key issues and recommendations

    International Nuclear Information System (INIS)

    The Conservation Foundation, a not-for-profit research and public education organization, asked individuals with diverse backgrounds and viewpoints to come together under Foundation leadership as a Dialogue Group on Low-Level Radioactive Waste Management. The group, including persons who represent waste generators, concerned citizens, state regulators, and environmentalists, met over an 18-month period to discuss issues crucial to the development of a national policy on low-level wastes. The Dialogue Group agreed that three principles, if accepted broadly, would form the basis of a sound national policy for managing low-level radioactive wastes: with proper implementation, technology exists to manage low-level waste safely; generators and their customers should pay disposal costs; and greater public involvement at all stages can improve the disposal system. These principles acted as polestars for the group as it worked toward a series of policy recommendations in four main areas: (1) cleaning up closed commercial sites; (2) remodeling a system for defining and classifying low-level radioactive waste; (3) siting new low-level waste disposal facilities; and (4) decommissioning, long-term care, and liability. This report presents an extensive discussion of these recommendations covering qualifications, limitations, and alternatives

  18. Status of low-level radioactive waste requirements development in the Department of Energy

    International Nuclear Information System (INIS)

    The Department of Energy (DOE) manages its low-level radioactive waste in accordance with the policies, guidelines and requirements specified in DOE Order 5820.2A, 'Radioactive Waste Management', issued in 1988. Since that time, DOE has reorganized its waste management programs, instituted new policies with emphasis on environmental protection, safety and health protection, and strengthened the management of hazardous waste. An evaluation of DOE Order 5820.2A has shown the need to revise the Order in light of recent organizational and operational policies. In addition, the Order should be more comprehensive, clarify organizational responsibilities, and be more compatible with similar Federal regulations. A revision could also integrate recent interim guidance for management of low-level waste (LLW), such as determination of material as radioactive waste, management of naturally-occurring radioactive material, use of commercial disposal facilities, and the management of special case waste that is unique to DOE. (author)

  19. Radioactive waste management: a summary of state laws and administration. National Low-Level Radioactive Waste Management Program. Revision 6

    International Nuclear Information System (INIS)

    This is the sixth update of ''Radioactive Waste Management: A Summary of State Laws and Administration.'' It completely replaces the fifth update (15 September 1984). The updated report covers low-level radioactive waste compacts, and the administration, the legislature and the laws related to radioactive waste management in each of the fifty states. The report is organized by low-level waste compact regions. Each section begins with a description of the low-level waste compact, followed by reports on each state within the region. There are also sections for states which have made plans to dispose of waste independently of a compact, and for those states which have not yet declared their intentions. The report on each compact is divided into four sections: Cover Page, Chair Organization, State Delegations, and Compact

  20. Maryland and District of Columbia State Briefing Book for low-level radioactive waste management

    International Nuclear Information System (INIS)

    The District of Columbia and Maryland State Briefing Book is one of a series of state briefing books on low-level radioactive waste management practices. It has been prepared to assist state and federal agency officials in planning for safe low-level radioactive waste disposal. The report contains a profile of low-level radioactive waste generators in the District of Columbia and Maryland. The profile is the result of a survey of NRC licensees in the District of Columbia and Maryland. The briefing book also contains a comprehensive assessment of low-level radioactive waste management issues and concerns as defined by all major interested parties including industry, government, the media, and interest groups. The assessment was developed through personal communications with representatives of interested parties, and through a review of media sources. Lastly, the briefing book provides demographic and socioeconomic data and a discussion of relevant government agencies and activities, all of which may impact waste management practices in the District of Columbia and Maryland

  1. An update of a national database of low-level radioactive waste in Canada

    Energy Technology Data Exchange (ETDEWEB)

    De, P.L.; Barker, R.C. [Atomic Energy Canada Ltd. Research, Ottawa, Ontario (Canada). Low-Level Radioactive Waste Management Office

    1993-03-01

    This paper gives an overview and update of a national database of low-level radioactive waste in Canada. To provide a relevant perspective, Canadian data are compared with US data on annual waste arisings and with disposal initiatives of the US compacts and states. Presented also is an assessment of the data and its implications for disposal solutions in Canada.

  2. Modelling and assessment work in support of the Drigg low-level radioactive waste disposal site

    International Nuclear Information System (INIS)

    Associated with low-level radioactive waste disposal operations at Drigg in Cumbria is a programme of technical support work. The role of this work in the recent review of the site authorisation is described, with particular emphasis on the hydrogeological modelling and radiological assessment studies. The scope of the ongoing technical programme is described. (author)

  3. Management of low-level natural radioactivity wastes of phosphate mining and processing

    International Nuclear Information System (INIS)

    Redistribution of the uranium-series radionuclides associated with phosphate deposits produces what are, in effect, low-level radioactive wastes. Proposed management of these materials involved (1) restricting by-product uses to applications not causing significant exposures to man; and (2) returning other material to the land with simulation of the natural radioactivity depth profile by covering high activity overburden, tailings, clays, gypsum and other radioactivity-bearing wastes with a lower activity overburden layer. Radon flux models are being developed to aid design of materials placement

  4. Low-level radioactive waste management at Argonne National Laboratory-East

    International Nuclear Information System (INIS)

    This paper is an overview of the low-level radioactive waste management practices and treatment systems at Argonne National Laboratory - East (ANL-E). It addresses the systems, processes, types of waste treated, and the status and performance of the systems. ANL-E is a Department of Energy laboratory that is engaged in a variety of research projects, some of which generate radioactive waste, in addition a significant amount of radioactive waste remains from previous projects and decontamination and decommissioning of facilities where this work was performed

  5. Anaerobic digestion of low-level radioactive cellulosic and animal wastes

    International Nuclear Information System (INIS)

    A preliminary process design and a cost estimate have been made for a volume reduction plant for low-level, solid radioactive wastes generated at ORNL. The process is based on extension of existing anaerobic digestion technology and on laboratory studies indicating the feasibiity of this technology for digestion of the organic portion of low-level, solid radioactive wastes. A gaseous effluent (CO2 and CH4) is vented in the process, and a liquid ffluent containing undigested solids is filtered to remove solids, which are buried. The liquid is discharged to the low-level liquid waste system at ORNL. Overall volume reduction of solid waste by this process is estimated to be approximately 20:1. Costs appear to be comparable to costs for compaction. The process design is conservative, and several potential improvements which could increase efficiency are discussed in this report

  6. Recommended regulatory program plan for low-level radioactive waste management in Maryland

    International Nuclear Information System (INIS)

    The National Program for Low-Level Radioactive Waste Management was instituted by the US Department of Energy to assist the states in carrying out this new federal policy. Based on the premise that the safe disposal of low-level waste is technologically feasible and that states have the necessary degree of authority to set management policy, the National Program is helping them to develop a responsive, comprehensive regulatory program. The State of Maryland is actively engaged with the National Program in its efforts to form a comprehensive management program. The purpose of this plan is to review existing statutory and regulatory program responsibilities and provide a recommended management scheme for low-level radioactive waste

  7. 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.

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

    International Nuclear Information System (INIS)

    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

  9. Experiment close out of lysimeter field testing of low-level radioactive waste forms

    International Nuclear Information System (INIS)

    The Field Lysimeter Investigations: Low-Level Waste Data Base Development Program is obtaining information on the performance of radioactive waste forms. These experiments were recently shut down and the contents of the lysimeters have been examined in accordance with a detailed waste form and soil sampling plan. Ion-exchange resins from a commercial nuclear power station were solidified into waste forms using portland cement and vinyl ester-styrene. These waste forms were tested to (a) obtain information on performance of waste forms in typical disposal environments, (b) compare field results with bench leach studies, (c) develop a low-level waste data base for use in performance assessment source term calculations, and (d) apply the DUST computer code to compare predicted cumulative release to actual field data. The program, funded by the Nuclear Regulatory Commission (NRC), includes observed radio nuclide releases from waste forms in field lysimeters at two test sites over 10 years of successful operation. The purpose of this paper is to present the results of the examination of waste forms and soils of the two lysimeter arrays after shut down. During this examination, the waste forms were characterized after removal from the lysimeters and the results compared to the findings of the original characterizations. Vertical soil cores were taken from the soil columns and analyzed with radiochemistry to define movement of radionuclides in the soils after release from the waste forms. A comparison is made of the DUST and BLT code predictions of releases and movement, using recently developed partition coefficients and leachate measurements, to actual radio nuclide movement through the soil columns as determined from these core analyses

  10. Low-level radioactive waste from commercial nuclear reactors. Volume 1. Recommendations for technology developments with potential to significantly improve low-level radioactive waste management

    International Nuclear Information System (INIS)

    The overall task of this program was to provide an assessment of currently available technology for treating commercial low-level radioactive waste (LLRW), to initiate development of a methodology for choosing one technology for a given application, and to identify research needed to improve current treatment techniques and decision methodology. The resulting report is issued in four volumes. Volume 1 provides an executive summary and a general introduction to the four-volume set, in addition to recommendations for research and development (R and D) for low-level radioactive waste (LLRW) treatment. Generic, long-range, and/or high-risk programs identified and prioritized as needed R and D in the LLRW field include: (1) systems analysis to develop decision methodology; (2) alternative processes for dismantling, decontaminating, and decommissioning; (3) ion exchange; (4) incinerator technology; (5) disposal technology; (6) demonstration of advanced technologies; (7) technical assistance; (8) below regulatory concern materials; (9) mechanical treatment techniques; (10) monitoring and analysis procedures; (11) radical process improvements; (12) physical, chemical, thermal, and biological processes; (13) fundamental chemistry; (14) interim storage; (15) modeling; and (16) information transfer. The several areas are discussed in detail

  11. A low-level radioactive waste disposal facility siting simulation exercise

    Energy Technology Data Exchange (ETDEWEB)

    Rope, R.C.; Roop, R.D.

    1986-01-01

    The DOE Low-Level Waste Management Program has developed the Low-Level Radioactive Waste Siting Simulation, a role playing exercise designed to facilitate the process of siting Low-Level Waste (LLW) disposal facilities. This paper describes the development, content, and usefulness of the siting simulation. The simulation consists of two sessions: in the first, participants negotiate the selection of siting criteria, and in the second, a preferred site is chosen from three suitable candidate sites. Several workshops involving the simulation have been conducted for persons involved in the planning of LLW management activities. The simulation is useful as a training tool, a vehicle to foster communication, and a step toward consensus building and conflict resolution. The siting simulation is now available through the DOE Low-Level Waste Management Program for use by states, regional compacts, and other organizations involved in the development of LLW disposal facilities. 6 refs.

  12. Regulatory authority of the Rocky Mountain states for low-level radioactive waste packaging and transportation

    International Nuclear Information System (INIS)

    The newly-formed Rocky Mountain Low-Level Radioactive Waste Compact is an interstate agreement for the management of low-level radioactive waste (LLW). Eligible members of the compact are Arizona, Colorado, Nevada, New Mexico, Utah, and Wyoming. Each state must ratify the compact within its legislature for the compact to become effective in that state and to make that state a full-fledged member of the compact. By so adopting the compact, each state agrees to the terms and conditions specified therein. Among those terms and conditions are provisions requiring each member state to adopt and enforce procedures requiring low-level waste shipments originating within its borders and destined for a regional facility to conform to packaging and transportation requirements and regulations. These procedures are to include periodic inspections of packaging and shipping practices, periodic inspections of waste containers while in the custody of carriers and appropriate enforcement actions for violations. To carry out this responsibility, each state must have an adequate statutory and regulatory inspection and enforcement authority to ensure the safe transportation of low-level radioactive waste. Three states in the compact region, Arizona, Utah and Wyoming, have incorporated the Department of Transportation regulations in their entirety, and have no published rules and regulations of their own. The other states in the compact, Colorado, Nevada and New Mexico all have separate rules and regulations that incorporate the DOT regulations. A brief description of the regulatory requirements of each state is presented

  13. Strategy and plan for siting and licensing a Rocky Mountain low-level radioactive waste facility

    International Nuclear Information System (INIS)

    In 1979, the States of Nevada and Washington temporarily closed their commercial low-level radioactive waste (LLW) disposal facilities and South Carolina, the only other state hosting such a facility, restricted the amount of waste it would accept. All three states then announced that they did not intend to continue the status quo of accepting all of the country's commercial low-level radioactive waste. Faced with this situation, other states began considering alternative LLW management and disposal options. In the Rocky Mountain region, this evolved into discussions for the development of an interstate compact to manage low-level waste. Inherent in this management plan was a strategy to site and license a new LLW disposal facility for the Rocky Mountain region. The Rocky Mountain Low-Level Radioactive Waste Compact was negotiated over the course of a year, with final agreement on the language of the compact agreed to in early 1982. States eligible to join the compact are Arizona, Colorado, Nevada, New Mexico, Utah, and Wyoming. Colorado adopted the compact into law in 1982, and Nevada, New Mexico and Wyoming adopted it in 1983. Utah has joined the Northwest Compact, although it may decide to join the Rocky Mountain Compact after a new disposal facility is developed for the region. Arizona has taken no action on the Rocky Mountain Compact

  14. Strategy and plan for siting and licensing a Rocky Mountain low-level radioactive waste facility

    Energy Technology Data Exchange (ETDEWEB)

    Whitman, M.

    1983-09-01

    In 1979, the States of Nevada and Washington temporarily closed their commercial low-level radioactive waste (LLW) disposal facilities and South Carolina, the only other state hosting such a facility, restricted the amount of waste it would accept. All three states then announced that they did not intend to continue the status quo of accepting all of the country's commercial low-level radioactive waste. Faced with this situation, other states began considering alternative LLW management and disposal options. In the Rocky Mountain region, this evolved into discussions for the development of an interstate compact to manage low-level waste. Inherent in this management plan was a strategy to site and license a new LLW disposal facility for the Rocky Mountain region. The Rocky Mountain Low-Level Radioactive Waste Compact was negotiated over the course of a year, with final agreement on the language of the compact agreed to in early 1982. States eligible to join the compact are Arizona, Colorado, Nevada, New Mexico, Utah, and Wyoming. Colorado adopted the compact into law in 1982, and Nevada, New Mexico and Wyoming adopted it in 1983. Utah has joined the Northwest Compact, although it may decide to join the Rocky Mountain Compact after a new disposal facility is developed for the region. Arizona has taken no action on the Rocky Mountain Compact.

  15. Operational and regulatory impacts of regional management on transportation of commercial low-level radioactive waste

    International Nuclear Information System (INIS)

    The 96th Congress of the United States, as part of the Low-level Radioactive Waste Policy Act of 1980 (Public Law 96-573), instructed the Secretary of the Department of Energy (DOE) to prepare a report on the current US low-level waste management situation and the conditions and requirements for management on a regional basis. The Transportation Technology Center has compared the transportation requirement and regional management scenarios for commercial low-level radioactive waste in support of the DOE response to this instruction. Using 1979 low-level waste volumes shipped to commercial burial grounds and six management regions postulated by DOE, transportation requirements were estimated and compared for the two management scenarios in terms of cumulative shipping distance and transportation cost. Effects of these results on the demand for transportation services and equipment and on population risks were considered. Finally, current regulatory issues and the potential effects of regional management on regulation of low-level waste transportation were reviewed

  16. Adopting plasma pyrolysis for management of low-level solid radioactive waste in India

    International Nuclear Information System (INIS)

    Since Plasma Pyrolysis of Low-Level Solid Radioactive Waste has the potential of reducing waste volumes by a factor of up to 1000:1, the new technology is seen as a sound engineering and economic option for managing voluminous low-active wastes. Development and adoption of such technique, to replace existing methods of Low-Level Solid Radioactive Waste management, is borne out of a compelling need to conserve disposal space. While Plasma-based systems are already in use for disposal of medical, toxic and other industrial wastes, the level of maturity is yet to be attained in their radioactive applications. A Prototype Plasma Pyrolysis Unit is being set up in India which, after extensive trials, will function as a full-scale plant for the volume reduction of Low-Level Solid Radioactive Wastes. This paper deals with the transition philosophy from the current techniques to the Plasma-based process. The design and engineering of the proposed facility and various system components is also briefly touched upon. (author)

  17. Discussion paper: siting a low-level radioactive waste disposal facility in the Central Interstate Low-Level Radioactive Waste Compact region. A model for other regions

    International Nuclear Information System (INIS)

    While this paper is intended to be broad enough in scope to cover the concerns and implementation guidelines of any compact commission, the focus will be on the procedures and guidelines that must be followed under the terms of the Central Interstate Low-Level Radioactive Waste Compact. This is not necessarily an endorsement of the Central States Compact approach to siting but is rather an attempt to discuss the siting process by using an existing compact as an example. As stated earlier, each compact commission will have to follow the specific guidelines of its compact. Many of the procedures to be followed and technical standards to be considered, however, apply to all the compacts

  18. Discussion paper: siting a low-level radioactive waste disposal facility in the Central Interstate Low-Level Radioactive Waste Compact region. A model for other regions

    Energy Technology Data Exchange (ETDEWEB)

    Peery, R.J.

    1984-07-01

    While this paper is intended to be broad enough in scope to cover the concerns and implementation guidelines of any compact commission, the focus will be on the procedures and guidelines that must be followed under the terms of the Central Interstate Low-Level Radioactive Waste Compact. This is not necessarily an endorsement of the Central States Compact approach to siting but is rather an attempt to discuss the siting process by using an existing compact as an example. As stated earlier, each compact commission will have to follow the specific guidelines of its compact. Many of the procedures to be followed and technical standards to be considered, however, apply to all the compacts.

  19. Use of engineered soils beneath low-level radioactive waste disposal facilities

    Energy Technology Data Exchange (ETDEWEB)

    Sandford, T.C.; Humphrey, D.N.; DeMascio, F.A. [Univ. of Maine, Orono, ME (United States). Dept. of Civil Engineering

    1993-03-01

    Current regulations are oriented toward locating low-level radioactive waste disposal facilities on sites that have a substantial natural soil barrier and are above the groundwater table. In some of the northern states, like Maine, the overburden soils are glacially derived and in most places provide a thin cover over bedrock with a high groundwater table. Thus, the orientation of current regulations can severely limit the availability of suitable sites. A common characteristic of many locations in glaciated regions is the rapid change of soil types that may occur and the heterogeneity within a given soil type. In addition, the bedrock may be fractured, providing avenues for water movement. A reliable characterization of these sites can be difficult, even with a detailed subsurface exploration program. Moreover, fluctuating groundwater and frost as well as the natural deposition processes have introduced macro features such as cracks, fissures, sand and silt seams, and root holes. The significant effect that these macro features have on the permeability and adsorptive capacity of a large mass is often ignored or poorly accounted for in the analyses. This paper will examine an alternate approach, which is to use engineered soils as a substitute for some or all of the natural soil and to treat the fractures in the underlying bedrock. The site selection would no longer be primarily determined by the natural soil and rock and could even be placed in locations with no existing soils. Engineered soils can be used for below- or aboveground facilities.

  20. Greater-than-Class C low-level radioactive waste transportation regulations and requirements study

    International Nuclear Information System (INIS)

    The purpose of this report is to identify the regulations and requirements for transporting greater-than-Class C (GTCC) low-level radioactive waste (LLW) and to identify planning activities that need to be accomplished in preparation for transporting GTCC LLW. The regulations and requirements for transporting hazardous materials, of which GTCC LLW is included, are complex and include several Federal agencies, state and local governments, and Indian tribes. This report is divided into five sections and three appendices. Section 1 introduces the report. Section 2 identifies and discusses the transportation regulations and requirements. The regulations and requirements are divided into Federal, state, local government, and Indian tribes subsections. This report does not identify the regulations or requirements of specific state, local government, and Indian tribes, since the storage, treatment, and disposal facility locations and transportation routes have not been specifically identified. Section 3 identifies the planning needed to ensure that all transportation activities are in compliance with the regulations and requirements. It is divided into (a) transportation packaging; (b) transportation operations; (c) system safety and risk analysis, (d) route selection; (e) emergency preparedness and response; and (f) safeguards and security. This section does not provide actual planning since the details of the Department of Energy (DOE) GTCC LLW Program have not been finalized, e.g., waste characterization and quantity, storage, treatment and disposal facility locations, and acceptance criteria. Sections 4 and 5 provide conclusions and referenced documents, respectively

  1. Methods for verifying compliance with low-level radioactive waste acceptance criteria

    International Nuclear Information System (INIS)

    This report summarizes the methods that are currently employed and those that can be used to verify compliance with low-level radioactive waste (LLW) disposal facility waste acceptance criteria (WAC). This report presents the applicable regulations representing the Federal, State, and site-specific criteria for accepting LLW. Typical LLW generators are summarized, along with descriptions of their waste streams and final waste forms. General procedures and methods used by the LLW generators to verify compliance with the disposal facility WAC are presented. The report was written to provide an understanding of how a regulator could verify compliance with a LLW disposal facility's WAC. A comprehensive study of the methodology used to verify waste generator compliance with the disposal facility WAC is presented in this report. The study involved compiling the relevant regulations to define the WAC, reviewing regulatory agency inspection programs, and summarizing waste verification technology and equipment. The results of the study indicate that waste generators conduct verification programs that include packaging, classification, characterization, and stabilization elements. The current LLW disposal facilities perform waste verification steps on incoming shipments. A model inspection and verification program, which includes an emphasis on the generator's waste application documentation of their waste verification program, is recommended. The disposal facility verification procedures primarily involve the use of portable radiological survey instrumentation. The actual verification of generator compliance to the LLW disposal facility WAC is performed through a combination of incoming shipment checks and generator site audits

  2. Methods for verifying compliance with low-level radioactive waste acceptance criteria

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1993-09-01

    This report summarizes the methods that are currently employed and those that can be used to verify compliance with low-level radioactive waste (LLW) disposal facility waste acceptance criteria (WAC). This report presents the applicable regulations representing the Federal, State, and site-specific criteria for accepting LLW. Typical LLW generators are summarized, along with descriptions of their waste streams and final waste forms. General procedures and methods used by the LLW generators to verify compliance with the disposal facility WAC are presented. The report was written to provide an understanding of how a regulator could verify compliance with a LLW disposal facility`s WAC. A comprehensive study of the methodology used to verify waste generator compliance with the disposal facility WAC is presented in this report. The study involved compiling the relevant regulations to define the WAC, reviewing regulatory agency inspection programs, and summarizing waste verification technology and equipment. The results of the study indicate that waste generators conduct verification programs that include packaging, classification, characterization, and stabilization elements. The current LLW disposal facilities perform waste verification steps on incoming shipments. A model inspection and verification program, which includes an emphasis on the generator`s waste application documentation of their waste verification program, is recommended. The disposal facility verification procedures primarily involve the use of portable radiological survey instrumentation. The actual verification of generator compliance to the LLW disposal facility WAC is performed through a combination of incoming shipment checks and generator site audits.

  3. Water balance at a low-level radioactive-waste disposal site

    Science.gov (United States)

    Healy, R.W.; Gray, J.R.; De Vries, G. M.; Mills, P.C.

    1989-01-01

    The water balance at a low-level radioactive-waste disposal site in northwestern Illinois was studied from July 1982 through June 1984. Continuous data collection allowed estimates to be made for each component of the water-balance equation independent of other components. The average annual precipitation was 948 millimeters. Average annual evapotranspiration was estimated at 637 millimeters, runoff was 160 millimeters, change in water storage in a waste-trench cover was 24 millimeters, and deep percolation was 208 millimeters. The magnitude of the difference between precipitation and all other components (81 millimeters per year) indicates that, in a similar environment, the water-budget method would be useful in estimating evapotranspiration, but questionable for estimation of other components. Precipitation depth and temporal distribution had a very strong effect on all other components of the water-balance equation. Due to the variability of precipitation from year to year, it appears that two years of data are inadequate for characterization of the long-term average water balance at the site.

  4. Comprehensive low-level radioactive waste management plan for the Commonwealth of Kentucky

    Energy Technology Data Exchange (ETDEWEB)

    Carr, R.M.; Mills, D.; Perkins, C.; Riddle, R.

    1984-03-01

    Part I of the Comprehensive Low-Level Radioactive Waste Management Plan for the Commonwealth of Kentucky discusses the alternatives that have been examined to manage the low-level radioactive waste currently generated in the state. Part II includes a history of the commercial operation of the Maxey Flats Nuclear Waste Disposal Site in Fleming County, Kentucky. The reasons for closure of the facility by the Human Resources Cabinet, the licensing agency, are identified. The site stabilization program managed by the Natural Resources and Environmental Protection Cabinet is described in Chapter VI. Future activities to be conducted at the Maxey Flats Disposal Site will include site stabilization activities, routine operations and maintenance, and environmental monitoring programs as described in Chapter VII.

  5. Role of the state in the regulation of low-level radioactive waste

    International Nuclear Information System (INIS)

    This document describes the role of the State in the regulation of low-level radioactive waste in the context of the Low-Level Radioactive Waste Policy Act of 1980 (Public Law 96-573), which recognizes that the States are responsible for disposal of the waste and as such may develop interstate compacts. The perspective is the present national regulatory framework for the waste system, including generation, transport, treatment, storage and disposal. Although not a definitive legal statement of the area in which States may properly act, the regulatory authority of all Compact States as Agreement States, States with a limited Agreement, and as non-Agreement States is described. The analysis is based on the assumption that the disposal site is State land

  6. Comprehensive low-level radioactive waste management plan for the Commonwealth of Kentucky

    International Nuclear Information System (INIS)

    Part I of the Comprehensive Low-Level Radioactive Waste Management Plan for the Commonwealth of Kentucky discusses the alternatives that have been examined to manage the low-level radioactive waste currently generated in the state. Part II includes a history of the commercial operation of the Maxey Flats Nuclear Waste Disposal Site in Fleming County, Kentucky. The reasons for closure of the facility by the Human Resources Cabinet, the licensing agency, are identified. The site stabilization program managed by the Natural Resources and Environmental Protection Cabinet is described in Chapter VI. Future activities to be conducted at the Maxey Flats Disposal Site will include site stabilization activities, routine operations and maintenance, and environmental monitoring programs as described in Chapter VII

  7. Site selection and licensing issues: Southwest Compact low-level radioactive waste disposal site

    Energy Technology Data Exchange (ETDEWEB)

    Grant, J.L.

    1989-11-01

    The low-level radioactive waste disposal site in California is being selected through a three-phase program. Phase 1 is a systematic statewide, regional, and local screening study. This program was conducted during 1986 and 1987, and culminated in the selection of three candidate sites fur further study. The candidate sites are identified as the Panamint, Silurian, and Ward Valley sites. Phase 2 comprises site characterization and environmental and socio-economic impact study activities at the three candidate sites. Based upon the site characterization studies, the candidate sites are ranked according to the desirability and conformance with regulatory requirements. Phase 3 comprises preparation of a license application for the selected candidate site. The license application will include a detailed characterization of the site, detailed design and operations plans for the proposed facility, and assessments of potential impacts of the site upon the environment and the local communities. Five types of siting criteria were developed to govern the site selection process. These types are: technical suitability exclusionary criteria, high-avoidance criteria beyond technical suitability requirements, discretionary criteria, public acceptance, and schedule requirements of the LLWR Policy Act Amendments. This paper discusses the application of the hydrological and geotechnical criteria during the siting and licensing studies in California. These criteria address site location and performance, and the degree to which present and future site behavior can be predicted. Primary regulatory requirements governing the suitability of a site are that the site must be hydrologically and geologically simple enough for the confident prediction of future behavior, and that the site must be stable enough that frequent or intensive maintenance of the closed site will not be required. This paper addresses the methods to measure site suitability at each stage of the process, methods to

  8. Experience with disposal of low-level radioactive waste: building confidence for and against the regulations

    Energy Technology Data Exchange (ETDEWEB)

    Kastenberg, W.E.; Lowenthal, M.D. [University of California, Dept. of Nuclear Engineering, CA (United States)

    2001-07-01

    Following the controversy regarding the potential use of the Ward Valley site in California as a low level radioactive waste facility, an Advisory Group and a Scientific Panel were formed to recommend alternatives to the Governor. During the course of the Group and Panel deliberations, the arguments for and against near surface burial and waste classification were crystallized. In this paper we discuss the bases upon which the arguments were formed and what we can learn from them. (author)

  9. Near-field/far-field interface of a near-surface low level radioactive waste site

    OpenAIRE

    Beadle, Ian R.; S. Boult; Graham, J.; Hand, V. L.; Humphreys, Paul; Trivedi, D. P.; Warwick, P.

    2004-01-01

    Experimental and Modelling studies have been used to investigate the biogeochemical processes occurring at the interface zone between the near-field and far-field of the Drigg Low- Level radioactive Waste (LLW) trenches. These have led to a conceptual model of interface biogeochemistry, which has subsequently been modelled by the BNFL code known as the Generalised Repository Model (GRM). GRM simulations suggest that as organic rich leachate migrates into the far-field, iron III minerals such ...

  10. Insuring low-level radioactive waste sites: Past, present, and future

    Energy Technology Data Exchange (ETDEWEB)

    Viveiros, G.F. III

    1989-11-01

    The primary purpose of the paper is to provide information concerning the availability of nuclear liability insurance coverage under the Facility Form for low-level radioactive waste facilities only. The paper describes the past history of insurers and their merger into the Nuclear Atomic Energy Liability Underwriters (MAELU). The paper discusses the coverage afforded, underwriting suspension, and work the nuclear insurance pools are doing to lift the suspension.

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

    International Nuclear Information System (INIS)

    The northeastern states, with support of the Coalition of Northeastern Governors (CONEG), are developing compact(s) for the disposal and management of low-level radioactive waste (LLRW) generated in the eleven northeastern states (Connecticut, Delaware, Maine, Maryland, Massachusetts, New Hampshire, New Jersey, New York, Pennsylvania, Rhode Island, and Vermont). The Technical Subcommittee has made a projection of future low-level radioactive waste to the year 2000 based on existing waste volume data and anticipated growth in the Northeast states. Aware of the difficulties involved with any long range projection - unforeseen events can drastically change projections based on current assumptions - the Technical Subcommittee believes that waste volume projections should be reviewed annually as updated information becomes available. The Technical Subcommittee made the following findings based upon a conservative projection methodology: volumes of low-level waste produced annually in the eleven states individually and collectively are expected to grow continually through the year 2000 with the rate of increase varying by state; by the year 2000, the Northeast is projected to generate 58,000 m3 of low-level waste annually, about 1.9 times the current average; and based on current estimates, 47% of the total projected waste volume in the year 2000 will be produced by nuclear power plants, compared to the current average of 54%. Non-reactor wastes will equal 53% of the total in the year 2000 compared to the current 46%

  12. Low-level radioactive-waste compacts. Status report as of July 1982

    International Nuclear Information System (INIS)

    The Low-Level Radioactive Waste Policy Act (P.L. 96-573), enacted in December 1980, established as federal policy that states take responsibility for providing disposal capacity for low-level radioactive waste (LLW) generated within their borders, except for defense waste and Federal R and D. At the request of Senator James A. McClure, Chairman of the Senate Committee on Energy and Natural Resources, DOE has documented the progress of states individually and collectively in fulfilling their responsibilities under the Public Law. Regionalization through formation of low-level waste compacts has been the primary vehicle by which many states are assuming this responsibility. To date seven low-level waste compacts have been drafted and six have been enacted by state legislatures or ratified by a governor. As indicated by national progress to date, DOE considers the task of compacting achievable by the January 1, 1986, exclusionary date set in law, although several states and NRC questioned this

  13. Low-level radioactive-waste compacts. Status report as of July 1982

    Energy Technology Data Exchange (ETDEWEB)

    1982-07-01

    The Low-Level Radioactive Waste Policy Act (P.L. 96-573), enacted in December 1980, established as federal policy that states take responsibility for providing disposal capacity for low-level radioactive waste (LLW) generated within their borders, except for defense waste and Federal R and D. At the request of Senator James A. McClure, Chairman of the Senate Committee on Energy and Natural Resources, DOE has documented the progress of states individually and collectively in fulfilling their responsibilities under the Public Law. Regionalization through formation of low-level waste compacts has been the primary vehicle by which many states are assuming this responsibility. To date seven low-level waste compacts have been drafted and six have been enacted by state legislatures or ratified by a governor. As indicated by national progress to date, DOE considers the task of compacting achievable by the January 1, 1986, exclusionary date set in law, although several states and NRC questioned this.

  14. Disposal of low-level radioactive waste at the Savannah River Site

    Energy Technology Data Exchange (ETDEWEB)

    Sauls, V.W. [Dept. of Energy, Aiken, SC (United States). Savannah River Field Office

    1993-03-01

    An important objective of the Savannah River Site`s low-level radioactive waste management program is to isolate the waste from the environment both now and well into the future. A key element in achieving this is the disposal of low-level radioactive waste in sealed concrete vaults. Historically the Site has disposed of low-level radioactive waste via shallow land burial. In 1987, it was decided that better isolation from the environment was required. At that time several options for achieving this isolation were studied and below grade concrete vaults were chosen as the best method. This paper discusses the performance objectives for the vaults, the current design of the vaults and plans for the design of future vaults, the cost to construct the vaults, and the performance assessment on the vaults. Construction of the first set of vaults is essentially complete and readiness reviews before the start of waste receipt are being performed. Startup is to begin late in calendar year 1992 and continue through early CY 1993. The performance assessment is under way and the first draft is to be completed in early 1993.

  15. Survey of microbiological effects in low-level radioactive waste disposed of to land

    International Nuclear Information System (INIS)

    An evaluation of published literature was mounted to determine the current position of research into microbiological effects in low-level radioactive waste disposal sites and to assess the need for further research. It is concluded from the survey that the microbial activity present in domestic landfills also occurs in shallow land burial low-level radioactive waste disposal sites. The microbial activity results in the release of tritium as tritiated methane to the atmosphere and tritiated components to the leachate. Carbon-14 migration is also enhanced. It also accelerates the corrosion of steel and concrete used to contain the wastes. There is little evidence for enhanced migration of radionuclides as a result of their incorporation in bacteria but there is considerable evidence for enhancement resulting from the presence of complexing agents (such as ethylenediamine-tetraacetic acid and tributyl phosphate) in the waste. Research in this field has been observed to be very active in the United States. Its objective is to predict with more certainty the important parameters for future low-level radioactive waste site designs. Quantitative prediction of microbial effects and their magnitude is not easy to deduce from the published literature, and new site designs will differ markedly from those that have been in operation over the last thirty years. (author)

  16. DRINK: a biogeochemical source term model for low level radioactive waste disposal sites.

    Science.gov (United States)

    Humphreys, P; McGarry, R; Hoffmann, A; Binks, P

    1997-07-01

    Interactions between element chemistry and the ambient geochemistry play a significant role in the control of radionuclide migration in the geosphere. These same interactions influence radionuclide release from near surface, low level radioactive waste, disposal sites once physical containment has degraded. In situations where LLW contains significant amounts of metal and organic materials such as cellulose, microbial degradation in conjunction with corrosion can significantly perturb the ambient geochemistry. These processes typically produce a transition from oxidising to reducing conditions and can influence radionuclide migration through changes in both the dominant radionuclide species and mineral phases. The DRINK (DRIgg Near field Kinetic) code is a biogeochemical transport code designed to simulate the long term evolution of the UK low level radioactive waste disposal site at Drigg. Drigg is the UK's principal solid low level radioactive waste disposal site and has been receiving waste since 1959. The interaction between microbial activity, the ambient geochemistry and radionuclide chemistry is central to the DRINK approach with the development of the ambient pH, redox potential and bulk geochemistry being directly influenced by microbial activity. This paper describes the microbial aspects of the code, site data underpinning the microbial model, the microbiology/chemistry interface and provides an example of the code in action. PMID:9340003

  17. Guidance document for prepermit bioassay testing of low-level radioactive waste

    Energy Technology Data Exchange (ETDEWEB)

    Anderson, S.L.; Harrison, F.L.

    1990-11-01

    In response to the mandate of Public Law 92-532, the Marine Protection, Research, and Sanctuaries Act (MPRSA) of 1972, as amended, the Environmental Protection Agency (EPA) has developed a program to promulgate regulations and criteria to control the ocean disposal of radioactive wastes. The EPA seeks to understand the mechanisms for biological response of marine organisms to the low levels of radioactivity that may arise from the release of these wastes as a result of ocean-disposal practices. Such information will play an important role in determining the adequacy of environmental assessments provided to the EPA in support of any disposal permit application. Although the EPA requires packaging of low-level radioactive waste to prevent release during radiodecay of the materials, some release of radioactive material into the deep-sea environment may occur when a package deteriorates. Therefore, methods for evaluating the impact on biota are being evaluated. Mortality and phenotypic responses are not anticipated at the expected low environmental levels that might occur if radioactive materials were released from the low-level waste packages. Therefore, traditional bioassay systems are unsuitable for assessing sublethal effects on biota in the marine environment. The EPA Office of Radiation Programs (ORP) has had an ongoing program to examine sublethal responses to radiation at the cellular level, using cytogenetic end points. This technical guidance report represents prepermit bioassay procedures that potentially may be applicable to the assessment of effects from a mixture of radionuclides that could be released from a point source at the ocean bottom. Methodologies along with rationale and a discussion of uncertainty are presented for the sediment benthic bioassay protocols identified in this report.

  18. Guidance document for prepermit bioassay testing of low-level radioactive waste

    International Nuclear Information System (INIS)

    In response to the mandate of Public Law 92-532, the Marine Protection, Research, and Sanctuaries Act (MPRSA) of 1972, as amended, the Environmental Protection Agency (EPA) has developed a program to promulgate regulations and criteria to control the ocean disposal of radioactive wastes. The EPA seeks to understand the mechanisms for biological response of marine organisms to the low levels of radioactivity that may arise from the release of these wastes as a result of ocean-disposal practices. Such information will play an important role in determining the adequacy of environmental assessments provided to the EPA in support of any disposal permit application. Although the EPA requires packaging of low-level radioactive waste to prevent release during radiodecay of the materials, some release of radioactive material into the deep-sea environment may occur when a package deteriorates. Therefore, methods for evaluating the impact on biota are being evaluated. Mortality and phenotypic responses are not anticipated at the expected low environmental levels that might occur if radioactive materials were released from the low-level waste packages. Therefore, traditional bioassay systems are unsuitable for assessing sublethal effects on biota in the marine environment. The EPA Office of Radiation Programs (ORP) has had an ongoing program to examine sublethal responses to radiation at the cellular level, using cytogenetic end points. This technical guidance report represents prepermit bioassay procedures that potentially may be applicable to the assessment of effects from a mixture of radionuclides that could be released from a point source at the ocean bottom. Methodologies along with rationale and a discussion of uncertainty are presented for the sediment benthic bioassay protocols identified in this report

  19. The low-level waste handbook: A user's guide to the Low-Level Radioactive Waste Policy Amendments Act of 1985

    International Nuclear Information System (INIS)

    This report provides a detailed, section-by-section analysis of the Low-Level Radioactive Waste Policy Amendments Act of 1985. Appendices include lists of relevant law and legislation, relevant Congressional committees, members of Congress mentioned in the report, and exact copies of the 1980 and 1985 Acts

  20. Design and operational considerations of United States commercial near-surface low-level radioactive waste disposal facilities

    International Nuclear Information System (INIS)

    In accordance with the Low-Level Radioactive Waste Policy Amendments Act of 1985, states are responsible for providing for disposal of commercially generated low-level radioactive waste (LLW) within their borders. LLW in the US is defined as all radioactive waste that is not classified as spent nuclear fuel, high-level radioactive waste, transuranic waste, or by-product material resulting from the extraction of uranium from ore. Commercial waste includes LLW generated by hospitals, universities, industry, pharmaceutical companies, and power utilities. LLW generated by the country''s defense operations is the responsibility of the Federal government and its agency, the Department of Energy. The commercial LLRW disposal sites discussed in this report are located near: Sheffield, Illinois (closed); Maxey Flats, Kentucky (closed); Beatty, Nevada (closed); West Valley, New York (closed); Barnwell, South Carolina (operating); Richland, Washington (operating); Ward Valley, California, (proposed); Sierra Blanca, Texas (proposed); Wake County, North Carolina (proposed); and Boyd County, Nebraska (proposed). While some comparisons between the sites described in this report are appropriate, this must be done with caution. In addition to differences in climate and geology between sites, LLW facilities in the past were not designed and operated to today''s standards. This report summarizes each site''s design and operational considerations for near-surface disposal of low-level radioactive waste. The report includes: a description of waste characteristics; design and operational features; post closure measures and plans; cost and duration of site characterization, construction, and operation; recent related R and D activities for LLW treatment and disposal; and the status of the LLW system in the US

  1. Hazards of past low-level radioactive waste ocean dumping have been overemphasized

    International Nuclear Information System (INIS)

    From 1946 to 1970, the United States disposed of low-level radioactive waste by dumping it into the ocean. Today, more than a decade after all dumping stopped, concerns over the potential environmental and public health consequences of past ocean dumping persist. In an evaluation of the adequacy of federal efforts to deal with this issue, GAO found that: the Federal Government has no complete and accurate catalogue of information on how much, what kind, and where low-level nuclear waste was dumped because detailed records were not required; the overwhelming body of scientific research and opinion shows that concerns over the potential public health and environmental consequences posed by past ocean dumping activity are unwarranted and overemphasized; and although the Environmental Protection Agency has been slow in developing low-level radioactive waste ocean dumping regulations, its current approach is sound. Nonetheless, improvements are needed in developing specific dumpsite monitoring requirements. Accordingly, GAO makes specific recommendations to improve the effectiveness of federal efforts in the area

  2. Fundamental research on thermal plasma technology for treatment of low level radioactive solid waste

    International Nuclear Information System (INIS)

    It is expected to establish the technology for treatment of low level radioactive solid waste generated in nuclear power plants. The main problems are volume reduction and stabilization of radionuclides acceptable for final disposal. Thermal plasma technology offers advantages for such waste treatment because of the easy supply of heat at high temperature independent on chemical and physical properties of the waste. New, non-contaminated waste, such as metallic, inorganic and combustible materials, have been melted in a crucible furnace. Transferred type of a DC plasma torch with a solid electrode was used as heat source and rated up to 50 kW. The main results obtained are as follows: (1) Metallic and inorganic materials can be melted and vitrified. Combustible materials can be pyrolyzed. Consequently high volume reduction rates can be attained. (2) Compressive strength of solidified products is more than twice as great as that of cement composites used for solidification of the liquid waste. Leaching rate of main components of the slag layer is in the same order of that of the high level radioactive waste glass. (3) In order to get guiding principle for design of off-gas treating system, compositions of the off-gas and properties of the dust entrained in the off-gas are clarified. From these results, technical prospects so that plasma heating technology can be applied for treatment of low level radioactive solid waste have been obtained. (author)

  3. New York State low-level radioactive waste status report for 1998

    International Nuclear Information System (INIS)

    This report summarizes data on low-level radioactive waste (LLRW) generated in New York State: it is based on reports from generators that must be filed annually with the New York State Energy Research and Development Authority (NYSERDA) and on data from the US Department of Energy (US DOE). The New York State Low-Level Radioactive Waste Management Act (State Act) requires LLRW generators in the State to submit annual reports detailing the classes and quantities of waste generated. This is the 13th year generators have been required to submit these reports to NYSERDA. The data are summarized in a series of tables and figures. There are four sections in the report. Section 1 covers volume, activity, and other characteristics of waste shipped for disposal in 1998. Activity is the measure of a material's radioactivity, or the number of radiation-emitting events occurring each second. Section 2 summarizes volume, activity, and other characteristics of waste held for storage as of December 31, 1998. Section 3 shows historical LLRW generation and includes generators' projections for the next five years. Section 4 provides a list, by county, of all facilities from which 1998 LLRW reports were received. 2 figs., 23 tabs

  4. Aboveground roofed design for the disposal of low-level radioactive waste in Maine

    Energy Technology Data Exchange (ETDEWEB)

    Alexander, J.A. [Univ. of Maine, Orono, ME (United States)

    1993-03-01

    The conceptual designs proposed in this report resulted from a study for the Maine Low-level Radioactive Waste Authority to develop conceptual designs for a safe and reliable disposal facility for Maine`s low-level radioactive waste (LLW). Freezing temperatures, heavy rainfall, high groundwater tables, and very complex and shallow glaciated soils found in Maine place severe constraints on the design. The fundamental idea behind the study was to consider Maine`s climatic and geological conditions at the beginning of conceptual design rather than starting with a design for another location and adapting it for Maine`s conditions. The conceptual designs recommended are entirely above ground and consist of an inner vault designed to provide shielding and protection against inadvertent intrusion and an outer building to protect the inner vault from water. The air dry conditions within the outer building should lead to almost indefinite service life for the concrete inner vault and the waste containers. This concept differs sharply from the usual aboveground vault in its reliance on at least two independent, but more or less conventional, roofing systems for primary and secondary protection against leakage of radioisotopes from the facility. Features include disposal of waste in air dry environment, waste loading and visual inspection by remote-controlled overhead cranes, and reliance on engineered soils for tertiary protection against release of radioactive materials.

  5. New York State Low-Level Radioactive Waste Status Report for 1992

    Energy Technology Data Exchange (ETDEWEB)

    Attridge, T.; Rapaport, S.; Yang, Qian

    1993-06-01

    This report summarizes data on low-level radioactive waste (LLRW) generation in New York State for calendar year 1992. It is based on reports from generators that must be filed annually with the New York State Energy Research and Development Authority (Energy Authority) and on data from the US Department of Energy. The New York State Low-Level Radioactive Waste Management Act (State Act) requires LLRW generators in the State to submit annual reports detailing the classes and quantities of waste generated. This is the seventh year generators have been required to submit reports on their waste to the Energy Authority. The data are summarized in a series of tables and figures. There are three sections in the report. Section 1 covers volume, radioactivity and other characteristics of waste generated in 1992. Section 2 shows historical LLRW generation over the years and includes generators` projections for the next five years. Section 3 provides a list of all facilities for which 1992 LLRW reports were received.

  6. New York State low-level radioactive waste status report for 1998

    Energy Technology Data Exchange (ETDEWEB)

    Voelk, H.

    1999-06-01

    This report summarizes data on low-level radioactive waste (LLRW) generated in New York State: it is based on reports from generators that must be filed annually with the New York State Energy Research and Development Authority (NYSERDA) and on data from the US Department of Energy (US DOE). The New York State Low-Level Radioactive Waste Management Act (State Act) requires LLRW generators in the State to submit annual reports detailing the classes and quantities of waste generated. This is the 13th year generators have been required to submit these reports to NYSERDA. The data are summarized in a series of tables and figures. There are four sections in the report. Section 1 covers volume, activity, and other characteristics of waste shipped for disposal in 1998. Activity is the measure of a material`s radioactivity, or the number of radiation-emitting events occurring each second. Section 2 summarizes volume, activity, and other characteristics of waste held for storage as of December 31, 1998. Section 3 shows historical LLRW generation and includes generators` projections for the next five years. Section 4 provides a list, by county, of all facilities from which 1998 LLRW reports were received. 2 figs., 23 tabs.

  7. Survey of agents and techniques applicable to the solidification of low-level radioactive wastes

    International Nuclear Information System (INIS)

    A review of the various solidification agents and techniques that are currently available or potentially applicable for the solidification of low-level radioactive wastes is presented. An overview of the types and quantities of low-level wastes produced is presented. Descriptions of waste form matrix materials, the wastes types for which they have been or may be applied and available information concerning relevant waste form properties and characteristics follow. Also included are descriptions of the processing techniques themselves with an emphasis on those operating parameters which impact upon waste form properties. The solidification agents considered in this survey include: hydraulic cements, thermoplastic materials, thermosetting polymers, glasses, synthetic minerals and composite materials. This survey is part of a program supported by the United States Department of Energy's Low-Level Waste Management Program (LLWMP). This work provides input into LLWMP efforts to develop and compile information relevant to the treatment and processing of low-level wastes and their disposal by shallow land burial

  8. Survey of agents and techniques applicable to the solidification of low-level radioactive wastes

    Energy Technology Data Exchange (ETDEWEB)

    Fuhrmann, M.; Neilson, R.M. Jr.; Colombo, P.

    1981-12-01

    A review of the various solidification agents and techniques that are currently available or potentially applicable for the solidification of low-level radioactive wastes is presented. An overview of the types and quantities of low-level wastes produced is presented. Descriptions of waste form matrix materials, the wastes types for which they have been or may be applied and available information concerning relevant waste form properties and characteristics follow. Also included are descriptions of the processing techniques themselves with an emphasis on those operating parameters which impact upon waste form properties. The solidification agents considered in this survey include: hydraulic cements, thermoplastic materials, thermosetting polymers, glasses, synthetic minerals and composite materials. This survey is part of a program supported by the United States Department of Energy's Low-Level Waste Management Program (LLWMP). This work provides input into LLWMP efforts to develop and compile information relevant to the treatment and processing of low-level wastes and their disposal by shallow land burial.

  9. Evaluating public involvement in the National Low-Level Radioactive Waste Management Program

    International Nuclear Information System (INIS)

    The Department of Energy contracted with the Keystone Center to evaluate the effectiveness of the National Low-Level Radioactive Waste Management Program's public-involvement efforts. The Center chose six evaluators with diverse training and experience related to low-level waste management and public-participation programs. Keystone's evaluation was based on (a) observations by the evaluators who attended the National Program-sponsored strategy review meetings and fairs; (b) interviews with low-level waste generators, local government officials, state legislators, public-interest groups, and members of the general public; and (c) observations of the final National Program strategy task force meeting. The evaluators concluded that, overall, the public-participation processes yielded some very positive results - for policy development and for DOE and the EG and G staff. They judged the strategy document to be complete, concise, and helpful to public dialogue on low-level waste issues. They also made specific recommendations for improvements to the public-participation program

  10. Overview of the management of solid low level radioactive waste at Sellafield and Drigg

    Energy Technology Data Exchange (ETDEWEB)

    Scott, Rob [British Nuclear Fuels, Cumbria (United Kingdom); Hagger, Richard C. [BNFL, Warrington (United Kingdom)

    2003-07-01

    Low level radioactive wastes have been disposed of in the United Kingdom in ner-surface facilities for over 40 years. This has mainly been at the Drigg disposal site on the Cumbrian coast, some six kilometres to the south of the Sellafield nuclear reprocessing site. The Drigg site also receives waste from a wide range of sources including nuclear power stations, nuclear fuel cycle facilities, isotope manufacturing sites, universities, general industry and cleanup of historically contaminated sites. Disposals until the late 1980s were solely by tipping essentially loose wastes into excavated trenches. More recently, trench disposals have been phased out in preference to emplacement of containerised, conditioned wastes in concrete vaults. This paper is principally from the perspective of a disposal facility operator. Firstly the regulatory framework to low level waste disposal is outlined. This is then followed by a review of practices and projects associated with the Sellafield and Drigg sits and also some of the supporting technical work.

  11. Overview of the management of solid low level radioactive waste at Sellafield and Drigg

    International Nuclear Information System (INIS)

    Low level radioactive wastes have been disposed of in the United Kingdom in ner-surface facilities for over 40 years. This has mainly been at the Drigg disposal site on the Cumbrian coast, some six kilometres to the south of the Sellafield nuclear reprocessing site. The Drigg site also receives waste from a wide range of sources including nuclear power stations, nuclear fuel cycle facilities, isotope manufacturing sites, universities, general industry and cleanup of historically contaminated sites. Disposals until the late 1980s were solely by tipping essentially loose wastes into excavated trenches. More recently, trench disposals have been phased out in preference to emplacement of containerised, conditioned wastes in concrete vaults. This paper is principally from the perspective of a disposal facility operator. Firstly the regulatory framework to low level waste disposal is outlined. This is then followed by a review of practices and projects associated with the Sellafield and Drigg sits and also some of the supporting technical work

  12. The storage center of very-low level radioactive wastes; Le centre de stockage des dechets de tres faible activite

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2008-07-01

    The low level radioactive wastes have a radioactivity level as same as the natural radioactivity. This wastes category and their storage has been taken into account by the french legislation. This document presents the storage principles of the site, containment, safety and the Center organization. (A.L.B.)

  13. Physical and chemical environment and radionuclide migration in a low level radioactive waste repository

    International Nuclear Information System (INIS)

    The expected physical and chemical environment within the low-level radioactive waste repository to be sited at Chalk River is being studied to establish the rate of radionuclide migration. Chemical conditions in the repository are being assessed for their effect on buffer performance and the degradation of the concrete structure. Experimental programs include the effect of changes in solution chemistry on radionuclide distribution between buffer/backfill materials and the aqueous phase; the chemical stability of the buffer materials and the determination of the controlling mechanism for radionuclide transport during infiltration

  14. Natural radioactivity of sand samples by low-level gamma spectrometry

    International Nuclear Information System (INIS)

    The natural radioactivities of compressed powdered sand samples from different locations along the Qena-Safaga highway were measured in face to face geometry applying a low-level γ-ray spectrometry method. The average measured values of U, Th and K are: 6.3, 6.2 and 1.5 x 104 ppm, respectively. Some samples were found to be free from thorium to the minimum detectable activity of the spectrometer. Results are discussed and compared with other results presented. (author)

  15. Developing operating procedures for a low-level radioactive waste disposal facility

    International Nuclear Information System (INIS)

    This document is intended to assist persons who are developing operating and emergency procedures for a low-level radioactive waste disposal facility. It provides 25 procedures that are considered to be relatively independent of the characteristics of a disposal facility site, the facility design, and operations at the facility. These generic procedures should form a good starting point for final procedures on their subjects for the disposal facility. In addition, this document provides 55 annotated outlines of other procedures that are common to disposal facilities. The annotated outlines are meant as checklists to assist the developer of new procedures

  16. Current Regulations and Guidance - New Approaches for Risk-Informed Low-Level Radioactive Waste Management

    International Nuclear Information System (INIS)

    This paper presents the historical foundations and future challenges for commercial low-level radioactive waste (LLRW) management in the United States. LLRW has been managed at government facilities since the beginning of the nuclear age and in the commercial sector since the early 1960's. Over the intervening years many technical, management and regulatory changes have occurred. Significant progress has been made in waste form, waste packaging and in recognizing radionuclides important to performance of disposal technologies and disposal facilities. This presentation will examine approaches using existing regulations and risk-informed approaches to improve guidance, licensing and management of LLRW. (authors)

  17. Developing operating procedures for a low-level radioactive waste disposal facility

    Energy Technology Data Exchange (ETDEWEB)

    Sutherland, A.A.; Miner, G.L.; Grahn, K.F.; Pollard, C.G. [Rogers and Associates Engineering Corp., Salt Lake City, UT (United States)

    1993-10-01

    This document is intended to assist persons who are developing operating and emergency procedures for a low-level radioactive waste disposal facility. It provides 25 procedures that are considered to be relatively independent of the characteristics of a disposal facility site, the facility design, and operations at the facility. These generic procedures should form a good starting point for final procedures on their subjects for the disposal facility. In addition, this document provides 55 annotated outlines of other procedures that are common to disposal facilities. The annotated outlines are meant as checklists to assist the developer of new procedures.

  18. State of the art review of alternatives to shallow land burial of low level radioactive waste

    International Nuclear Information System (INIS)

    A review of alternatives to shallow land burial for disposal of low level radioactive waste was conducted to assist ORNL in developing a program for the evaluation, selection, and demonstration of the most acceptable alternatives. The alternatives were categorized as follows: (1) near term isolation concepts, (2) far term isolation concepts, (3) dispersion concepts, and (4) conversion concepts. Detailed descriptions of near term isolation concepts are provided. The descriptions include: (1) method of isolation, (2) waste forms that can be accommodated, (3) advantages and disadvantages, (4) facility and equipment requirements, (5) unusual operational or maintenance requirements, (6) information/technology development requirements, and (7) related investigations of the concept

  19. In situ grouting of a low-level radioactive waste trench

    International Nuclear Information System (INIS)

    A shallow land burial trench containing low level radioactive waste was injected with a particulate grout to help control subsidence and radionuclide migration. The trench's accessible voids have been estimated at 20 vol %, and most of these voids appear to have been filled with grout. This injection was accomplished with a simple, labor intensive technique, and an inexperienced crew at an estimated cost of about $55,000. The grout costs $0.21/gal and 8081 gal was injected into the trench. 5 refs., 10 figs., 4 tabs

  20. New York State low-level radioactive waste status report for 1997

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-06-01

    This report summarizes data on low-level radioactive waste (LLRW) generated in New York State. It is based on reports from generators that must be filed annually with the New York State Energy Research and Development Authority (NYSERDA) and on data from the US Department of Energy (US DOE). The data are summarized in a series of tables and figures. There are four sections in this report. Section 1 covers volume, activity, and other characteristics of waste shipped for disposal in 1997. (Activity is the measure of a material`s radioactivity, or the number of radiation-emitting events occurring each second.) Section 2 summarizes volume, activity, and other characteristics of waste held for storage as of December 31, 1997. Section 3 shows historical LLRW generation and includes generators` projections for the next five years. Section 4 provides a list, by county, of all facilities from which 1997 LLRW reports were received.

  1. Radioactive Waste Management Complex low-level waste radiological performance assessment

    Energy Technology Data Exchange (ETDEWEB)

    Maheras, S.J.; Rood, A.S.; Magnuson, S.O.; Sussman, M.E.; Bhatt, R.N.

    1994-04-01

    This report documents the projected radiological dose impacts associated with the disposal of radioactive low-level waste at the Radioactive Waste Management Complex at the Idaho National Engineering Laboratory. This radiological performance assessment was conducted to evaluate compliance with applicable radiological criteria of the US Department of Energy and the US Environmental Protection Agency for protection of the public and the environment. The calculations involved modeling the transport of radionuclides from buried waste, to surface soil and subsurface media, and eventually to members of the public via air, groundwater, and food chain pathways. Projections of doses were made for both offsite receptors and individuals inadvertently intruding onto the site after closure. In addition, uncertainty and sensitivity analyses were performed. The results of the analyses indicate compliance with established radiological criteria and provide reasonable assurance that public health and safety will be protected.

  2. SLBM-A Fortran code for shallow land burial of low level radioactive waste

    International Nuclear Information System (INIS)

    The safety performance of shallow land burial sites for low level radioactive wastes are required for a number of scenarios related to the activity disposal mode; source release mode; type of burial facility and geohydrology of the site. This report deals with a program code in FORTRAN-77 for the safety performance assessment of different scenarios associated with shallow land burial of radioactive waste. The code is made operational in SINTRAN III, UNIX and MS-DOS environments. A display system is also attached to the code in these environments. The mathematical basis of the code; the description of input and output data files and a general discussion on the results obtained from a sample execution of the code are also included in the report. (author)

  3. A practical approach to volume minimisation of low level radioactive waste at UKAEA, Winfrith

    Energy Technology Data Exchange (ETDEWEB)

    Lewis, A.; Hawkins, G.; Milverton, P. [UKAEA, Solid Waste Services Section, Winfrith Technology Centre, Dorchester, Dorset (United Kingdom)

    2003-07-01

    To fulfil the United Kingdom Atomic Energy Authority (UKAEA) policy on best practicable environmental option (BPEO), the requirements of the radioactive substances act (RSA) 1993 and to meet the BNFL Drigg Conditions of Acceptance, the UKAEA Winfrith employ a range of techniques to minimise the volume of low level radioactive waste (LLW) consigned to BNFL drigg for final disposal. To achieve this the UKAEA Winfrith solid waste services section commissioned a plasma cutting facility, a lead decontamination facility and the Winfrith abrasive cleaning machine (WACM). These techniques coupled with regular supercompaction campaigns and a free release procedure ensure UKAEA Winfrith minimise the volume of LLW consigned to BNFL Drigg. This paper describes the waste minimisation techniques, the supercompaction campaigns and the free release monitoring programme employed at UKAEA Winfrith. (orig.)

  4. A practical approach to volume minimisation of low level radioactive waste at UKAEA, Winfrith

    International Nuclear Information System (INIS)

    To fulfil the United Kingdom Atomic Energy Authority (UKAEA) policy on best practicable environmental option (BPEO), the requirements of the radioactive substances act (RSA) 1993 and to meet the BNFL Drigg Conditions of Acceptance, the UKAEA Winfrith employ a range of techniques to minimise the volume of low level radioactive waste (LLW) consigned to BNFL drigg for final disposal. To achieve this the UKAEA Winfrith solid waste services section commissioned a plasma cutting facility, a lead decontamination facility and the Winfrith abrasive cleaning machine (WACM). These techniques coupled with regular supercompaction campaigns and a free release procedure ensure UKAEA Winfrith minimise the volume of LLW consigned to BNFL Drigg. This paper describes the waste minimisation techniques, the supercompaction campaigns and the free release monitoring programme employed at UKAEA Winfrith. (orig.)

  5. Specific calibration problems for gammaspectrometric measurements of low-level radioactivity in environmental samples

    Energy Technology Data Exchange (ETDEWEB)

    Arnold, D. [Physikalisch-Technische Bundesanstalt, Braunschweig (Germany); Wershofen, H. [Physikalisch-Technische Bundesanstalt, Braunschweig (Germany)

    1997-03-01

    Gammaspectrometric measurements of low-level radioactivity in environmental samples are always done in a close source detector geometry. This geometry causes coincidence-summing effects for measurements of multi-photon emitting nuclides. The measurements of radioactivity in environmental samples are also influenced by the absorption of photons in the materials which have to be analysed. Both effects must be taken into account by correction factors with respect to an energy-specific calibration of the detector system for a given geometry and a given composition of the calibration source. The importance of these corrections is emphasized. It is the aim of the present paper to compare different experimental and theoretical methods for the determination of these correction factors published by various authors and to report about efforts to refine them. (orig.)

  6. Hydraulic containment of low-level radioactive waste disposal sites: [Final technical report

    International Nuclear Information System (INIS)

    This document describes the use of impermeable barriers for the containment of liquid radioactive wastes at low-level radioactive waste disposal sites. Included are a review of existing barrier systems, assessments of laboratory and field data, and simulations of system performance under humid and arid conditions. Alternatives are identified as the most promising of the existing systems based on retention of irradiated water, field installation feasibility, and response to aggressive permeation. In decreasing order of preference, the favored systems are asphalt slurry, high density polyethylene synthetic liner, polyvinyl chloride synthetic liner, lean portland cement concrete, and compacted bentonite liner. It should be stressed that all five of these alternatives effectively retain irradiated water in the humid and arid simulations. Recommendations on the design and operation of the hydraulic containment system and suggestions on avenues for future research are included. 102 refs., 27 figs., 23 tabs

  7. New York State low-level radioactive waste status report for 1997

    International Nuclear Information System (INIS)

    This report summarizes data on low-level radioactive waste (LLRW) generated in New York State. It is based on reports from generators that must be filed annually with the New York State Energy Research and Development Authority (NYSERDA) and on data from the US Department of Energy (US DOE). The data are summarized in a series of tables and figures. There are four sections in this report. Section 1 covers volume, activity, and other characteristics of waste shipped for disposal in 1997. (Activity is the measure of a material's radioactivity, or the number of radiation-emitting events occurring each second.) Section 2 summarizes volume, activity, and other characteristics of waste held for storage as of December 31, 1997. Section 3 shows historical LLRW generation and includes generators' projections for the next five years. Section 4 provides a list, by county, of all facilities from which 1997 LLRW reports were received

  8. Radioactive waste management: a summary of state laws and administration. National Low-Level Radioactive Waste Mangement Program

    International Nuclear Information System (INIS)

    This is the first quarterly update of Radioactive Waste Management: A Summary of State Laws and Administration. Because states have been very active on waste management issues, the whole report is being reissued in this update. It covers the administration, the legislature and the laws in the 50 states related to radioactive waste. The report for each state is divided into four sections: Cover Page; Administrative; Legislative; and Applicable Legislation. The cover page indicates whether or not it is an Agreement State, the low-level waste compacts in which the state is listed as an eligible state, and the high-level waste repository site screening regions in which the state or a portion of it is located. The administrative section provides information on the governor, lead agencies, other involved administrative agencies, relevant commissions, boards and councils and various contacts. The Legislative section provides general information on the legislature and lists legislative leaders, the relevant committees and their chairs and a legislative contact. In the section covering Applicable Legislation, laws related to radiation protection, low-level waste and high-level waste have been summarized. Hazardous waste siting laws are included for states that do not have a siting law covering radioactive waste. The section also contains summaries of relevant bills introduced in 1982 and 1983 legislative sessions and their disposition. In general, the information in this report is accurate as of 15 April 1983

  9. Impact of technology applications to the management of low-level radioactive wastes

    International Nuclear Information System (INIS)

    Low-level radioactive wastes are generated from reactor sources (nuclear power reactors) as well as from nonreactor sources (academic, medical, governmental, and industrial). In recent years, about 50,000 m3 per year of such wastes have been generated in the United States and about 10,000 m3 per year in Canada. Direct disposal of these wastes in shallow ground has been a favored method in both countries in the past. In the United States, three operating commercial sites at Barnwell, South Carolina; Beatty, Nevada; and Richland, Washington, receive most of the commercial low-level waste generated. However, with recent advances in waste management, technologies are being applied to achieve optimum goals in terms of protection of human health and safety and the environment, as well as cost-effectiveness. These technologies must be applied from the generation sources through waste minimization and optimum segregation -- followed by waste processing, conditioning, storage, and disposal. A number of technologies that are available and can be applied as appropriate -- given the physical, chemical, and radiological characteristics of the waste -- include shredding, baling, compaction, supercompaction, decontamination, incineration, chemical treatment/conditioning, immobilization, and packaging. Interim and retrievable storage can be accomplished in a wide variety of storage structures, and several types of engineered disposal facility designs are now available. By applying an integrated approach to radioactive waste management, potential adverse impacts on human health and safety and the environment can be minimized. 15 refs., 1 fig., 1 tab

  10. Viability study for the implantation of an incineration unit for low level radioactive wastes

    International Nuclear Information System (INIS)

    Incineration have been a world-wide accepted volume reduction technique for combustible materials due to its high efficiency and excellent results. This technique is used since the last century as an alternative to reduce cities garbage and during the last four decades for the hazardous wastes. The nuclear industry is also involved in this technique development related to the low level radioactive waste management. There are different types of incineration installations and the definition of the right system is based on a criterious survey of its main characteristics, related to the rad wastes as well technical, economical and burocratic parameters. After the autonomous Brazilian nuclear programme development and the onlook of the future intensive nuclear energy uses, a radwaste generation increase is expected. One of the installations where these radwastes volumes are awaited to be high is the Experimental Center of ARAMAR (CEA). Nuclear reactors for propulsion and power generation have been developed in CEA beyond other nuclear combustible cycle activities. In this panorama it is important to evaluate the incineration role in CEA installations, as a volume reduction technique for an appropriate radioactive wastes management implementation. In this work main aspects related to the low level radwaste incineration systems were up rised. This information are important to a coherent viability study and also to give a clear and impartial about a topic that is still non discussed in the national scenery. (author)

  11. Assessment of microbial processes on gas production at radioactive low-level waste disposal sites

    International Nuclear Information System (INIS)

    Factors controlling gaseous emanations from low level radioactive waste disposal sites are assessed. Importance of gaseous fluxes of methane, carbon dioxide, and possible hydrogen from the site, stems from the inclusion of tritium and/or carbon-14 into the elemental composition of these compounds. In that the primary source of these gases is the biodegradation of organic components of the waste material, primary emphasis of the study involved an examination of the biochemical pathways producing methane, carbon dioxide, and hydrogen, and the environmental parameters controlling the activity of the microbial community involved. Initial examination of the data indicates that the ecosystem is anaerobic. As the result of the complexity of the pathway leading to methane production, factors such as substrate availability, which limit the initial reaction in the sequence, greatly affect the overall rate of methane evolution. Biochemical transformations of methane, hydrogen and carbon dioxide as they pass through the soil profile above the trench are discussed. Results of gas studies performed at three commercial low level radioactive waste disposal sites are reviewed. Methods used to obtain trench and soil gas samples are discussed. Estimates of rates of gas production and amounts released into the atmosphere (by the GASFLOW model) are evaluated. Tritium and carbon-14 gaseous compounds have been measured in these studies; tritiated methane is the major radionuclide species in all disposal trenches studied. The concentration of methane in a typical trench increases with the age of the trench, whereas the concentration of carbon dioxide is similar in all trenches

  12. Radioactive dating and methods of low-level counting. Proceedings of a symposium

    International Nuclear Information System (INIS)

    Since 1962, when the first Symposium on Radioactive Dating was organized in Athens by the International Atomic Energy Agency and the Joint Commission on Applied Radioactivity of the International Council of Scientific Unions (ICSU), the methods of radioactive dating have been continuously refined and applied to various problems in geochronology, archaeology and other disciplines. A number of new techniques have been developed which have resulted in an increase not only in range and accuracy of measurement but also in applications. To present a comprehensive picture of the latest work, the same two organizations sponsored a Symposium in Monaco on 2-10 March on Radioactive Dating and Methods of Low-Level Counting. At the meeting were 172 participants from 30 countries, and 57 papers were presented. To improve still further the accuracy of the radiocarbon dating method, some of the basic assumptions are being examined. Many physical and cosmochemical phenomena are involved in the movement of radiocarbon from the atmosphere into the biosphere and the oceans. The important conclusions drawn from the recent work correlating the latest results are presented in these proceedings; their implications throw much light on natural and cosmological events in the past. There has been increasing interest in the study of meteorites, their origin, age and history, and the study of dating by primeval isotopes has been greatly advanced by perfecting the technique for detecting very small activities of radioelements. The Symposium succeeded in attracting many of the recognized world authorities, and it is hoped that the present volume, which contains the papers and a record of the discussions, will be a significant contribution to the study of radioactive dating

  13. Gross Alpha Beta Radioactivity in Air Filters Measured by Ultra Low Level α/β Counter

    Science.gov (United States)

    Cfarku, Florinda; Bylyku, Elida; Deda, Antoneta; Dhoqina, Polikron; Bakiu, Erjona; Perpunja, Flamur

    2010-01-01

    Study of radioactivity in air as very important for life is done regularly using different methods in every country. As a result of nuclear reactors, atomic centrals, institutions and laboratories, which use the radioactivity substances in open or closed sources, there are a lot radioactive wastes. Mixing of these wastes after treatment with rivers and lakes waters makes very important control of radioactivity. At the other side nuclear and radiological accidents are another source of the contamination of air and water. Due to their radio toxicity, especially those of Sr90, Pu239, etc. a contamination hazard for human begins exist even at low concentration levels. Measurements of radioactivity in air have been performed in many parts of the world mostly for assessment of the doses and risk resulting from consuming air. In this study we present the results of international comparison organized by IAEA Vienna, Austria for the air filters spiked with unknown Alpha and Beta Activity. For the calibration of system we used the same filters spiked: a) with Pu-239 as alpha source; b) Sr-90 as beta source and also the blank filter. The measurements of air filter samples after calibration of the system are done with Ultra Low Level α/β Counter (MPC 9604) Protean Instrument Corporation. The high sensitivity of the system for the determination of the Gross Alpha and Beta activity makes sure detection of low values activity of air filters. Our laboratory results are: Aα = (0.19±0.01) Bq/filter and Aα (IAEA) = (0.17±0.009) Bq/filter; Aβ = (0.33±0.009) Bq/filter and Aβ (IAEA) = (0.29±0.01) Bq/filter. As it seems our results are in good agreement with reference values given by IAEA (International Atomic Energy Agency).

  14. Italian low-level radioactive waste management regulation, with special regard to mixed wastes

    International Nuclear Information System (INIS)

    Wastes are produced in all human activities, and their management becomes more difficult and urgent. In fact the increase of the life standards, based on widespread production and consumption of a large variety of products, especially in the developed countries has led the problem of managing and disposing wastes to sometimes dramatic levels. In addition to, the increasing number of different production processes and of the resources used implies specific treatment for each type of waste. Therefore specific treatment technologies and regulations have to be applied to the various waste categories. A particular emphasis is devoted to the radioactive wastes, owing to their particular characteristics, i. e. the electromagnetic energy of the contained radionuclides. Low level radioactive wastes are currently produced in many research and medical activities. From a technological point of view, such wastes pose much smaller management problems than those from nuclear power plants, owing to their relatively small amounts and low radioactivity levels. However their management and disposal rise some important problems, in terms of the correct radiation protection procedure, in relation to the specific health risks and to their being often 'mixed', i. e. contaminated with other chemical, biological, toxic, noxious and even infected substances. The authors review the European and Italian regulations about the management of radioactive, chemical and biological, toxic and noxious wastes, with special emphasis on the problem of mixed wastes. Moreover the authors present a summary of the results of the recent workshop, held in Italy, about this problem. In this work the high and medium level radioactive wastes are not been taken into account

  15. Remediation of the low-level radioactive waste burial site at Williams Air Force Base

    International Nuclear Information System (INIS)

    The Air Force initiated a contract to develop and prepare detailed work plans for the removal of five concrete cylinders and associated field activities at site RW-11 at Williams AFB. Cylinders were believed to contain low-level radioactive waste including radium-luminous painted dials and radium-bearing parts. Although the general location of the cylinders was known, the exact configuration and contents of the cylinders was unknown. Plans included site preparation, excavation, monitoring, packaging, disposal, closure, and health and safety. The Health and Safety Plan was developed based on the premise that Radium 226 was the primary isotope of concern. The primary health hazard for workers and the public associated with site excavation was inhalation of airborne radioactive dust. Contingency plans were prepared in the event any radiation activity was detected above background levels or other radioactive isotopes were detected at the site. Criteria used to determine whether the site posed a threat to human health or the environment was based on an action level of 10 millirem Total Effective Dose Equivalent. Williams AFB is a closed installation that was placed on the Superfund National Priorities List. This paper discusses the plans what were developed to remove the buried waste, the execution of the plans, and closure of the site RW-11

  16. Radioactive waste management complex low-level waste radiological composite analysis

    Energy Technology Data Exchange (ETDEWEB)

    McCarthy, J.M.; Becker, B.H.; Magnuson, S.O.; Keck, K.N.; Honeycutt, T.K.

    1998-05-01

    The composite analysis estimates the projected cumulative impacts to future members of the public from the disposal of low-level radioactive waste (LLW) at the Idaho National Engineering and Environmental Laboratory (INEEL) Radioactive Waste Management Complex (RWMC) and all other sources of radioactive contamination at the INEEL that could interact with the LLW disposal facility to affect the radiological dose. Based upon the composite analysis evaluation, waste buried in the Subsurface Disposal Area (SDA) at the RWMC is the only source at the INEEL that will significantly interact with the LLW facility. The source term used in the composite analysis consists of all historical SDA subsurface disposals of radionuclides as well as the authorized LLW subsurface disposal inventory and projected LLW subsurface disposal inventory. Exposure scenarios evaluated in the composite analysis include all the all-pathways and groundwater protection scenarios. The projected dose of 58 mrem/yr exceeds the composite analysis guidance dose constraint of 30 mrem/yr; therefore, an options analysis was conducted to determine the feasibility of reducing the projected annual dose. Three options for creating such a reduction were considered: (1) lowering infiltration of precipitation through the waste by providing a better cover, (2) maintaining control over the RWMC and portions of the INEEL indefinitely, and (3) extending the period of institutional control beyond the 100 years assumed in the composite analysis. Of the three options investigated, maintaining control over the RWMC and a small part of the present INEEL appears to be feasible and cost effective.

  17. West Valley low-level radioactive waste site revisited: Microbiological analysis of leachates

    International Nuclear Information System (INIS)

    The abundance and types of microorganisms in leachate samples from the West Valley low-level radioactive waste disposal site were enumerated. This study was undertaken in support of the study conducted by Ecology and Environment, Inc., to assess the extent of radioactive gas emissions from the site. Total aerobic and anaerobic bacteria were enumerated as colony forming units (CFU) by dilution agar plate technique, and denitrifiers, sulfate-reducers and methanogens by the most probable number technique (MPN). Of the three trenches 3, 9, and 11 sampled, trench 11 contained the most number of organisms in the leachate. Concentrations of carbon-14 and tritium were highest in trench 11 leachate. Populations of aerobes and anaerobes in trench 9 leachate were one order of magnitude less than in trench 11 leachate while the methanogens were three orders of magnitude greater than in trench 11 leachate. The methane content from trench 9 was high due to the presence of a large number of methanogens; the gas in this trench also contained the most radioactivity. Trench 3 leachate contained the least number of microorganisms. Comparison of microbial populations in leachates sampled from trenches 3 and 9 during October 1978 and 1989 showed differences in the total number of microbial types. Variations in populations of the different types of organisms in the leachate reflect the changing nutrient conditions in the trenches. 14 refs., 3 figs., 4 tabs

  18. Low-level radioactive waste disposal operations worldwide, with special reference to organic compounds in leachates and gases

    International Nuclear Information System (INIS)

    Low- and intermediate-level radioactive wastes are defined and ground disposal practices worldwide are discussed. The organic content of low-level wastes is tabulated and the organic composition of leachates and gaseous emissions from low-level wastes in the U.K. and U.S.A. are discussed. The radionuclide content of these leachates is tabulated. (U.K.)

  19. Hydrogeologic factors in the selection of shallow land burial sites for the disposal of low-level radioactive waste

    Science.gov (United States)

    Fischer, John N.

    1986-01-01

    In the United States, low-level radioactive waste is disposed of by shallow land burial. Commercial low-level radioactive waste has been buried at six sites, and low-level radioactive waste generated by the Federal Government has been buried at nine major and several minor sites. Several existing low-level radioactive waste sites have not provided expected protection of the environment. These shortcomings are related, at least in part, to an inadequate understanding of site hydrogeology at the time the sites were selected. To better understand the natural systems and the effect of hydrogeologic factors on long-term site performance, the U.S. Geological Survey has conducted investigations at five of the six commercial low-level radioactive waste sites and at three Federal sites. These studies, combined with those of other Federal and State agencies, have identified and confirmed important hydrogeologic factors in the effective disposal of low-level radioactive waste by shallow land burial. These factors include precipitation, surface drainage, topography, site stability, geology, thickness of the host soil-rock horizon, soil and sediment permeability, soil and water chemistry, and depth to the water table.

  20. Sampling and analyses of colloids at the Drigg low level radioactive waste disposal site.

    Science.gov (United States)

    Warwick, P; Allinson, S; Beckett, K; Eilbeck, A; Fairhurst, A; Russel-Flint, K; Verrall, K

    2002-04-01

    Water samples have been extracted from inside (from standpipes) and from outside (from boreholes) of the trenches at the low level radioactive waste disposal site at Drigg in Cumbria, UK. The samples were taken anaerobically from between 8.5 and 10.0 m below the surface using a submersible pump at low flow rates to ensure that the waters in the standpipes and boreholes were maintained at constant levels. To ensure representative samples, the Eh, pH. conductivity, temperature, iron and dissolved oxygen concentrations of the waters were taken during initial purging and during sampling. The gross tritium, gross non-tritium beta, gross alpha and gamma activities of each sample were determined using suitable sample preparation and counting techniques. Samples were then anaerobically, sequentially filtered through 12 microm, 1 microm, 30 kDa and 500 Da filter membranes. The filtrates were analysed for gross alpha, gross non-tritium beta and gamma activities. SEM and STEM analyses were used to determine the colloid population. An energy dispersive analyser on the SEM was used to determine the major elements present in the colloids. UV-visible spectrophotometry, fluorescence spectrophotometry and high performance size exclusion liquid chromatography were used to analyse the waters before and after treatment with ion exchange materials to determine whether natural organic matter was present in the waters. Results showed that two major types of colloids (iron containing colloids and silicon containing colloids) were present in the waters. There were also a small number of other colloids that contain, as major elements, aluminium, calcium and chromium. Organic colloids were also present. The majority of the radioactivity in the waters was due to tritium. Waters taken from outside the trenches contained low levels of non-tritium beta activities and alpha activities which were lower than the minimum detectable amount. Waters taken from the trenches contained non-tritium beta

  1. Biochemical process of low level radioactive liquid simulation waste containing detergent

    Energy Technology Data Exchange (ETDEWEB)

    Kundari, Noor Anis, E-mail: nooranis@batan.go.id; Putra, Sugili; Mukaromah, Umi [Sekolah Tinggi Teknologi Nuklir – Badan Tenaga Nuklir Nasional Jl. Babarsari P.O. BOX 6101 YKBB Yogyakarta 55281 Telp : (0274) 48085, 489716, Fax : (0274) 489715 (Indonesia)

    2015-12-29

    Research of biochemical process of low level radioactive liquid waste containing detergent has been done. Thse organic liquid wastes are generated in nuclear facilities such as from laundry. The wastes that are cotegorized as hazard and poison materials are also radioactive. It must be treated properly by detoxification of the hazard and decontamination of the radionuclides to ensure that the disposal of the waste meets the requirement of standard quality of water. This research was intended to determine decontamination factor and separation efficiensies, its kinetics law, and to produce a supernatant that ensured the environmental quality standard. The radioactive element in the waste was thorium with activity of 5.10{sup −5} Ci/m{sup 3}. The radioactive liquid waste which were generated in simulation plant contains detergents that was further processed by aerobic biochemical process using SGB 103 bacteria in a batch reactor equipped with aerators. Two different concentration of samples were processed and analyzed for 212 hours and 183 hours respectively at a room temperature. The product of this process is a liquid phase called as supernatant and solid phase material called sludge. The chemical oxygen demand (COD), biological oxygen demand (BOD), suspended solid (SS), and its alpha activity were analyzed. The results show that the decontamination factor and the separation efficiency of the lower concentration samples are higher compared to the samples with high concentration. Regarding the decontamination factor, the result for 212 hours processing of waste with detergent concentration of 1.496 g/L was 3.496 times, whereas at the detergent concentration of 0.748 g/L was 15.305 times for 183 hours processing. In case of the separation efficiency, the results for both samples were 71.396% and 93.465% respectively. The Bacterial growth kinetics equation follow Monod’s model and the decreasing of COD and BOD were first order with the rate constant of 0

  2. Treatment of low-level radioactive waste by plasma. A proven technology?

    International Nuclear Information System (INIS)

    Large amounts of actual and historical low level radioactive waste, with varying characteristics, are stored and generated from the operation and maintenance of nuclear power plants, the nuclear fuel cycle, research laboratories, pharmaceutical and medical facilities. Virtual all of these waste streams can be treated by the plasma technology resulting in a final product free of organics, liquids and moisture, and meeting without a doubt the acceptance criteria for safe storage and disposal. The plasma is a highly desirable heat source. Its high temperature of up to 10.000degC can treat the radioactive waste as is. The inorganic materials are melted into a glassy slag, containing most of the radioactive isotopes, while the organic material is vaporized into a syngas and subsequently oxidized in an afterburner. This technology is very suitable for historical waste containing mixtures of inorganic, organic, liquids, sludge, etc, with almost no waste preparation and with minimal risk for radioactive contamination and exposure. Plasma technology offers a high volume waste reduction factor (VRF) that minimizes the volume and overall costs of waste storage and disposal. In addition, as plasma technology can recondition previously conditioned waste packages that no longer meet the present acceptance criteria for final disposal, it offers a solution to the growing demand for improved quality of final waste forms. As such, plasma technology is of great value, not just to waste producers but to future generations as well. This paper describes further the principles of plasma, the different waste feed systems, off-gas treatment, operational experience and future plasma plants. (author)

  3. Biochemical process of low level radioactive liquid simulation waste containing detergent

    Science.gov (United States)

    Kundari, Noor Anis; Putra, Sugili; Mukaromah, Umi

    2015-12-01

    Research of biochemical process of low level radioactive liquid waste containing detergent has been done. Thse organic liquid wastes are generated in nuclear facilities such as from laundry. The wastes that are cotegorized as hazard and poison materials are also radioactive. It must be treated properly by detoxification of the hazard and decontamination of the radionuclides to ensure that the disposal of the waste meets the requirement of standard quality of water. This research was intended to determine decontamination factor and separation efficiensies, its kinetics law, and to produce a supernatant that ensured the environmental quality standard. The radioactive element in the waste was thorium with activity of 5.10-5 Ci/m3. The radioactive liquid waste which were generated in simulation plant contains detergents that was further processed by aerobic biochemical process using SGB 103 bacteria in a batch reactor equipped with aerators. Two different concentration of samples were processed and analyzed for 212 hours and 183 hours respectively at a room temperature. The product of this process is a liquid phase called as supernatant and solid phase material called sludge. The chemical oxygen demand (COD), biological oxygen demand (BOD), suspended solid (SS), and its alpha activity were analyzed. The results show that the decontamination factor and the separation efficiency of the lower concentration samples are higher compared to the samples with high concentration. Regarding the decontamination factor, the result for 212 hours processing of waste with detergent concentration of 1.496 g/L was 3.496 times, whereas at the detergent concentration of 0.748 g/L was 15.305 times for 183 hours processing. In case of the separation efficiency, the results for both samples were 71.396% and 93.465% respectively. The Bacterial growth kinetics equation follow Monod's model and the decreasing of COD and BOD were first order with the rate constant of 0.01 hour-1.

  4. Low-level radioactive waste source terms for the 1992 integrated data base

    Energy Technology Data Exchange (ETDEWEB)

    Loghry, S L; Kibbey, A H; Godbee, H W; Icenhour, A S; DePaoli, S M

    1995-01-01

    This technical manual presents updated generic source terms (i.e., unitized amounts and radionuclide compositions) which have been developed for use in the Integrated Data Base (IDB) Program of the U.S. Department of Energy (DOE). These source terms were used in the IDB annual report, Integrated Data Base for 1992: Spent Fuel and Radioactive Waste Inventories, Projections, and Characteristics, DOE/RW-0006, Rev. 8, October 1992. They are useful as a basis for projecting future amounts (volume and radioactivity) of low-level radioactive waste (LLW) shipped for disposal at commercial burial grounds or sent for storage at DOE solid-waste sites. Commercial fuel cycle LLW categories include boiling-water reactor, pressurized-water reactor, fuel fabrication, and uranium hexafluoride (UF{sub 6}) conversion. Commercial nonfuel cycle LLW includes institutional/industrial (I/I) waste. The LLW from DOE operations is category as uranium/thorium fission product, induced activity, tritium, alpha, and {open_quotes}other{close_quotes}. Fuel cycle commercial LLW source terms are normalized on the basis of net electrical output [MW(e)-year], except for UF{sub 6} conversion, which is normalized on the basis of heavy metal requirement [metric tons of initial heavy metal ]. The nonfuel cycle commercial LLW source term is normalized on the basis of volume (cubic meters) and radioactivity (curies) for each subclass within the I/I category. The DOE LLW is normalized in a manner similar to that for commercial I/I waste. The revised source terms are based on the best available historical data through 1992.

  5. Comparative approaches to siting low-level radioactive waste disposal facilities

    International Nuclear Information System (INIS)

    This report describes activities in nine States to select site locations for new disposal facilities for low-level radioactive waste. These nine States have completed processes leading to identification of specific site locations for onsite investigations. For each State, the status, legal and regulatory framework, site criteria, and site selection process are described. In most cases, States and compact regions decided to assign responsibility for site selection to agencies of government and to use top-down mapping methods for site selection. The report discusses quantitative and qualitative techniques used in applying top-down screenings, various approaches for delineating units of land for comparison, issues involved in excluding land from further consideration, and different positions taken by the siting organizations in considering public acceptance, land use, and land availability as factors in site selection

  6. Plasma arc melting treatment of low level radioactive waste with centrifugal hearth

    International Nuclear Information System (INIS)

    Plasma Arc Melting technology may possible be able to treat various kinds of waste streams through volume reduction and stabilization into a disposal waste form. The ability of other melting technologies to convert inorganic material in a single step, however, varies according to the characteristics of the materials. Plasma technology also can treat organic waste by selecting the oxidation atmosphere. The Japan Atomic Power Company (JAPC) has decided to construct a low level radioactive waste treatment facility using the Plasma Arc Centrifugal Treatment (PACT) process with an 8 ft rotating hearth and 1.2 MW transferred torch developed by Retech (Ukiah, CA. USA) in the Tsuruga power station. In Japan, the plasma technology has been developed for incineration ash treatment, but the JAPC plant will be the first treatment system using plasma technology for solid waste with various characteristics and shapes. (author)

  7. Model training curriculum for Low-Level Radioactive Waste Disposal Facility Operations

    Energy Technology Data Exchange (ETDEWEB)

    Tyner, C.J.; Birk, S.M.

    1995-09-01

    This document is to assist in the development of the training programs required to be in place for the operating license for a low-level radioactive waste disposal facility. It consists of an introductory document and four additional appendixes of individual training program curricula. This information will provide the starting point for the more detailed facility-specific training programs that will be developed as the facility hires and trains new personnel and begins operation. This document is comprehensive and is intended as a guide for the development of a company- or facility-specific program. The individual licensee does not need to use this model training curriculum as written. Instead, this document can be used as a menu for the development, modification, or verification of customized training programs.

  8. Model training curriculum for Low-Level Radioactive Waste Disposal Facility Operations

    International Nuclear Information System (INIS)

    This document is to assist in the development of the training programs required to be in place for the operating license for a low-level radioactive waste disposal facility. It consists of an introductory document and four additional appendixes of individual training program curricula. This information will provide the starting point for the more detailed facility-specific training programs that will be developed as the facility hires and trains new personnel and begins operation. This document is comprehensive and is intended as a guide for the development of a company- or facility-specific program. The individual licensee does not need to use this model training curriculum as written. Instead, this document can be used as a menu for the development, modification, or verification of customized training programs

  9. Low-level radioactive waste technology: a selected, annotated bibliography. [416 references

    Energy Technology Data Exchange (ETDEWEB)

    Fore, C.S.; Carrier, R.F.; Brewster, R.H.; Hyder, L.K.; Barnes, K.A.

    1981-10-01

    This annotated bibliography of 416 references represents the third in a series to be published by the Hazardous Materials Information Center containing scientific, technical, economic, and regulatory information relevant to low-level radioactive waste technology. The bibliography focuses on disposal site, environmental transport, and waste treatment studies as well as general reviews on the subject. The publication covers both domestic and foreign literature for the period 1951 to 1981. Major chapters selected are Chemical and Physical Aspects; Container Design and Performance; Disposal Site; Environmental Transport; General Studies and Reviews; Geology, Hydrology, and Site Resources; Regulatory and Economic Aspects; Social Aspects; Transportation Technology; Waste Production; and Waste Treatment. Entries in each of the chapters are further classified as a field study, laboratory study, theoretical study, or general overview involving one or more of these research areas.

  10. Shallow land burial of low-level radioactive wastes. A selected, annotated bibliography

    Energy Technology Data Exchange (ETDEWEB)

    Fore, C.S.; Vaughan, N.D.; Tappen, J. (comps.)

    1978-06-01

    The data file was built to provide information support to DOE researchers in the field of low-level radioactive waste disposal and management. The scope of the data base emphasizes studies which deal with the ''old'' Manhattan sites, commercial disposal sites, and the specific parameters which affect the soil and geologic migration of radionuclides. Specialized data fields have been incorporated into the data base to improve the ease and accuracy of locating pertinent references. Specific radionuclides for which data are presented are listed in the ''Measured Radionuclides'' field, and specific parameters which affect the migration of these radionuclides are presented in the ''Measured Parameters'' field. The 504 references are rated indicating applicability to shallow land burial technology and whether interpretation is required. Indexes are provided for author, geographic location, title, measured parameters, measured radionuclides, keywords, subject categories, and publication description. (DLC)

  11. An experimental survey of the factors that affect leaching from low-level radioactive waste forms

    Energy Technology Data Exchange (ETDEWEB)

    Dougherty, D.R.; Pietrzak, R.F.; Fuhrmann, M.; Colombo, P.

    1988-09-01

    This report represents the results of an experimental survey of the factors that affect leaching from several types of solidified low-level radioactive waste forms. The goal of these investigations was to determine those factors that accelerate leaching without changing its mechanism(s). Typically, although not in every case,the accelerating factors include: increased temperature, increased waste loading (i.e., increased waste to binder ratio), and decreased size (i.e., decreased waste form volume to surface area ratio). Additional factors that were studied were: increased leachant volume to waste form surface area ratio, pH, leachant composition (groundwaters, natural and synthetic chelating agents), leachant flow rate or replacement frequency and waste form porosity and surface condition. Other potential factors, including the radiation environment and pressure, were omitted based on a survey of the literature. 82 refs., 236 figs., 13 tabs.

  12. Investigation of the geology of the low-level radioactive waste burial site at Drigg, Cumbria

    International Nuclear Information System (INIS)

    The geology of the low-level solid radioactive waste disposal site at Drigg, Cumbria has been investigated on the basis of a number of shallow excavations and 35 boreholes. The glacial sequence varies from 10 to 42 m in thickness and ranges from coarse sands and gravels to compact boulder clays. These overlie an irregular surface of St Bees Sandstone which probably contains a deep-erosion channel. The site is underlain by at least one boulder clay horizon. Clays restrict the direct downward movement of surface infiltration into the deeper permeable sands and gravels considered to be in hydraulic continuity with the St Bees Sandstone, but give rise to perched water tables in which lateral flow may occur. The streams which traverse the site are potentially influent throughout their length and may lose water to sand and peat deposits where these exist in the south-western part of the site. (author)

  13. Design and operational experience of low level radioactive waste disposal in the United Kingdom

    International Nuclear Information System (INIS)

    Low level radioactive wastes have been disposed of at the Drigg near-surface disposal site for over 30 years. These are carried out under a disposal authorization granted by the UK Environment Agency. This is augmented by a three tier comprehensive system of waste controls developed by BNFL involving wasteform specification, consignor and waste stream qualification and waste consignment verification. Until 1988 wastes were disposed of into trench facilities. However, based on a series of integrated optioneering studies, new arrangements have since been brought into operation. Central to these is a wasteform specification based principally on high force compaction of wastes, grouting within 20 m3 steel overpack containers to essentially eliminate associated voidage and subsequent disposal in concrete lined vaults. These arrangements ensure efficient utilisation of the Drigg site capacity and a cost-effective disposal concept which meets both national and international standards. (author). 7 figs

  14. Comparative approaches to siting low-level radioactive waste disposal facilities

    Energy Technology Data Exchange (ETDEWEB)

    Newberry, W.F.

    1994-07-01

    This report describes activities in nine States to select site locations for new disposal facilities for low-level radioactive waste. These nine States have completed processes leading to identification of specific site locations for onsite investigations. For each State, the status, legal and regulatory framework, site criteria, and site selection process are described. In most cases, States and compact regions decided to assign responsibility for site selection to agencies of government and to use top-down mapping methods for site selection. The report discusses quantitative and qualitative techniques used in applying top-down screenings, various approaches for delineating units of land for comparison, issues involved in excluding land from further consideration, and different positions taken by the siting organizations in considering public acceptance, land use, and land availability as factors in site selection.

  15. Sulfur polymer cement, a new stabilization agent for mixed and low- level radioactive waste

    International Nuclear Information System (INIS)

    Solidification and stabilization agents for radioactive, hazardous, and mixed wastes are failing to pass governmental tests at alarming rates. The Department of Energy's National Low-Level Waste Management Program funded testing of Sulfur Polymer Cement (SPC) by Brookhaven National Laboratory during the 1980s. Those tests and tests by the US Bureau of Mines (the original developer of SPC), universities, states, and the concrete industry have shown SPC to be superior to hydraulic cements in most cases. Superior in what wastes can be successfully combined and in the quantity of waste that can be combined and still pass the tests established by the US Environmental Protection Agency and the US Nuclear Regulatory Commission

  16. Shallow land burial of low-level radioactive wastes. A selected, annotated bibliography

    International Nuclear Information System (INIS)

    The data file was built to provide information support to DOE researchers in the field of low-level radioactive waste disposal and management. The scope of the data base emphasizes studies which deal with the ''old'' Manhattan sites, commercial disposal sites, and the specific parameters which affect the soil and geologic migration of radionuclides. Specialized data fields have been incorporated into the data base to improve the ease and accuracy of locating pertinent references. Specific radionuclides for which data are presented are listed in the ''Measured Radionuclides'' field, and specific parameters which affect the migration of these radionuclides are presented in the ''Measured Parameters'' field. The 504 references are rated indicating applicability to shallow land burial technology and whether interpretation is required. Indexes are provided for author, geographic location, title, measured parameters, measured radionuclides, keywords, subject categories, and publication description

  17. Comparison of SUREPAK life cycle costs to other methods of low-level radioactive waste management

    International Nuclear Information System (INIS)

    Comparisons of costs of low-level radioactive waste management techniques invariably degenerate into parochial arguments over differences in commercial objectives. The purpose of this paper is to establish a common basis for comparing technologies and then to examine the result as a complete cycle instead of a snapshot view taken at an arbitrary point in the progression. One objective is to portray cost sensitivity in terms of the options available for waste management. A second, perhaps less obvious, point is the definition of cost factors hidden from the short-term view. The final objective is to show the cumulative effects of costs externally imposed without reference to the technology employed (e.g., legislated surcharges based on arbitrary parameters)

  18. BNFL Lysimeter programme to investigate the leaching of radionuclides from low-level radioactive waste

    Energy Technology Data Exchange (ETDEWEB)

    Clayton, K.; Clegg, R.; Holmes, R.G.G. [British Nuclear Fuels plc, Sellafield (United Kingdom); Newton, G.W.A. [Newton Systems, Manchester (United Kingdom)

    1993-12-31

    British Nuclear Fuels plc has initiated an experimental programme to measure the leaching behavior of radionuclides from various low level radioactive waste (LLW) materials using Lysimeters. The programme commenced in 1986 and to date 10 lysimeters have been commissioned. These have concentrated on simulating shallow trench conditions but a further programme is now planned to study concrete vault environments. The aim of the study is to provide information on leaching processes as part of the ongoing Drigg Near Field Programme, and also to yield input data for radiological assessment purposes. Towards this end, data have been gained from the lysimeters on basic chemistry, gas generation and radionuclide Release Coefficients. This paper concentrates on one of the lysimeters which has recently been decommissioned and for which interim analytical data are available. Some general comments are given on BNFL`s experience using lysimeters and their applicability as a rapid and effective technique for studying near field degradation processes.

  19. Separation and recovery of sodium nitrate from low-level radioactive liquid waste by electrodialysis

    International Nuclear Information System (INIS)

    An advanced method, in which electrodialysis separation of sodium nitrate and decomposition of nitrate ion are combined, has been developed to remove nitrate ion from low-level radioactive liquid wastes including nitrate salts of high concentration. In the electrodialysis separation, the sodium nitrate was recovered as nitric acid and sodium hydroxide. When they are reused, it is necessary to reduce the quantity of impurities getting mixed with them from the waste fluid as much as possible. In this study, therefore, a cation exchange membrane with permselectivity for sodium ion and an anion exchange membrane with permselectivity for monovalent anion were employed. Using these membranes sodium and nitrate ions were effectively removed form a sodium nitrate solution of high concentration. And also it was confirmed that sodium ion was successfully separated from cesium and strontium ions and that nitrate ion was separated from sulfate and phosphate ions. (author)

  20. Geochemical and biological research at the NEA dumpsite for low-level radioactive waste

    International Nuclear Information System (INIS)

    A geochemical and biological study of the sea floor at the NEA dumpsite for low-level radioactive waste is reported. The sea bottom has rather steep hillsides. Slumps are usual phenomena and could be triggered by the dumping operations. The sediment is described in terms of its mineralogical and elemental composition. The variation in CaCO3 content accounts for most of the variation in the elemental composition and cation exchange capacity. The present depth of the lysocline is shown to be about 4700 m. A description is given of the early diagenetic processes: (1) Mineralization of organic material, (2) Cation exchange, (3) Change in redox conditions and (4) Carbonate dissolution and recrystallization; and discussed in terms of their effects on the redistribution and transport of trace elements and radionuclides within the sediment and between sediment and overlying water. (orig.)

  1. Issues in the review of a license application for an above grade low-level radioactive waste disposal facility

    Energy Technology Data Exchange (ETDEWEB)

    Ringenberg, J.D. [Nebraska Dept. of Environmental Quality, NE (United States)

    1993-03-01

    In December 1987, Nebraska was selected by the Central Interstate Compact (CIC) Commission as the host state for the construction of a low-level radioactive waste disposal facility. After spending a year in the site screening process, the Compact`s developer, US Ecology, selected three sites for detailed site characterization. These sites were located in Nemaha, Nuckolls and Boyd Counties. One year later the Boyd County site was selected as the preferred site and additional site characterization studies were undertaken. On July 29, 1990, US Ecology submitted a license application to the Nebraska Department of Environmental Control (now Department of Environmental Quality-NDEQ). This paper will present issues that the NDEQ has dealt with since Nebraska`s selection as the host state for the CIC facility.

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

    International Nuclear Information System (INIS)

    The volume of low-level radioactive waste generated in the eleven Northeast states has undergone significant change since the inital 1982 analysis and projection. These revised projections incorporate improved data reporting and evidence of sharp declines in certain categories of waste. Volumes in the 1982-1983 period reflect waste shipped for disposal as reported by disposal site operators. Projected waste volumes represent waste intended for disposal. The recent dramatic changes in source reduction and waste management practices underscore the need for annual review of waste volume projections. The volume of waste shipped for off-site disposal has declined approximately 12% in two years, from an average 1,092,500 ft3 annually in 1979 to 1981 to an average annual 956,500 ft3 in 1982 to 1983; reactor waste disposal volumes declined by about 39,000 ft3 or 7% during this period. Non-reactor waste volumes shipped for disposal declined by over 70,000 ft3 or 15% during this period. The data suggest that generators increased their use of such management practices as source reduction, compaction, or, for carbon-14 and tritium, temporary storage followed by disposal as non-radioactive waste under the NRC de minimus standard effective March 1981. Using the Technical Subcommittee projection methodology, the volume of low-level waste produced annually in the eleven states, individually and collectively, is expected to increase through the year 2000, but at a significantly lower rate of increase than initially projected. By the year 2000, the Northeast is projected to generate 1,137,600 ft3 of waste annually, an increase of about 20% over 1982 to 1983 average volume

  3. Evaluating public involvement in the national low-level radioactive-waste-management program. Final report

    International Nuclear Information System (INIS)

    An extensive public involvement approach has been developed to obtain the views and assistance of state and local governments, citizen groups, industry, professional societies and other organizations in the preparation and review of a national strategy document on low-level radioactive wastes. Six evaluators who have a wide diversity of backgrounds were selected to evaluate the effectiveness of this approach. This final report presents findings discussed under the headings: Introduction to the Recent History of Low-level Waste Policy Development (LLWMP) and the Role of Public Participation; Public Participation Mechanisms Employed in Preparing the National Strategy Document; the Keystone's Evaluation Process; and Findings. The overall evaluation of the process was very positive. It was clear that the LLWMP staff was seriously committed to building a credible public participation process. The evaluation team was provided rough cost figures for the various components of the LLWMP effort and concluded that, in its opinion, the public participation process provided benefits to the federal government that exceeded its costs. Moreover, the costs of the individual components were not out of line with each one's usefulness and contribution to the overall effort

  4. Low-level radioactive waste facility siting in the Rocky Mountain compact region

    International Nuclear Information System (INIS)

    The puprose of the Rocky Mountain Low-Level Radioactive Waste Compact is to develop a regional management system for low-level waste (LLW) generated in the six states eligible for membership: Arizona, Colorado, Nevada, New Mexico, Utah and Wyoming. Under the terms of the compact, any party state generating at least 20% of the region's waste becomes responsible for hosting a regional LLW management facility. However, the compact prescribes no system which the host state must follow to develop a facility, but rather calls on the state to fulfill its responsibility through reliance on its own laws and regulations. Few of the Rocky Mountain compact states have legislation dealing specifically with LLW facility siting. Authority for LLW facility siting is usually obtained from radiation control statutes and solid or hazardous waste statutes. A state-by-state analysis of the siting authorities of each of the Rock Mountain compact states as they pertain to LLW disposal facility siting is presented. Siting authority for LLW disposal facilities in the Rocky Mountain compact region runs from no authority, as in Wyoming, to general statutory authority for which regulations would have to be promulgated, as in Arizona and Nevada, to more detailed siting laws, as in Colorado and New Mexico. Barring an amendment to, or different interpretation of, the Utah Hazardous Waste Facility Siting Act, none of the Rocky Mountain States' LLW facility siting authorities preempt local veto authorities

  5. US Army facility for the consolidation of low-level radioactive waste

    International Nuclear Information System (INIS)

    A preliminary study of a waste consolidation facility for the Department of the Army's low-level radioactive waste was carried out to determine a possible site and perform a cost-benefit analysis. Four sites were assessed as possible locations for such a facility, using predetermined site selection criteria. To assist in the selection of a site, an evaluation of environmental issues was included as part of each site review. In addition, a preliminary design for a waste consolidation facility was developed, and facilities at each site were reviewed for their availability and suitability for this purpose. Currently available processes for volume reduction, as well as processes still under development, were then investigated, and the support and handling equipment and the staff needed for the safe operation of a waste consolidation facility were studied. Using current costs for the transportation and burial of low-level waste, a cost comparison was then made between waste disposal with and without the utilization of volume reduction. Finally, regulations that could affect the operation of a waste consolidation facility were identified and their impact was assessed. 11 references, 5 figures, 16 tables

  6. Modeling in low-level radioactive waste management from the US Geological Survey perspective

    International Nuclear Information System (INIS)

    The United States Geological Survey (USGS) is a long-standing proponent of using models as tools in geohydrologic investigations. These models vary from maps and core samples to elaborate digital computer algorithms, depending on the needed application and resources available. Being a non-regulatory scientific agency, the USGS uses models primarily for: improving modeling technology, testing hypotheses, management of water resources, providing technical advice to other agencies, parameter sensitivity analysis, and determination of parameter values (inverse problems). At low-level radioactive waste disposal sites, we are most interested in developing better capabilities for understanding the groundwater flor regime within and away from burial trenches, geochemical factors affecting nuclide concentration and mobility in groundwater, and the effects that various changes in the geohydrologic conditions have on groundwater flow and nuclide migration. Although the Geological Survey has modeling capabilities in a variety of complex problems, significant deficiencies and limitations remain in certain areas, such as fracture flow conditions and solute transport in the unsaturated zone. However, even more serious are the deficiencies in measuring or estimating adequate input data for models and verification of model utility on real problems. Flow and transport models are being used by the USGS in several low-level disposal site studies, with varying degrees of sucess

  7. US Army facility for the consolidation of low-level radioactive waste

    Energy Technology Data Exchange (ETDEWEB)

    Stein, S.L.; Tanner, J.E.; Murphy, B.L.; Gillings, J.C.; Hadley, R.T.; Lyso, O.M.; Gilchrist, R.L.; Murphy, D.W.

    1983-12-01

    A preliminary study of a waste consolidation facility for the Department of the Army's low-level radioactive waste was carried out to determine a possible site and perform a cost-benefit analysis. Four sites were assessed as possible locations for such a facility, using predetermined site selection criteria. To assist in the selection of a site, an evaluation of environmental issues was included as part of each site review. In addition, a preliminary design for a waste consolidation facility was developed, and facilities at each site were reviewed for their availability and suitability for this purpose. Currently available processes for volume reduction, as well as processes still under development, were then investigated, and the support and handling equipment and the staff needed for the safe operation of a waste consolidation facility were studied. Using current costs for the transportation and burial of low-level waste, a cost comparison was then made between waste disposal with and without the utilization of volume reduction. Finally, regulations that could affect the operation of a waste consolidation facility were identified and their impact was assessed. 11 references, 5 figures, 16 tables.

  8. Prediction of waste leaching from solidified low-level radioactive waste

    Science.gov (United States)

    Tahboub, Alaeddin Borhan

    In 1983 a research program called Special Waste-Form Lysimeter Arid (SWLA) was initiated at Hanford Lysimeter testing facility near Richland, Washington to evaluate radionuclide release from solidified Low-Level Radioactive waste from underground burial facilities. The goal of this research is to help interpret experimental results from the Hanford site and formulate recommendations regarding source-term modeling for Low- Level waste forms. The specific objective is to test the diffusion source-term models based on ANS/ANSI 16.1 (ANS, 1986) laboratory leach test. The project uses the SWMS_2d model to predict the leaching of 137Cs, 90Sr, 60Co, and 3H radio nuclides from the waste form contained in Hanford lysimeters. Effective diffusion coefficients (De's) as measured by the above standard test were obtained from published literature for each nuclide. These De's together with the published soil properties and environmental conditions at the Hanford site are the model input. The source term modeling results are compared to the measured lysimeter data. Results showed that, the model is able to predict release of 3H. The model was not able to predict the release of 60Co from the waste form, which indicate that there are other processes rather than diffusion involved. The effective diffusion coefficient from ANS/ANSI 16.1 test can be used only for non reactive radionuclides like 3H (tritium).

  9. Experience in low level radioactive waste disposal in the United Kingdom

    International Nuclear Information System (INIS)

    Low level radioactive wastes have been disposed of in the United Kingdom in near-surface facilities for over 30 years. This has mainly been at the Drigg disposal site on the Cumbrian coast, some six kilometres to the south of the Sellafield nuclear reprocessing site. The Drigg site receives waste from a wide range of sources including nuclear power stations, nuclear fuel cycle facilities, isotope manufacturing sites, universities, general industry and clean-up of historically contaminated sites. Disposals until the late 1980s were solely by tipping essentially loose wastes into excavated trenches. More recently, trench disposals are being phased out in preference to emplacement of containerized conditioned wastes in concrete vaults. British Nuclear Fuels plc (BNFL) owns and operates the Drigg disposal site and this review of experience is from the perspective of a disposal facility operator. Firstly, however, the regulatory framework to low level waste disposal is outlined. This is then followed by a review of practices and projects associated with the Drigg site and also some of the supporting technical work. 2 figs., 1 tab

  10. National profile on commercially generated low-level radioactive mixed waste

    Energy Technology Data Exchange (ETDEWEB)

    Klein, J.A.; Mrochek, J.E.; Jolley, R.L.; Osborne-Lee, I.W.; Francis, A.A.; Wright, T. [Oak Ridge National Lab., TN (United States)

    1992-12-01

    This report details the findings and conclusions drawn from a survey undertaken as part of a joint US Nuclear Regulatory Commission and US Environmental Protection Agency-sponsored project entitled ``National Profile on Commercially Generated Low-Level Radioactive Mixed Waste.`` The overall objective of the work was to compile a national profile on the volumes, characteristics, and treatability of commercially generated low-level mixed waste for 1990 by five major facility categories-academic, industrial, medical, and NRC-/Agreement State-licensed goverment facilities and nuclear utilities. Included in this report are descriptions of the methodology used to collect and collate the data, the procedures used to estimate the mixed waste generation rate for commercial facilities in the United States in 1990, and the identification of available treatment technologies to meet applicable EPA treatment standards (40 CFR Part 268) and, if possible, to render the hazardous component of specific mixed waste streams nonhazardous. The report also contains information on existing and potential commercial waste treatment facilities that may provide treatment for specific waste streams identified in the national survey. The report does not include any aspect of the Department of Energy`s (DOES) management of mixed waste and generally does not address wastes from remedial action activities.

  11. National profile on commercially generated low-level radioactive mixed waste

    International Nuclear Information System (INIS)

    This report details the findings and conclusions drawn from a survey undertaken as part of a joint US Nuclear Regulatory Commission and US Environmental Protection Agency-sponsored project entitled ''National Profile on Commercially Generated Low-Level Radioactive Mixed Waste.'' The overall objective of the work was to compile a national profile on the volumes, characteristics, and treatability of commercially generated low-level mixed waste for 1990 by five major facility categories-academic, industrial, medical, and NRC-/Agreement State-licensed goverment facilities and nuclear utilities. Included in this report are descriptions of the methodology used to collect and collate the data, the procedures used to estimate the mixed waste generation rate for commercial facilities in the United States in 1990, and the identification of available treatment technologies to meet applicable EPA treatment standards (40 CFR Part 268) and, if possible, to render the hazardous component of specific mixed waste streams nonhazardous. The report also contains information on existing and potential commercial waste treatment facilities that may provide treatment for specific waste streams identified in the national survey. The report does not include any aspect of the Department of Energy's (DOES) management of mixed waste and generally does not address wastes from remedial action activities

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

    International Nuclear Information System (INIS)

    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. Low-level radioactive waste facility siting in the Rocky Mountain compact region

    Energy Technology Data Exchange (ETDEWEB)

    Whitman, M.

    1983-09-01

    The puprose of the Rocky Mountain Low-Level Radioactive Waste Compact is to develop a regional management system for low-level waste (LLW) generated in the six states eligible for membership: Arizona, Colorado, Nevada, New Mexico, Utah and Wyoming. Under the terms of the compact, any party state generating at least 20% of the region's waste becomes responsible for hosting a regional LLW management facility. However, the compact prescribes no system which the host state must follow to develop a facility, but rather calls on the state to fulfill its responsibility through reliance on its own laws and regulations. Few of the Rocky Mountain compact states have legislation dealing specifically with LLW facility siting. Authority for LLW facility siting is usually obtained from radiation control statutes and solid or hazardous waste statutes. A state-by-state analysis of the siting authorities of each of the Rock Mountain compact states as they pertain to LLW disposal facility siting is presented. Siting authority for LLW disposal facilities in the Rocky Mountain compact region runs from no authority, as in Wyoming, to general statutory authority for which regulations would have to be promulgated, as in Arizona and Nevada, to more detailed siting laws, as in Colorado and New Mexico. Barring an amendment to, or different interpretation of, the Utah Hazardous Waste Facility Siting Act, none of the Rocky Mountain States' LLW facility siting authorities preempt local veto authorities.

  14. The engineering application research of heat-pump evaporation technology dealing with low level radioactive liquid waste

    International Nuclear Information System (INIS)

    More and more radioactive wastes had been produced along with the development of nuclear industry, in which low level radioactive liquid waste is the most. There are many techniques to deal with low level radioactive liquid waste. 'The three-steps' method has been used widely in China for its advantages, which is high purify capability, simple technical principle and steady operation system. But the shortage which is high energy consumption is also obvious. The project of The Engineering Application Research of Heat-Pump Evaporation Technology Dealing with Low Level Radioactive Liquid Waste is about to set up an heat-pump evaporation system, which 1 m3 per hour liquid waste can be treated. in order to research and improve treatment technic of low level radioactive liquid evaporation. In the technology system of heat-pump evaporation, a steam-compressor used recycle the energy of second steam caused in evaporation process, in this way, it can enhance evaporation efficiency and reduce energy consumption under the condition of enough purify capability. The project will be tested by non-radioactivity and radioactivity experiments, and then the researching report will be written, the technic parameter and operation rule of the system in dealing with low radioactive liquid waste will be obtained, so that heat-pump can attain expanding demand in nuclear industry. (authors)

  15. Report to Congress in response to Public Law 99-240: 1990 Annual report on low-level radioactive waste management progress

    International Nuclear Information System (INIS)

    This report summarizes the progress during 1990 of states and compact regions in establishing new low-level radioactive waste disposal facilities. It also provides summary information on the volume of low-level radioactive waste received for disposal in 1990 by commercially operated low-level radioactive waste disposal facilities. This report is in response to section 7 (b) of the Low-Level Radioactive Waste Policy Act, as amended by Public Law 99-240

  16. Performance objectives for disposal of low-level radioactive wastes on the Oak Ridge Reservation

    International Nuclear Information System (INIS)

    This report presents a set of performance objectives for disposal of low-level radioactive wastes in a new facility on the Oak Ridge Reservation. The principal performance objectives include a limit on annual committed effective dose equivalent averaged over a lifetime of 0.25 mSv (25 mrem) for any member of the public beyond the boundary of the disposal facility, and a limit on annual committed effective dose equivalent averaged over a lifetime of 1 mSv (0.1 rem) and a limit on committed effective dose equivalent in any year of 5 mSv (0.5 rem) for any individual who inadvertently intrudes onto the disposal site after loss of active institutional controls. In addition, releases of radioactivity beyond the site boundary shall not result in annual dose equivalents to any number of the public from all sources of exposure that exceed limits established by Federal regulatory authorities and shall be kept as low as reasonably achievable. This report reviews generally applicable radiation protection standards for the public and environmental radiation standards for specific practices that have been developed by national and international authorities and discusses the use of limits on risk rather than dose as performance objectives and consideration of chemical toxicity rather than radiation dose in establishing limits on intakes of uranium. 63 refs., 7 figs., 2 tabs

  17. Treatment of low level radioactive wastewater by means of NF process

    International Nuclear Information System (INIS)

    Highlights: • Nanofiltration can offer one of the approaches in optimizing membrane system. • Operation parameters especially the pressure affect nuclides’ removal efficiency. • Organic polyamide membrane shows radiation resistance. • A summary of DF and flux values can be taken as reference in designing the membrane system for LLRWs treatment. - Abstract: Membrane technology has been proved as an effective technology in the treatment of low level radioactive wastewaters (LLRWs). As ‘loose reverse osmosis’, nanofiltration can be integrated with RO and offers the high permeate flux at low pressure without obvious loss of decontamination efficiency. In the paper, three kinds of commercially available NF membrane materials were investigated by lab-scale experiment with respect to the nuclide rejection. The results demonstrate the efficient elimination. The membrane flux can be improved by the elevation of temperature and cross-flow velocity within the ranges of 20–30 °C and 0.4–1.0 m s−1. The radiation resistance test demonstrates no obvious loss of flux and nuclide rejection after a long term operation in the radioactive circumstance. A brief comparison of LLRWs treatment methods shows that NF can perform the pre-treatment of RO and optimize the entire membrane system with high flux and low pressure. In the paper, decontamination factor and flux values of the tested membranes at different operation condition are summarized as the reference for membrane selection and system design

  18. Groundwater geochemistry near the storage sites of low-level radioactive waste: Implications for uranium migration

    Energy Technology Data Exchange (ETDEWEB)

    Gaskova, Olga L.; Boguslavsky, Anatoly E. [Institute of Geology and Mineralogy SB RAS, Ac. Koptyug prosp. 3, Novosibirsk 630090 (Russian Federation)

    2013-07-01

    This paper presents results of detailed sampling of groundwater and surface water near the storage sites of radioactive waste from the Electrochemical Plant ECP (Zelenogorsk, Krasnoyarsk region, Russia) and the Angarsk Electrolysis Chemical Complex AEC (Angarsk, Irkutsk region, Russia), both of which have produced enriched uranium since 1960's. The liquid (LRW) and solid (SRW) radioactive wastes belong to the category of low-level activity waste. The main result is that the uranium is below the recommended MPC for drinking waters in all types of groundwater around the sludge of ECP and AEC. But alkaline nitrate solutions have been penetrating and spreading into the aquifers under the LRW sludge pits. According to our calculations, redox conditions in the groundwater influenced by discharge are controlled by the couple NO{sub 3}{sup -}/NO{sub 2}{sup -} that facilitates U(VI) migration. The groundwater under SRW repositories is distinguished by its low mineralization and neutral pH. Co-contaminants, such as Mo, V, and Zr may serve as markers of techno-genous contamination in storage sites of the LRW sludge. (authors)

  19. Radiolytic generation of chloro-organic compounds in transuranic and low-level radioactive waste

    International Nuclear Information System (INIS)

    The radiolytic degradation of chloro-plastics is being investigated to evaluate the formation of chlorinated volatile organic compounds in radioactive waste. These chlorinated VOCs, when their subsequent migration in the geosphere is considered, are potential sources of ground-water contamination. This contamination is an important consideration for transuranic waste repositories being proposed for the Waste Isolation Pilot Plant project and the several additional low-level radioactive waste sites being considered throughout the United States. The production of chlorinated volatile organic compounds due to the interaction of ionizing radiation with chloro-plastic materials has been well-established in both this work and past studies. This occurs as a result of gamma, beta, and alpha particle interactions with the plastic material. The assemblage of organic compounds generated depends on the type of plastic material, the type of ionizing radiation, the gaseous environment present and the irradiation temperature. In the authors' experiments, gas generation data were obtained by mounting representative plastics near (3 mm) an alpha particle source (Am-241 foil). This assembly was placed in an irradiation vessel which contained air, nitrogen, or a hydrogen/carbon dioxide mixture, at near-atmospheric pressures, to simulate the range of atmospheres likely to be encountered in the subsurface. The gas phase in the vessels are periodically sampled for net gas production. The gas phase concentrations are monitored over time to determine trends and calculate the radiolytic yield for the various gaseous products

  20. Treatment of low level radioactive wastewater by means of NF process

    Energy Technology Data Exchange (ETDEWEB)

    Chen, Ding; Zhao, Xuan, E-mail: zhxinet@tsinghua.edu.cn; Li, Fuzhi

    2014-10-15

    Highlights: • Nanofiltration can offer one of the approaches in optimizing membrane system. • Operation parameters especially the pressure affect nuclides’ removal efficiency. • Organic polyamide membrane shows radiation resistance. • A summary of DF and flux values can be taken as reference in designing the membrane system for LLRWs treatment. - Abstract: Membrane technology has been proved as an effective technology in the treatment of low level radioactive wastewaters (LLRWs). As ‘loose reverse osmosis’, nanofiltration can be integrated with RO and offers the high permeate flux at low pressure without obvious loss of decontamination efficiency. In the paper, three kinds of commercially available NF membrane materials were investigated by lab-scale experiment with respect to the nuclide rejection. The results demonstrate the efficient elimination. The membrane flux can be improved by the elevation of temperature and cross-flow velocity within the ranges of 20–30 °C and 0.4–1.0 m s{sup −1}. The radiation resistance test demonstrates no obvious loss of flux and nuclide rejection after a long term operation in the radioactive circumstance. A brief comparison of LLRWs treatment methods shows that NF can perform the pre-treatment of RO and optimize the entire membrane system with high flux and low pressure. In the paper, decontamination factor and flux values of the tested membranes at different operation condition are summarized as the reference for membrane selection and system design.

  1. Performance assessment review guide for DOE low-level radioactive waste disposal facilities

    Energy Technology Data Exchange (ETDEWEB)

    Dodge, R.L.; Hansen, W.R.; Kennedy, W.E. Jr.; Layton, D.W.; Lee, D.W.; Maheras, S.T.; Neuder, S.M.; Wilhite, E.L.; Curl, R.U.; Grahn, K.F.; Heath, B.A.; Turner, K.H. [Dames and Moore, Denver, CO (United States)

    1991-10-01

    This report was prepared under the direction of the Performance Assessment Peer Review Panel. The intent is to help Department of Energy sites prepare performance assessments that meet the Panel`s expectations in terms of detail, quality, content, and consistency. Information on the Panel review process and philosophy are provided, as well as important technical issues that will be focused on during a review. This guidance is not intended to provide a detailed review plan as in NUREG-1200, Standard Review Plan for Review of a License Application for a Low-Level Radioactive Waste Disposal Facility (January 1988). The focus and intent of the Panel`s reviews differ significantly from a regulatory review. The review of a performance assessment by the Panel uses the collective professional judgment of the members to ascertain that the approach taken the methodology used, the assumptions made, etc., are technically sound and adequately justified. The results of the Panel`s review will be used by Department of Energy Headquarters in determining compliance with the requirements of DOE Order 5820.2A, ``Radioactive Waste Management.``

  2. Performance assessment review guide for DOE low-level radioactive waste disposal facilities

    International Nuclear Information System (INIS)

    This report was prepared under the direction of the Performance Assessment Peer Review Panel. The intent is to help Department of Energy sites prepare performance assessments that meet the Panel's expectations in terms of detail, quality, content, and consistency. Information on the Panel review process and philosophy are provided, as well as important technical issues that will be focused on during a review. This guidance is not intended to provide a detailed review plan as in NUREG-1200, Standard Review Plan for Review of a License Application for a Low-Level Radioactive Waste Disposal Facility (January 1988). The focus and intent of the Panel's reviews differ significantly from a regulatory review. The review of a performance assessment by the Panel uses the collective professional judgment of the members to ascertain that the approach taken the methodology used, the assumptions made, etc., are technically sound and adequately justified. The results of the Panel's review will be used by Department of Energy Headquarters in determining compliance with the requirements of DOE Order 5820.2A, ''Radioactive Waste Management.''

  3. Performance assessment review guide for DOE low-level radioactive waste disposal facilities

    Energy Technology Data Exchange (ETDEWEB)

    Dodge, R.L.; Hansen, W.R.; Kennedy, W.E. Jr.; Layton, D.W.; Lee, D.W.; Maheras, S.T.; Neuder, S.M.; Wilhite, E.L.; Curl, R.U.; Grahn, K.F.; Heath, B.A.; Turner, K.H. (Dames and Moore, Denver, CO (United States))

    1991-10-01

    This report was prepared under the direction of the Performance Assessment Peer Review Panel. The intent is to help Department of Energy sites prepare performance assessments that meet the Panel's expectations in terms of detail, quality, content, and consistency. Information on the Panel review process and philosophy are provided, as well as important technical issues that will be focused on during a review. This guidance is not intended to provide a detailed review plan as in NUREG-1200, Standard Review Plan for Review of a License Application for a Low-Level Radioactive Waste Disposal Facility (January 1988). The focus and intent of the Panel's reviews differ significantly from a regulatory review. The review of a performance assessment by the Panel uses the collective professional judgment of the members to ascertain that the approach taken the methodology used, the assumptions made, etc., are technically sound and adequately justified. The results of the Panel's review will be used by Department of Energy Headquarters in determining compliance with the requirements of DOE Order 5820.2A, Radioactive Waste Management.''

  4. Preliminary criteria for shallow-land storage/disposal of low-level radioactive solid waste in an arid environment

    International Nuclear Information System (INIS)

    Preliminary criteria for shallow land storage/disposal of low level radioactive solid waste in an arid environment were developed. Criteria which address the establishment and operation of a storage/disposal facility for low-level radioactive solid wastes are discussed. These were developed from the following sources: (1) a literature review of solid waste burial; (2) a review of the regulations, standards, and codes pertinent to the burial of radioactive wastes; (3) on site experience; and (4) evaluation of existing burial grounds and practices

  5. Evaluation of Activity Concentration Values and Doses due to the Transport of Low Level Radioactive Material

    Energy Technology Data Exchange (ETDEWEB)

    Rawl, Richard R [ORNL; Scofield, Patricia A [ORNL; Leggett, Richard Wayne [ORNL; Eckerman, Keith F [ORNL

    2010-04-01

    The International Atomic Energy Agency (IAEA) initiated an international Coordinated Research Project (CRP) to evaluate the safety of transport of naturally occurring radioactive material (NORM). This report presents the United States contribution to that IAEA research program. The focus of this report is on the analysis of the potential doses resulting from the transport of low level radioactive material. Specific areas of research included: (1) an examination of the technical approach used in the derivation of exempt activity concentration values and a comparison of the doses associated with the transport of materials included or not included in the provisions of Paragraph 107(e) of the IAEA Safety Standards, Regulations for the Safe Transport of Radioactive Material, Safety Requirements No. TS-R-1; (2) determination of the doses resulting from different treatment of progeny for exempt values versus the A{sub 1}/A{sub 2} values; and (3) evaluation of the dose justifications for the provisions applicable to exempt materials and low specific activity materials (LSA-I). It was found that the 'previous or intended use' (PIU) provision in Paragraph 107(e) is not risk informed since doses to the most highly exposed persons (e.g., truck drivers) are comparable regardless of intended use of the transported material. The PIU clause can also have important economic implications for co-mined ores and products that are not intended for the fuel cycle but that have uranium extracted as part of their industrial processing. In examination of the footnotes in Table 2 of TS-R-1, which identifies the progeny included in the exempt or A1/A2 values, there is no explanation of how the progeny were selected. It is recommended that the progeny for both the exemption and A{sub 1}/A{sub 2} values should be similar regardless of application, and that the same physical information should be used in deriving the limits. Based on the evaluation of doses due to the transport of low-level

  6. State-of-the-art report on low-level radioactive waste treatment

    International Nuclear Information System (INIS)

    An attempt is made to identify the main sources of low-level radioactive wastes that are generated in the United States. To place the waste problem in perspective, rough estimates are given of the annual amounts of each generic type of waste that is generated. Most of the wet solid wastes arise from the cleanup of gaseous and liquid radioactive streams prior to discharge or recycle. The treatment of the process streams and the secondary wet solid wastes thus generated is described for each type of government or fuel cycle installation. Similarly, the institutional wet wastes are also described. The dry wastes from all sources have smilar physical and chemical characteristics in that they can be classified as compactible, noncompactible, combustible, noncombustible, or combinations thereof. The various treatment options for concentrated or solid wet wastes and for dry wastes are discussed. Among the dry-waste treatment methods are compaction, baling, and incineration, as well as chopping, cutting, and shredding. Organic materials can usually be incinerated or, in some cases, biodegraded. The filter sludges, spent resins, incinerator ashes, and concentrated liquids are usually solidified in cement, urea-formaldehyde, or unsaturated polyester resins prior to burial. Asphalt has not yet been used as a solidificaton agent in the United States, but it probably will be used in the near future. The treatment of radioactive medical and bioresearch wastes is described, but the waste from radiochenmical, pharmaceutical, and other industries is not well defined at the present time. Recovery of waste metals and treatment of hazardous contaminated wastes are discussed briefly. Some areas appearing to need more research, development, and demonstration are specifically pointed out

  7. State-of-the-art report on low-level radioactive waste treatment

    Energy Technology Data Exchange (ETDEWEB)

    Kibbey, A.H.; Godbee, H.W.

    1980-09-01

    An attempt is made to identify the main sources of low-level radioactive wastes that are generated in the United States. To place the waste problem in perspective, rough estimates are given of the annual amounts of each generic type of waste that is generated. Most of the wet solid wastes arise from the cleanup of gaseous and liquid radioactive streams prior to discharge or recycle. The treatment of the process streams and the secondary wet solid wastes thus generated is described for each type of government or fuel cycle installation. Similarly, the institutional wet wastes are also described. The dry wastes from all sources have smilar physical and chemical characteristics in that they can be classified as compactible, noncompactible, combustible, noncombustible, or combinations thereof. The various treatment options for concentrated or solid wet wastes and for dry wastes are discussed. Among the dry-waste treatment methods are compaction, baling, and incineration, as well as chopping, cutting, and shredding. Organic materials can usually be incinerated or, in some cases, biodegraded. The filter sludges, spent resins, incinerator ashes, and concentrated liquids are usually solidified in cement, urea-formaldehyde, or unsaturated polyester resins prior to burial. Asphalt has not yet been used as a solidificaton agent in the United States, but it probably will be used in the near future. The treatment of radioactive medical and bioresearch wastes is described, but the waste from radiochenmical, pharmaceutical, and other industries is not well defined at the present time. Recovery of waste metals and treatment of hazardous contaminated wastes are discussed briefly. Some areas appearing to need more research, development, and demonstration are specifically pointed out.

  8. Central interstate low-level radioactive waste compact region site exclusionary screening study. Phase I. Final report

    International Nuclear Information System (INIS)

    The Low-Level Radioactive Waste Policy Act of 1980 assigns to the states the responsibility for disposal of the low-level radioactive waste generated within their boundaries. It also provides for regional compacts among states to address their needs on a broader basis and permits restriction of the use of regional disposal facilities after January 1, 1986, to generators of low-level waste within the region. Each state, either individually or as a member of a compact, must therefore consider the establishment of a low-level radioactive waste disposal facility within its borders. The states of Arkansas, Kansas, Louisiana, Nebraska, and Oklahoma adopted the Central Interstate Low-Level Waste Compact (CILLWC) and legislation was submitted to Congress for consent in June of 1983 legislation is being reintroduced in the 99th Congress. In August of 1984, the CILLWC selected and contracted Dames and Moore to conduct a Phase I-Site Suitability Screening Study for a low-level radioactive waste disposal facility in the five-state region. This report presents the results of the Phase I Screening Study. Dames and Moore reported to the Technical Advisory Committee (TAC) of the CILLWC which provided guidance and comment on work progress and direction

  9. Surface erosion and hydrology of earth covers used in shallow land burial of low-level radioactive waste

    International Nuclear Information System (INIS)

    Shallow land burial is the current method of disposal of low-level radioactive waste in the United States. The most serious technical problems encountered in shallow land burial are water-related. Water is reported to come into contact with the waste by erosion of earth covers or through infiltration of precipitation through the earth covers. The objectives of this study were to: compare and evaluate the effects of crested wheatgrass and streambank wheatgrass on surface erosion of simulated earth covers at Idaho National Engineering Laboratory (INEL), characterize the surface hydrology, and estimate cumulative soil loss for average and extreme rainfall events and determine if the waste will become exposed during its burial life due to erosion. 30 refs., 26 figs., 21 tabs

  10. The development of special ISO freight containers for the transport of low level radioactive waste

    International Nuclear Information System (INIS)

    During the operation and maintenance of nuclear power stations, and other nuclear facilities, solid waste materials such as paper, plastics, filters, clothing, wood and metallic items are produced which are lightly or potentially radioactively contaminated. These items of trash are generally classified as low level waste (LLW) which, in the UK, is defined as having a radioactivity content of not more than 12 GBq/ton beta/gamma (about 300 mCi/t) and 4 GBq/ton alpha (about 100 mCi/t). LLW does not normally require to be shielded during normal handling and transport. LLW in the UK is routinely disposed at a special site at Drigg in Cumbria and until recently the disposal method used has been simple tumble-tipping into shallow trenches excavated in clay. Large re-usable tipping containers were used to transport the waste by road to the disposal site. Although various studies had confirmed the continued technical, safety and environmental acceptability of the simple disposal practices at Drigg, it was recognized that improvements would have to be made, mainly for presentational purposes. The new disposal concept adopted at Drigg was to construct concrete lined engineered vaults in which the containerized waste would be stacked uniformly. It was therefore necessary to develop a new method of waste packaging that was compatible with the new disposal concept. A number of proposals were considered. The authors proposed a system that would use ISO freight containers as both transport and disposal packages. This system was adopted and has been in service since mid 1988

  11. Protecting Lake Ontario - Treating Wastewater from the Remediated Low-Level Radioactive Waste Management Facility - 13227

    Energy Technology Data Exchange (ETDEWEB)

    Freihammer, Till; Chaput, Barb [AECOM, 99 Commerce Drive, Winnipeg, Manitoba, R3P 0Y7 (Canada); Vandergaast, Gary [Atomic Energy of Canada Limited, Port Hope, Ontario (Canada); Arey, Jimi [Public Works and Government Services Canada, Ontario (Canada)

    2013-07-01

    The Port Granby Project is part of the larger Port Hope Area Initiative, a community-based program for the development and implementation of a safe, local, long-term management solution for historic low level radioactive waste (LLRW) and marginally contaminated soils (MCS). The Port Granby Project involves the relocation and remediation of up to 0.45 million cubic metres of such waste from the current Port Granby Waste Management Facility located in the Municipality of Clarington, Ontario, adjacent to the shoreline of Lake Ontario. The waste material will be transferred to a new suitably engineered Long-Term Waste Management Facility (LTWMF) to be located inland approximately 700 m from the existing site. The development of the LTWMF will include construction and commissioning of a new Wastewater Treatment Plant (WWTP) designed to treat wastewater consisting of contaminated surface run off and leachate generated during the site remediation process at the Port Granby Waste Management Facility as well as long-term leachate generated at the new LTWMF. Numerous factors will influence the variable wastewater flow rates and influent loads to the new WWTP during remediation. The treatment processes will be comprised of equalization to minimize impacts from hydraulic peaks, fine screening, membrane bioreactor technology, and reverse osmosis. The residuals treatment will comprise of lime precipitation, thickening, dewatering, evaporation and drying. The distribution of the concentration of uranium and radium - 226 over the various process streams in the WWTP was estimated. This information was used to assess potential worker exposure to radioactivity in the various process areas. A mass balance approach was used to assess the distribution of uranium and radium - 226, by applying individual contaminant removal rates for each process element of the WTP, based on pilot scale results and experience-based assumptions. The mass balance calculations were repeated for various flow

  12. Radiological, physical, and chemical characterization of low-level alpha contaminated wastes stored at the Idaho National Engineering Laboratory

    International Nuclear Information System (INIS)

    This document provides radiological, physical, and chemical characterization data for low-level alpha-contaminated radioactive and low-level alpha-contaminated radioactive and hazardous (i.e., mixed) wastes stored at the Idaho National Engineering Laboratory and considered for treatment under the Private Sector Participation Initiative Program. Waste characterization data are provided in the form of INEL Waste Profile Sheets. These documents provide, for each content code, information on waste identification, waste description, waste storage configuration, physical/chemical waste composition, radionuclide and associated alpha activity waste characterization data, and hazardous constituents present in the waste. Information is provided for 97 waste streams which represent an estimated total volume of 25,450 m 3 corresponding to a total mass of approximately 12,000,000 kg. In addition, considerable information concerning alpha, beta, gamma, and neutron source term data specific to Rocky Flats-generated waste forms stored at the INEL are provided to assist in facility design specification

  13. Radiological, physical, and chemical characterization of low-level alpha contaminated wastes stored at the Idaho National Engineering Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    Apel, M.L.; Becker, G.K.; Ragan, Z.K.; Frasure, J.; Raivo, B.D.; Gale, L.G.; Pace, D.P.

    1994-03-01

    This document provides radiological, physical, and chemical characterization data for low-level alpha-contaminated radioactive and low-level alpha-contaminated radioactive and hazardous (i.e., mixed) wastes stored at the Idaho National Engineering Laboratory and considered for treatment under the Private Sector Participation Initiative Program. Waste characterization data are provided in the form of INEL Waste Profile Sheets. These documents provide, for each content code, information on waste identification, waste description, waste storage configuration, physical/chemical waste composition, radionuclide and associated alpha activity waste characterization data, and hazardous constituents present in the waste. Information is provided for 97 waste streams which represent an estimated total volume of 25,450 m 3 corresponding to a total mass of approximately 12,000,000 kg. In addition, considerable information concerning alpha, beta, gamma, and neutron source term data specific to Rocky Flats-generated waste forms stored at the INEL are provided to assist in facility design specification.

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

    Energy Technology Data Exchange (ETDEWEB)

    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.

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

    Energy Technology Data Exchange (ETDEWEB)

    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.

  16. Taiwan industrial cooperation program technology transfer for low-level radioactive waste final disposal - phase I.

    Energy Technology Data Exchange (ETDEWEB)

    Knowlton, Robert G.; Cochran, John Russell; Arnold, Bill Walter; Jow, Hong-Nian; Mattie, Patrick D.; Schelling, Frank Joseph Jr. (; .)

    2007-01-01

    Sandia National Laboratories and the Institute of Nuclear Energy Research, Taiwan have collaborated in a technology transfer program related to low-level radioactive waste (LLW) disposal in Taiwan. Phase I of this program included regulatory analysis of LLW final disposal, development of LLW disposal performance assessment capabilities, and preliminary performance assessments of two potential disposal sites. Performance objectives were based on regulations in Taiwan and comparisons to those in the United States. Probabilistic performance assessment models were constructed based on limited site data using software including GoldSim, BLT-MS, FEHM, and HELP. These software codes provided the probabilistic framework, container degradation, waste-form leaching, groundwater flow, radionuclide transport, and cover infiltration simulation capabilities in the performance assessment. Preliminary performance assessment analyses were conducted for a near-surface disposal system and a mined cavern disposal system at two representative sites in Taiwan. Results of example calculations indicate peak simulated concentrations to a receptor within a few hundred years of LLW disposal, primarily from highly soluble, non-sorbing radionuclides.

  17. Microbial degradation of low-level radioactive waste. Volume 1, Annual report for FY 1993

    Energy Technology Data Exchange (ETDEWEB)

    Rogers, R.D.; Hamilton, M.A.; Veeh, R.H.; McConnell, J.W. Jr.

    1994-04-01

    The Nuclear Regulatory Commission stipulates that disposed low-level radioactive waste (LLW) be stabilized. Because of apparent ease of use and normal structural integrity, cement has been widely used as a binder to solidify LLW. However, the resulting waste forms are sometimes susceptible to failure due to the actions of waste constituents, stress, and environment. This report reviews laboratory efforts that are being developed to address the effects of microbiologically influenced chemical attack on cement-solidified LLW. Groups of microorganisms are being employed that are capable of metabolically converting organic and inorganic substrates into organic and mineral acids. Such acids aggressively react with cement and can ultimately lead to structural failure. Results on the application of mechanisms inherent in microbially influenced degradation of cement-based material are the focus of this report. Sufficient data-validated evidence of the potential for microbially influenced deterioration of cement-solidified LLW has been developed during the course of this study. These data support the continued development of appropriate tests necessary to determine the resistance of cement-solidified LLW to microbially induced degradation that could impact the stability of the waste form. They also justify the continued effort of enumeration of the conditions necessary to support the microbiological growth and population expansion.

  18. Analysis of source term modeling for low-level radioactive waste performance assessments

    International Nuclear Information System (INIS)

    Site-specific radiological performance assessments are required for the disposal of low-level radioactive waste (LLW) at both commercial and US Department of Energy facilities. This work explores source term modeling of LLW disposal facilities by using two state-of-the-art computer codes, SOURCEI and SOURCE2. An overview of the performance assessment methodology is presented, and the basic processes modeled in the SOURCE1 and SOURCE2 codes are described. Comparisons are made between the two advective models for a variety of radionuclides, transport parameters, and waste-disposal technologies. These comparisons show that, in general, the zero-order model predicts undecayed cumulative fractions leached that are slightly greater than or equal to those of the first-order model. For long-lived radionuclides, results from the two models eventually reach the same value. By contrast, for short-lived radionuclides, the zero-order model predicts a slightly higher undecayed cumulative fraction leached than does the first-order model. A new methodology, based on sensitivity and uncertainty analyses, is developed for predicting intruder scenarios. This method is demonstrated for 137Cs in a tumulus-type disposal facility. The sensitivity and uncertainty analyses incorporate input-parameter uncertainty into the evaluation of a potential time of intrusion and the remaining radionuclide inventory. Finally, conclusions from this study are presented, and recommendations for continuing work are made

  19. A unique automation platform for measuring low level radioactivity in metabolite identification studies.

    Directory of Open Access Journals (Sweden)

    Joel Krauser

    Full Text Available Generation and interpretation of biotransformation data on drugs, i.e. identification of physiologically relevant metabolites, defining metabolic pathways and elucidation of metabolite structures, have become increasingly important to the drug development process. Profiling using (14C or (3H radiolabel is defined as the chromatographic separation and quantification of drug-related material in a given biological sample derived from an in vitro, preclinical in vivo or clinical study. Metabolite profiling is a very time intensive activity, particularly for preclinical in vivo or clinical studies which have defined limitations on radiation burden and exposure levels. A clear gap exists for certain studies which do not require specialized high volume automation technologies, yet these studies would still clearly benefit from automation. Use of radiolabeled compounds in preclinical and clinical ADME studies, specifically for metabolite profiling and identification are a very good example. The current lack of automation for measuring low level radioactivity in metabolite profiling requires substantial capacity, personal attention and resources from laboratory scientists. To help address these challenges and improve efficiency, we have innovated, developed and implemented a novel and flexible automation platform that integrates a robotic plate handling platform, HPLC or UPLC system, mass spectrometer and an automated fraction collector.

  20. Results of interagency effort to determine carbon-14 source term in low-level radioactive waste

    International Nuclear Information System (INIS)

    A preliminary estimate of the risks from the shallow land disposal of low-level radioactive wastes by EPA in 1984-1985 indicated that Carbon-14 caused virtually all of the risk and that these risks were relatively high. Therefore, an informal interagency group, which included the US Department of Energy, US Geological Survey, US Nuclear Regulatory Commission, and US Environmental Protection Agency, formed in 1985 to obtain up-to-date information on the activity and chemical form of Carbon-14 in the different types of LLW and how Carbon-14 behaves after disposal. The EPA acted as a focal point for collating the information collected by all of the Agencies and will publish a report in Fall 1986 on the results of the Carbon-14 data collection effort. Of particular importance, the study showed that Carbon-14 activity in LLW was overestimated approximately 2000%. This paper summarizes results of the Carbon-14 data collection effort. 40 references, 1 figure, 3 tables

  1. Hydrogeology of a low-level radioactive-waste disposal site near Sheffield, Illinois

    Science.gov (United States)

    Foster, J.B.; Erickson, J.R.; Healy, R.W.

    1984-01-01

    The Sheffield low-level radioactive-waste facility is located on 20 acres of rolling terrain 3 miles southwest of Sheffield, Illinois. The shallow hydrogeologic system is composed of glacial sediments. Pennsylvania shale and mudstone bedrock isolate the regional aquifers below from the hydrogeologic system in the overlying glacial deposits. Pebbly sand underlies 67 percent of the site. Two ground-water flow paths were identified. The primary path conveys ground water from the site to the east through the pebbly-sand unit; a secondary path conveys ground water to the south and east through less permeable material. The pebbly-sand unit provides an underdrain that eliminates the risk of water rising into the trenches. Digital computer model results indicate that the pebbly-sand unit controls ground-water movement. Tritium found migrating in ground water in the southeast corner of the site travels approximately 25 feet per year. A group of water samples from wells which contained the highest tritium concentrations had specific conductivities, alkalinities, hardness, and chloride, sulfate, calcium, and magnesium contents higher than normal for local shallow ground water. (USGS)

  2. Low-level radioactive Hanford wastes immobilized by cement-based grouts

    International Nuclear Information System (INIS)

    More than 5,300,000 liters (1,400,000 gal) of phosphate/sulfate waste (PSW) grout were produced and placed in vault 101 at the Hanford Site. This waste was generated during decontamination operations and maintenance of the fuel storage basin at the N Reactor. The low-level radioactive liquid wastes were mixed with a blend of portland cement, fly ash, and clays. Through cementing and pozzolanic reactions with water, the grout was solidified to immobilize contaminants and retain low permeability to groundwater. Testing conducted before the campaign is described. The usefulness of each quality verification technique is discussed, focusing mainly on data from the core samples. These data provide the best information on PSW grout since core samples from all regions and depths in the vault were tested. The nondestructive testing data are also useful as they provide property data from broad regions of the vault. The mean compressive strength of the PSW grout cores is 4.17 MPa, much higher than the criterion value of 0.35 MPa. Results also show that the leachability indices for 137Cs, 60Co, sodium, and SO4 for PSW grout cores exceed the leachability criterion by at least one index point. This means that the ability of the grout to resist leaching of waste species is at least ten times greater than the limiting criterion

  3. Codisposal of diminimus levels of low-level radioactive waste and sanitary waste: Final report

    International Nuclear Information System (INIS)

    Codisposal of low-level radioactive waste (LLRW) with municipal refuse was investigated in two pilot-scale controlled concrete lysimeters; 3.05 m x 3.05 m x 4.28 m that were lined with 0.762 mm (30-mil) HDA Gundline liner, elastomeric polyolefin alloy based high density polyethylene, and had provisions for leachate collection and recirculation. Shredded municipal refuse was placed within the landfills and spiked with radionuclides (Co-58, Sr-85, and Ce-141) at a level of 28 nCi/gm to simulate codisposal of LLRW with municipal refuse. Water was added to simulate normal rainfall events; the extent to which radionuclides and organics were leached from both landfills was recorded. To compare the effect of leachate recirculation on the indicator parameters, leachate recycle was practiced in one of the landfills, while the other was operated as a single-pass system. Analyses on leachate samples, collected from both landfills, included detection of Co-58, Sr-85, and Ce-141 along with pH, ORP, conductivity, total alkalinity, COD, BOD5, TOC, volatile fatty acids (acetic, propionic, isobutyric, butyric, and valeric), sulfide, chloride, iron, manganese, zinc, nickel, and cobalt. 113 refs., 47 figs., 23 tabs

  4. Economic analysis of a volume reduction/polyethylene solidification system for low-level radioactive wastes

    International Nuclear Information System (INIS)

    A study was conducted at Brookhaven National Laboratory to determine the economic feasibility of a fluidized bed volume reduction/polyethylene solidification system for low-level radioactive wastes. These results are compared with the ''null'' alternative of no volume reduction and solidification of aqueous waste streams in hydraulic cement. The economic analysis employed a levelized revenue requirement (LRR) technique conducted over a ten year period. An interactive computer program was written to conduct the LRR calculations. Both of the treatment/solidification options were considered for a number of scenarios including type of plant (BWR or PWR) and transportation distance to the disposal site. If current trends in the escalation rates of cost components continue, the volume reduction/polyethylene solidification option will be cost effective for both BWRs and PWRs. Data indicate that a minimum net annual savings of $0.8 million per year (for a PWR shipping its waste 750 miles) and a maximum net annual savings of $9 million per year (for a BWR shipping its waste 2500 miles) can be achieved. A sensitivity analysis was performed for the burial cost escalation rate, which indicated that variation of this factor will impact the total levelized revenue requirement. The burial cost escalation rate which yields a break-even condition was determined for each scenario considered. 11 refs., 8 figs., 39 tabs

  5. Environmental assessment approaches and results for the low level radioactive waste disposal site at Drigg

    Energy Technology Data Exchange (ETDEWEB)

    Fowler, L.; Lean, C

    2005-09-15

    A Post-Closure Radiological Safety Assessment (PCRSA) was undertaken by British Nuclear Fuels plc (BNFL) to support the Post-Closure Safety Case produced in September 2002 for the low level radioactive waste disposal site at Drigg, Cumbria. The PCRSA provided a qualitative and quantitative evaluation of the long-term radiological impacts from disposals at the Drigg site. A structured, iterative approach to the PCRSA was used to define the context and scenarios for consideration, to describe the engineered disposal system and its environment, to assess the impact through calculations and qualitative arguments and to feed back the results to the safety case and forward programme of technical work. The results of the PCRSA have identified that the most important radionuclides in terms of radiological impact are disposed uranium and thorium and their daughter products. The key exposure pathways relating to future impacts are the migration of radionuclides in groundwater and release to future terrestrial environments, exposures resulting from the potential disruption of the site by natural events, such as coastal erosion and glaciation, and speculative inadvertent human intrusion into the site. The PCRSA results have been used to identify areas for potential future work to address key areas of uncertainty, as part of the iterative assessment approach. Further focused analysis has enabled key pessimisms and uncertainties to be identified and assessed in support of the evaluation and development of options for the future management of the Drigg site. (author)

  6. Environmental assessment approaches and results for the low level radioactive waste disposal site at Drigg

    International Nuclear Information System (INIS)

    A Post-Closure Radiological Safety Assessment (PCRSA) was undertaken by British Nuclear Fuels plc (BNFL) to support the Post-Closure Safety Case produced in September 2002 for the low level radioactive waste disposal site at Drigg, Cumbria. The PCRSA provided a qualitative and quantitative evaluation of the long-term radiological impacts from disposals at the Drigg site. A structured, iterative approach to the PCRSA was used to define the context and scenarios for consideration, to describe the engineered disposal system and its environment, to assess the impact through calculations and qualitative arguments and to feed back the results to the safety case and forward programme of technical work. The results of the PCRSA have identified that the most important radionuclides in terms of radiological impact are disposed uranium and thorium and their daughter products. The key exposure pathways relating to future impacts are the migration of radionuclides in groundwater and release to future terrestrial environments, exposures resulting from the potential disruption of the site by natural events, such as coastal erosion and glaciation, and speculative inadvertent human intrusion into the site. The PCRSA results have been used to identify areas for potential future work to address key areas of uncertainty, as part of the iterative assessment approach. Further focused analysis has enabled key pessimisms and uncertainties to be identified and assessed in support of the evaluation and development of options for the future management of the Drigg site. (author)

  7. Determination of 93Zr in medium and low level radioactive wastes from Brazilian nuclear power plants

    International Nuclear Information System (INIS)

    The majority of long-lived radionuclides produced in the nuclear power plants can be regarded as difficult-to-measure radionuclides (RDM), hence chemical separation is necessary before the nuclear measurement of them. The zirconium isotope 93Zr is a long-lived pure β-particle-emitting radionuclide produced from 235U fission and from neutron activation of the stable isotope 92Zr and thus occurring as one of the radionuclides found in nuclear reactors. Due to its long half-life, 93Zr is one of the radionuclides of interest for the performance of assessment studies of waste storage or disposal. Two different methodologies based on extractive resins and LSC and ICP-MS techniques that enables the 93Zr determination in medium (ILW) and low level (LLW) radioactive wastes samples from Brazilian nuclear power plants has been developed in our laboratory. Analyzing real samples 65% and 75% chemical yields for 93Zr recovery were achieved for ICP-MS and LSC techniques, respectively. The detection limits were 0.045 μg.L-1 for ICP-MS and 0.05 Bq.L-1 for LSC techniques. (author)

  8. Hydrogeologic setting east of a low-level radioactive-waste disposal site near Sheffield, Illinois

    Science.gov (United States)

    Foster, J.B.; Garklavs, George; Mackey, G.W.

    1984-01-01

    Core samples from 45 test wells and 4 borings were used to describe the glacial geology of the area east of the low-level radioactive-waste disposal site near Sheffield, Bureau County, Illinois. Previous work has shown that shallow ground water beneath the disposal site flows east through a pebbly-sand unit of the Toulon Member of the Glasford Formation. The pebbly sand was found in core samples from wells in an area extending northeast from the waste-disposal site to a strip-mine lake and east along the south side of the lake. Other stratigraphic units identified in the study area are correlated with units found on the disposal site. The pebbly-sand unit of the Toulon Member grades from a pebbly sand on site into a coarse gravel with sand and pebbles towards the lake. The Hulick Till Member, a key bed, underlies the Toulon Member throughout most of the study area. A narrow channel-like depression in the Hulick Till is filled with coarse gravelly sand of the Toulon Member. The filled depression extends eastward from near the northeast corner of the waste-disposal site to the strip-mine lake. (USGS)

  9. Tritium migration from a low-level radioactive-waste disposal site near Chicago, Illinois

    Science.gov (United States)

    Nicholas, J.R.; Healy, R.W.

    1988-01-01

    This paper describes the results of a study to determine the geologic and hydrologic factors that control migration of tritium from a closed, low-level radioactive-waste disposal site. The disposal site, which operated from 1943 to mid1949, contains waste generated by research activities at the world's first nuclear reactors. Tritium has migrated horizontally at least 1,300 feet northward in glacial drift and more than 650 feet in the underlying dolomite. Thin, gently sloping sand layers in an otherwise clayey glacial drift are major conduits for ground-water flow and tritium migration in a perched zone beneath the disposal site. Tritium concentrations in the drift beneath the disposal site exceed 100,000 nanocuries per liter. Regional horizontal joints in the dolomite are enlarged by solution and are the major conduits for ground-water flow and tritium migration in the dolomite. A weathered zone at the top of the dolomite also is a pathway for tritium migration. The maximum measured tritium concentration in the dolomite is 29.4 nanocuries per liter. Fluctuations of tritium concentration in the dolomite are the result of dilution by seasonal recharge from the drift.

  10. Social assessment of siting a low-level radioactive waste storage facility in Michigan

    Energy Technology Data Exchange (ETDEWEB)

    Stoffle, R.W.; Traugott, M.J.; Stone, J.V.; McIntyre, P.D.; Davidson, C.C.; Jensen, F.V.; Coover, G.E. (Michigan Univ., Ann Arbor, MI (United States))

    1990-01-01

    This report presents findings from a social assessment of siting a low-level radioactive waste storage facility in Michigan. Social assessments derive from direct interaction between researchers and study participants. The report is organized into five chapters. Chapter One, Summary of Findings, focuses on key findings from the statewide telephone surveys and the in-depth ethnographic study conducted by the SNR/ISR study team. These and additional findings are discussed in greater detail in the three subsequent chapters. Chapter Two, Statewide Telephone Survey Findings, presents the knowledge, attitudes and beliefs statewide residents have regarding the LLRW project. Chapter Three, Statewide Demographic Findings, presents a detailed examination of differences among various demographic groups and includes regional analysis. Chapter Four, Hillsdale-area Ethnographic Study Findings, discusses perceived impacts of the proposed LLRW storage facility on local residents who mistakenly came to believe that their area had been specially selected as the location for the facility. Specifically, the chapter presents the development, spread, shape and persistence of what is termed a risk perception shadow in the greater Hillsdale area. Possible causes of the shadow also are discussed, and comparisons are made between statewide and Hillsdale-area survey populations. Chapter Five, Research Methods, presents a discussion of the social assessment research methods used to derive these findings.

  11. A new model for the disposal of low level radioactive waste in Turkey

    International Nuclear Information System (INIS)

    The disposal of radioactive waste which is the last step of radioactive waste management has been the most argued subject of the nuclear industry. Comparing with the high level waste which are in small volumes, the low level radioactive waste are produced in considerable volumes but there are more disposal options for them. The countries apply the proper disposal concepts according to their waste management policies that developed for their conditions. Since such a waste management policy has not been developed in our country, the existing legal situation includes only the discharge limits for the waste to be discharged. The disposal facility is the start point of nuclides to move around. The nuclides are carried with the vertical water movement down to saturated zone after they leaked to soil from bottom of disposal facility. They are carried to far field with the water movement in saturated zone. A radiation dose burden arises when this water is drunk by man or used in agriculture and farms. That dose which is subject to future generations after hundreds of years should be kept in a level that is acceptable as harmless for the existing generations. This rule has been accepted by the countries as a disposal principle. The most important factor effecting the nuclide movement in soil is the water movement. The Darcy velocity in our study is described as the vertical movement velocity of water in soil. The disposal unit of radioactive waste is covered with a very low permeable material therefore Darcy velocity is kept as a constant value while the cap material keeps its integrity. After the complete disintegration of cap material, Darcy velocity reaches to natural soil permeability and can again be assumed as a known value. Uncertainty lays on the duration between these two times on how the velocity will change. The general assumption is that the velocity change will be linear meaning that the last known permeability value of the cap material is directly connected to

  12. Challenges and Lessons Learned in Low-Level Radioactive Waste Management and Disposal in the Texas Compact

    International Nuclear Information System (INIS)

    This paper discusses challenges and lessons learned in approaching the management and disposal of commercial low-level radioactive waste in the Texas Compact. The State of Texas has actively worked decades to address radioactive waste management and disposal issues. The current strides made in Texas on the radioactive waste management front have benefited from unique attributes that help support a public policy foundation. The public policy of radioactive waste management, specifically low-level radioactive waste disposal, has been evolving in Texas for more than twenty years. The policy today is a product of past events and lessons learned. In many ways, public policy on radioactive waste disposal has come full circle. A purely scientific approach to radioactive waste management has not been the solution. Radioactive waste management public policy does not solely rely on technical expertise or state of the best technology. Sound science is simply not enough. Innovation in this case is largely people-based, focused on new ways to communicate and new opportunities to deliver a message of safe and effective radioactive waste management. (authors)

  13. Design and operational considerations of United States commercial nea-surface low-level radioactive waste disposal facilities

    International Nuclear Information System (INIS)

    Low-level radioactive waste disposal standards and techniques in the United States have evolved significantly since the early 1960's. Six commercial LLW disposal facilities(Barnwell, Richland, Ward Valley, Sierra Blanca, Wake County and Boyd County) operated and proposed between 1962 and 1997. This report summarizes each site's design and operational considerations for near-surface disposal of low-level radioactive waste. These new standards and mitigating efforts at closed facilities (Sheffield, Maxey Flats, Beatty and West Valley) have helped to ensure that the public has been safely protected from LLW. 15 refs

  14. Performance assessment methodology and preliminary results for low-level radioactive waste disposal in Taiwan

    International Nuclear Information System (INIS)

    Sandia National Laboratories (SNL) and Taiwan's Institute for Nuclear Energy Research (INER) have teamed together to evaluate several candidate sites for Low-Level Radioactive Waste (LLW) disposal in Taiwan. Taiwan currently has three nuclear power plants, with another under construction. Taiwan also has a research reactor, as well as medical and industrial wastes to contend with. Eventually the reactors will be decomissioned. Operational and decommissioning wastes will need to be disposed in a licensed disposal facility starting in 2014. Taiwan has adopted regulations similar to the US Nuclear Regulatory Commission's (NRC's) low-level radioactive waste rules (10 CFR 61) to govern the disposal of LLW. Taiwan has proposed several potential sites for the final disposal of LLW that is now in temporary storage on Lanyu Island and on-site at operating nuclear power plants, and for waste generated in the future through 2045. The planned final disposal facility will have a capacity of approximately 966,000 55-gallon drums. Taiwan is in the process of evaluating the best candidate site to pursue for licensing. Among these proposed sites there are basically two disposal concepts: shallow land burial and cavern disposal. A representative potential site for shallow land burial is located on a small island in the Taiwan Strait with basalt bedrock and interbedded sedimentary rocks. An engineered cover system would be constructed to limit infiltration for shallow land burial. A representative potential site for cavern disposal is located along the southeastern coast of Taiwan in a tunnel system that would be about 500 to 800 m below the surface. Bedrock at this site consists of argillite and meta-sedimentary rocks. Performance assessment analyses will be performed to evaluate future performance of the facility and the potential dose/risk to exposed populations. Preliminary performance assessment analyses will be used in the site-selection process and to aid in design of the

  15. The Treatment of Low Level Radioactive Liquid Waste Containing Detergent by Biological Activated Sludge Process

    International Nuclear Information System (INIS)

    The treatment of low level radioactive liquid waste containing persil detergent from laundry operation of contaminated clothes by activated sludge process has been done, for alternative process replacing the existing treatment by evaporation. The detergent concentration in water solution from laundry operation is 14.96 g/l. After rinsing operation of clothes and mixing of laundry water solution with another liquid waste, the waste water solution contains about ≤ 1.496 g/l of detergent and 10-3 Ci/m3 of Cs-137 activity. The simulation waste having equivalent activity of Cs-137 10-3 Ci/m3, detergent content (X) 1.496, 0.748, 0.374, 0.187, 0.1496 and 0.094 g/l on BOD value respectively 186, 115, 71, 48, 19, and 16 ppm was processed by activated sludge in reactor of 18.6 l capacity on ambient temperature. It is used Super Growth Bacteria (SGB) 102 and SGB 104, nitrogen and phosphor nutrition, and aeration. The result show that bacteria of SGB 102 and SGB 104 were able to degrade the persil detergent for attaining standard quality of water release category B in which BOD values 6 ppm. It was need 30 hours for X ≤ 0.187 g/l, 50 hours for 0.187 < X ≤ 0.374 g/l, 75 hours for 0.374 < X ≤ 0.748, and 100 hours for 0.748 < X ≤ 1.496 g/l. On the initial period the bacteria of SGB 104 interact most quickly to degrade the detergent comparing SGB 102. Biochemical oxidation process decontaminate the solution on the decontamination factor of 350, Cs-137 be concentrate in sludge by complexing with the bacteria wall until the activity of solution be become very low. (author)

  16. Use of engineered soils and other site modifications for low-level radioactive waste disposal

    International Nuclear Information System (INIS)

    The U.S. Nuclear Regulatory Commission requires that low-level radioactive waste (LLW) disposal facilities be designed to minimize contact between waste and infiltrating water through the use of site design features. The purpose of this investigation is to identify engineered barriers and evaluate their ability to enhance the long-term performance of an LLW disposal facility. Previously used barriers such as concrete overpacks, vaults, backfill, and engineered soil covers, are evaluated as well as state-of-the-art barriers, including an engineered sorptive soil layer underlying a facility and an advanced design soil cover incorporating a double-capillary layer. The purpose of this investigation is also to provide information in incorporating or excluding specific engineered barriers as part of new disposal facility designs. Evaluations are performed using performance assessment modeling techniques. A generic reference disposal facility design is used as a baseline for comparing the improvements in long-term performance offered by designs incorporating engineered barriers in generic and humid environments. These evaluations simulate water infiltration through the facility, waste leaching, radionuclide transport through the facility, and decay and ingrowth. They also calculate a maximum (peak annual) dose for each disposal system design. A relative dose reduction factor is calculated for each design evaluated. The results of this investigation are presented for concrete overpacks, concrete vaults, sorptive backfill, sorptive engineered soil underlying the facility, and sloped engineered soil covers using a single-capillary barrier and a double-capillary barrier. Designs using combinations of barriers are also evaluated. These designs include a vault plus overpacks, sorptive backfill plus overpacks, and overpack with vault plus sorptive backfill, underlying sorptive soil, and engineered soil cover

  17. Use of engineered soils and other site modifications for low-level radioactive waste disposal

    Energy Technology Data Exchange (ETDEWEB)

    1994-08-01

    The U.S. Nuclear Regulatory Commission requires that low-level radioactive waste (LLW) disposal facilities be designed to minimize contact between waste and infiltrating water through the use of site design features. The purpose of this investigation is to identify engineered barriers and evaluate their ability to enhance the long-term performance of an LLW disposal facility. Previously used barriers such as concrete overpacks, vaults, backfill, and engineered soil covers, are evaluated as well as state-of-the-art barriers, including an engineered sorptive soil layer underlying a facility and an advanced design soil cover incorporating a double-capillary layer. The purpose of this investigation is also to provide information in incorporating or excluding specific engineered barriers as part of new disposal facility designs. Evaluations are performed using performance assessment modeling techniques. A generic reference disposal facility design is used as a baseline for comparing the improvements in long-term performance offered by designs incorporating engineered barriers in generic and humid environments. These evaluations simulate water infiltration through the facility, waste leaching, radionuclide transport through the facility, and decay and ingrowth. They also calculate a maximum (peak annual) dose for each disposal system design. A relative dose reduction factor is calculated for each design evaluated. The results of this investigation are presented for concrete overpacks, concrete vaults, sorptive backfill, sorptive engineered soil underlying the facility, and sloped engineered soil covers using a single-capillary barrier and a double-capillary barrier. Designs using combinations of barriers are also evaluated. These designs include a vault plus overpacks, sorptive backfill plus overpacks, and overpack with vault plus sorptive backfill, underlying sorptive soil, and engineered soil cover.

  18. Intermodal transportation of low-level radioactive waste to the Nevada Test Site

    International Nuclear Information System (INIS)

    The Nevada Test Site (NTS) presently serves as a disposal site for low-level radioactive waste (LLW) generated by DOE-approved generators. The environmental impacts resulting from the disposal of LLW at the NTS are discussed in the Final Environmental Impact Statement (EIS) for the Nevada Test Site Off-Site Locations in the State of Nevada (NTS EIS). During the formal NTS EIS scoping period, it became clear that transportation of LLW was an issue that required attention. Therefore, the Nevada Transportation Protocol Working Group (TPWG) was formed in 1995 to identify, prioritize, and understand local issues and concerns associated with the transportation of LLW to the NTS. Currently, generators of LLW ship their waste to the NTS by legal-weight truck. In 1995, the TPWG suggested the DOE could reduce transportation costs and enhance public safety by using rail transportation. The DOE announced, in October 1996, that they would study the potential for intermodal transportation of LLW to the NTS, by transferring the LLW containers from rail cars to trucks for movements to the NTS. The TPWG and DOE/NV prepared the NTS Intermodal Transportation Facility Site and Routing Evaluation Study to present basic data and analyses on alternative rail-to-truck transfer sites and related truck routes for LLW shipments to the NTS. This Environmental Assessment (EA) identifies the potential environmental impacts and transportation risks of using new intermodal transfer sites and truck routes or continuing current operations to accomplish the objectives of minimizing radiological risk, enhancing safety, and reducing cost. DOE/NV will use the results of the assessment to decide whether or not to encourage the LLW generators and their transportation contractors to change their current operations to accomplish these objectives

  19. Storage for greater-than-Class C low-level radioactive waste

    Energy Technology Data Exchange (ETDEWEB)

    Beitel, G.A. [EG and G Idaho, Inc., Idaho Falls, ID (United States). Idaho National Engineering Lab.

    1991-12-31

    EG and G Idaho, Inc., at the Idaho National Engineering Laboratory (INEL) is actively pursuing technical storage alternatives for greater-than-Class C low-level radioactive waste (GTCC LLW) until a suitable licensed disposal facility is operating. A recently completed study projects that between 2200 and 6000 m{sup 3} of GTCC LLW will be generated by the year 2035; the base case estimate is 3250 m{sup 3}. The current plan envisions a disposal facility available as early as the year 2010. A long-term dedicated storage facility could be available in 1997. In the meantime, it is anticipated that a limited number of sealed sources that are no longer useful and have GTCC concentrations of radionuclides will require storage. Arrangements are being made to provide this interim storage at an existing DOE waste management facility. All interim stored waste will subsequently be moved to the dedicated storage facility once it is operating. Negotiations are under way to establish a host site for interim storage, which may be operational, at the earliest, by the second quarter of 1993. Two major activities toward developing a long-term dedicated storage facility are ongoing. (a) An engineering study, which explores costs for alternatives to provide environmentally safe storage and satisfy all regulations, is being prepared. Details of some of the findings of that study will be presented. (b) There is also an effort under way to seek the assistance of one or more private companies in providing dedicated storage. Alternatives and options will be discussed.

  20. Estimating Radiological Doses to Predators Foraging in a Low-Level Radioactive Waste Management Area

    Energy Technology Data Exchange (ETDEWEB)

    L.Soholt; G.Gonzales; P.Fresquez; K.Bennett; E.Lopez

    2003-03-01

    Since 1957, Los Alamos National Laboratory has operated Area G as its low-level, solid radioactive waste management and disposal area. Although the waste management area is developed, plants, small mammals, and avian and mammalian predators still occupy the less disturbed and revegetated portions of the land. For almost a decade, we have monitored the concentrations of selected radionuclides in soils, plants, and small mammals at Area G. The radionuclides tritium, plutonium-238, and plutonium-239 are regularly found at levels above regional background in all three media. Based on radionuclide concentrations in mice collected from 1994 to 1999, we calculated doses to higher trophic levels (owl, hawk, kestrel, and coyote) that forage on the waste management area. These predators play important functions in the regional ecosystems and are an important part of local Native American traditional tales that identify the uniqueness of their culture. The estimated doses are compared to Department of Energy's interim limit of 0.1 rad/day for the protection of terrestrial wildlife. We used exposure parameters that were derived from the literature for each receptor, including Environmental Protection Agency's exposure factors handbook. Estimated doses to predators ranged from 9E-06 to 2E-04 rad/day, assuming that they forage entirely on the waste management area. These doses are greater than those calculated for predators foraging exclusively in reference areas, but are still well below the interim dose limit. We believe that these calculated doses represent upper-bound estimates of exposure for local predators because the larger predators forage over areas that are much greater than the 63-acre waste management area. Based on these results, we concluded that predators foraging on this area do not face a hazard from radiological exposure under current site conditions.

  1. Several Opinions on Very Low Level Radioactive Waste%浅谈极低放射性废物

    Institute of Scientific and Technical Information of China (English)

    徐春艳; 杨海峰

    2011-01-01

    介绍了国际国内极低放射性废物的定义以及活度上限值的确定依据,并介绍了国内外的处置方法,以期对我国的放射性废物分类管理、审评和监督有所帮助。%This article sums up international experience about the classification principle, disposal and specific activity limits of very low level radioactive waste, and introduces practice on very low level radioactive waste disposal. The author hopes this will be helpful in the field of radioactive waste manage- ment, review and inspection.

  2. A Probabilistic Performance Assessment Study of Potential Low-Level Radioactive Waste Disposal Sites in Taiwan

    Science.gov (United States)

    Knowlton, R. G.; Arnold, B. W.; Mattie, P. D.; Kuo, M.; Tien, N.

    2006-12-01

    For several years now, Taiwan has been engaged in a process to select a low-level radioactive waste (LLW) disposal site. Taiwan is generating LLW from operational and decommissioning wastes associated with nuclear power reactors, as well as research, industrial, and medical radioactive wastes. The preliminary selection process has narrowed the search to four potential candidate sites. These sites are to be evaluated in a performance assessment analysis to determine the likelihood of meeting the regulatory criteria for disposal. Sandia National Laboratories and Taiwan's Institute of Nuclear Energy Research have been working together to develop the necessary performance assessment methodology and associated computer models to perform these analyses. The methodology utilizes both deterministic (e.g., single run) and probabilistic (e.g., multiple statistical realizations) analyses to achieve the goals. The probabilistic approach provides a means of quantitatively evaluating uncertainty in the model predictions and a more robust basis for performing sensitivity analyses to better understand what is driving the dose predictions from the models. Two types of disposal configurations are under consideration: a shallow land burial concept and a cavern disposal concept. The shallow land burial option includes a protective cover to limit infiltration potential to the waste. Both conceptual designs call for the disposal of 55 gallon waste drums within concrete lined trenches or tunnels, and backfilled with grout. Waste emplaced in the drums may be solidified. Both types of sites are underlain or placed within saturated fractured bedrock material. These factors have influenced the conceptual model development of each site, as well as the selection of the models to employ for the performance assessment analyses. Several existing codes were integrated in order to facilitate a comprehensive performance assessment methodology to evaluate the potential disposal sites. First, a need

  3. Proposed plan for vitrification demonstration of low-level radioactive wastes at the Fernald Environmental Management Project

    International Nuclear Information System (INIS)

    Glassware was made by the Romans several hundreds of years before Christ. Some of this glassware was discovered in ship wreckage at sea. The glassware has eroded less than 1/2 mm over 2500 years. The erosion rate of the crude Roman glass in corrosive salt water implies that low-level radioactive wastes dissolved in molten glass should remain entombed in the glass for extremely long periods of time (10,000 years plus). The extremely low leach rate for such a glass should keep concentrations in the environment below all regulatory limits and by that provide protection of the environment indefinitely. Vitrification is considered, by many, as a most effective (if not the most effective) treatment method for disposal of radioactive and numerous inorganic hazardous wastes. However, vitrification of low-level radioactive wastes at large production/commercial rates has not been accomplished and needs to be demonstrated to justify selecting vitrification as a competitive alternative to other treatment methods. This paper describes a proposed plan to demonstrate vitrification of low-level radioactive wastes at the Fernald Site (FS) located near Cincinnati, Ohio. Demonstrations will progress from laboratory to on-site bench-scale, to a pilot size, then to full-sized vitrifiers (glass melters). The bench sized unit will mainly prove the process and develop glass mixes using various waste forms and glass formers. The pilot scale unit will evaluate and develop operational requirements and processes. 3 figs., 2 tabs

  4. Potential impacts of 40 CFR 193 on the development of low-level radioactive waste disposal facilities

    Energy Technology Data Exchange (ETDEWEB)

    Alvarado, R.A. [Texas Low-Level Radioactive Waste Disposal Authority, Austin, TX (United States)

    1989-11-01

    Since the publication of the Advanced Notice of Proposed Rulemaking in August, 1983, the proposed environmental regulations regarding low-level radioactive waste have become a serious uncertainty in the development of new low-level radioactive waste disposal facilities. The proposed rule has been discussed on several occasions by the Technical Coordinating Committee and the purpose of this paper is to present the results of the Committee`s discussions regarding the proposed rule. The proposed standard has several closely related elements. The rule would prescribe limits on radiation exposure to individuals during processing, management and storage of low-level radioactive waste. It would set BRC levels and also set dose standards for the period following site closure. An important portion of the standard, as far as developing new facilities, is the ground water protection standard. The comments received during developing of 40 CFR 193 has also led the Environmental Protection Agency to propose 40 CFR 764 governing the disposal of naturally occurring radioactive material or NORM.

  5. Greater-than-Class C low-level radioactive waste shipping package/container identification and requirements study. National Low-Level Waste Management Program

    Energy Technology Data Exchange (ETDEWEB)

    Tyacke, M.

    1993-08-01

    This report identifies a variety of shipping packages (also referred to as casks) and waste containers currently available or being developed that could be used for greater-than-Class C (GTCC) low-level waste (LLW). Since GTCC LLW varies greatly in size, shape, and activity levels, the casks and waste containers that could be used range in size from small, to accommodate a single sealed radiation source, to very large-capacity casks/canisters used to transport or dry-store highly radioactive spent fuel. In some cases, the waste containers may serve directly as shipping packages, while in other cases, the containers would need to be placed in a transport cask. For the purpose of this report, it is assumed that the generator is responsible for transporting the waste to a Department of Energy (DOE) storage, treatment, or disposal facility. Unless DOE establishes specific acceptance criteria, the receiving facility would need the capability to accept any of the casks and waste containers identified in this report. In identifying potential casks and waste containers, no consideration was given to their adequacy relative to handling, storage, treatment, and disposal. Those considerations must be addressed separately as the capabilities of the receiving facility and the handling requirements and operations are better understood.

  6. The analysis of low-level radioactivity using the Bayesian statistics

    International Nuclear Information System (INIS)

    The analysis of low-level or dominant background dominant radioactiviy is complicated by the fact that sample net rate of activity above background may be negative, because of random fluctuations. (authors)

  7. Complex-wide review of DOE`s management of low-level radioactive waste - progress to date

    Energy Technology Data Exchange (ETDEWEB)

    Letourneau, M.J.

    1995-12-31

    The Defense Nuclear Facilities Safety Board (DNFSB) Recommendation 94-2 includes a recommendation that the Department of Energy (DOE) conduct a comprehensive, complex-wide review of the low-level waste issue to establish the dimensions of the low-level waste problem and to identify necessary corrective actions to address the safe disposition of past, present, and future volumes. DOE`s Implementation Plan calls for the conduct of a complex-wide review of low-level radioactive waste treatment, storage, and disposal sites to identify environmental, safety, and health vulnerabilities. The complex-wide review focuses on low-level waste disposal facilities through a site evaluation survey, reviews of existing documentation, and onsite observations. Low-level waste treatment and storage facilities will be assessed for their ability to meet waste acceptance criteria for disposal. Results from the complex-wide review will be used to form the basis for an integrated and planned set of actions to correct the identified vulnerabilities and to prompt development of new requirements for managing low-level waste.

  8. Evapotranspiration and microclimate at a low-level radioactive-waste disposal site in northwestern Illinois

    Science.gov (United States)

    Healy, R.W.; DeVries, M.P.; Sturrock, Alex M.

    1989-01-01

    From July 1982 through June 1984, a study was made of the evapotranspiration and microclimate at a low-level radioactive-waste disposal site near Sheffield, Bureau County, Illinois. Vegetation at the site consists of mixed pasture grasses, primarily awnless brome (Bromus inermis) and red clover (Trifoleum pratense). Three methods were used to estimate evapotranspiration: (1) an energy budget with the Bowen ratio, (2) an aerodynamic profile, and (3) a soil-based water budget. For the aerodynamic-profile method, sensible-heat flux was estimated by a profile equation and evapotranspiration was then calculated as the residual in the energy-balance equation. Estimates by the energy-budget and aerodynamic-profile methods were computed from hourly data and then summed by days and months. Yearly estimates (for March through November) by these methods were in close agreement: 648 and 626 millimeters, respectively. Daily estimates reach a maximum of about 6 millimeters. The water-budget method produced only monthly estimates based on weekly or biweekly soil-moisture content measurements. The yearly evapotranspiration estimated by this method (which actually included only the months of April through October) was 655 millimeters. The March-through-November average for the three methods of 657 millimeters was equivalent to 70 percent of total precipitation. Continuous measurements were made of incoming and reflected shortwave radiation, incoming and emitted longwave radiation, net radiation, soil-heat flux, soil temperature, horizontal windspeed, and wet- and dry-bulb air temperature. Windspeed and air temperature were measured at heights of 0.5 and 2.0 meters (and also at 1.0 meter after September 1983). Soilmoisture content of the soil zone was measured with a gamma-attenuation gage. Annual precipitation (938 millimeters) and average temperature (10.8 degrees Celsius) at the Sheffield site were virtually identical to long-term averages from nearby National Weather Service

  9. Cold laboratory test on nuclide removal from Low-Level Radioactive Liquid Waste by lanthanum phosphate reduction coprecipitation method

    Energy Technology Data Exchange (ETDEWEB)

    Igarashi, T. [Nuclear Technology and Engineering Corp., Tokai, Ibaraki (Japan); Fukumoto, Masahiro; Murata, E.; Kobayashi, T.; Ikeda, Satoshi

    1999-02-01

    Low Level Radioactive Waste Treatment Facility (LWTF) for the removal of radionuclides contained in Low Level Radioactive Liquid Waste (LLLW) from reprocessing plant in JNC Tokai Works is now under construction. The primary process has now been designed to be complex processes: removal of iodine, of carbonic acid in solution, of lanthanides coprecipitated with ferric hydroxide and of remaining radionuclides such as strontium can cesium. However, the study on the behavior of ruthenium in the coprecipitation process revealed that it is insufficient for removal of ruthenium. As an alternative process, coprecipitation with lanthanum phosphate method substituting for ferric hydroxide was studied. As the result of test, it was confirmed that the method is practical to remove ruthenium with other lanthanides from LLLW except strontium. In this report, the preliminary cold test was described briefly. (H. Itami)

  10. Gamma-ray spectrometry of ultra low levels of radioactivity within the material screening program for the GERDA experiment.

    Science.gov (United States)

    Budjás, D; Gangapshev, A M; Gasparro, J; Hampel, W; Heisel, M; Heusser, G; Hult, M; Klimenko, A A; Kuzminov, V V; Laubenstein, M; Maneschg, W; Simgen, H; Smolnikov, A A; Tomei, C; Vasiliev, S I

    2009-05-01

    In present and future experiments in the field of rare events physics a background index of 10(-3) counts/(keV kg a) or better in the region of interest is envisaged. A thorough material screening is mandatory in order to achieve this goal. The results of a systematic study of radioactive trace impurities in selected materials using ultra low-level gamma-ray spectrometry in the framework of the GERDA experiment are reported. PMID:19243966

  11. Performance evaluation and operational experience with a semi-automatic monitor for the radiological characterization of low-level wastes

    International Nuclear Information System (INIS)

    Chalk River Nuclear Laboratories (CRNL) have undertaken a Waste Disposal Project to co-ordinate the transition from the current practice of interim storage to permanent disposal for low-level radioactive wastes (LLW). The strategy of the project is to classify and segregate waste segments according to their hazardous radioactive lifetimes and to emplace them in disposal facilities engineered to isolate and contain them. To support this strategy, a waste characterization program was set up to estimate the volume and radioisotope inventories of the wastes managed by CRNL. A key element of the program is the demonstration of a non-invasive measurement technique for the isotope-specific characterization of solid LLW. This paper describes the approach taken at CRNL for the non-invasive assay of LLW and the field performance and early operational experience with a waste characterization monitor to be used in a waste processing facility

  12. Quality assurance for the transportation of hazardous (low-level radioactive, chemical/toxic, and medical) wastes

    International Nuclear Information System (INIS)

    The federal regulatory program governing the transportation of hazardous (low-level radioactive, chemical/toxic, and medical) wastes presently resides in many pieces of enabling legislation. With the advent of the Resource Conservation and Recovery Act, medical Waste Tracking Act, Low-Level Radioactive Waste Policy Act, and the myriad of federal, state, and local regulations, the transportation of hazardous waste has become subject to complex and confused regulatory requirements. As a result, the regulatory program is haphazard and is administered by a variety of regulatory departments, agencies, and offices. No one agency has taken the complete responsibility for a safe cradle-to-grave control. The Quality Assurance Program described in this paper provides the user with attributes necessary for consideration in the development of an effective system for the transportation of low-level radioactive, chemical/toxic, and medical wastes. The recommended program provides basic user-oriented guidelines to be implemented in developing such a system. The proposed guidelines provide a comprehensive method for management to control the handling and transportation of hazardous wastes. The systematic approach described will increase the level of public confidence in the ability of an organization to handle and safely transport hazardous wastes

  13. Recommendations for siting, development, and operation of a regional low-level radioactive waste disposal facility in Ohio

    Energy Technology Data Exchange (ETDEWEB)

    Harf, J.

    1994-12-31

    In 1984, pursuant to passage of the federal Low-Level Radioactive Waste Policy Act of 1980, the Ohio General Assembly voted overwhelmingly to join the Midwest Interstate Low-Level Radioactive Waste Commission. The original members of the Midwest Compact were Indiana, Iowa, Michigan, Minnesota, Missouri, Ohio, and Wisconsin; however, Michigan was expelled in July 1991, for failure to fulfill its obligations as host state for the first regional facility. At that time, Ohio assumed responsibility as host state and proceeded to negotiate amendments to the Compact. In September 1992, the legislative leadership requested that Governor George V. Voinovich appoint a Blue Ribbon Committee to offer recommendations on siting criteria and that the Low-Level Radioactive Waste Advisory Committee report on other aspects of facility development, operation, and long-term care. After a year of meetings, public hearings, and deliberation, the two reports were released. The reports contain detailed recommendations on a wide variety of issues, including socio-economic, hydrogeologic, and health effects criteria; the establishment of an administrative structure and process; implementation of public education and information programs; community compensation and benefits plans; and achievement of agreement state status with the NRC for purposes of licensing and regulating the Ohio facility. The recommendations will be incorporated into enabling legislation for introduction later this year.

  14. Regulatory control of solid low level radioactive waste disposal in the UK

    International Nuclear Information System (INIS)

    The following topics are described: (i) regulatory authorities; (ii) inspection; (iii) waste categories; (iv) disposal routes for low level waste; (v) inspection of disposal routes; (vi) waste quality checking; (vii) reporting and application of results; and (viii) European Network activities. (P.A.)

  15. 1979 state-by-state assessment of low-level radioactive wastes shipped to commercial burial grounds

    International Nuclear Information System (INIS)

    This report provides, on a state-by-state basis, estimates of the quantities and characteristics of low-level radioactive wastes (LLW) generated in 1979 in the following sectors: commercial nuclear power plants, medical and educational institutions, industry (other than commercial nuclear power plants), and government and military. An estimated 79,914 cm3 of radioactive waste, containing 477,437 Ci of radioactivity were buried in the three US commercial burial grounds in 1979. By the best approximation available at the time of this report, the volume that could be attributed to the industrial category is 17,881 cm3 and the volume that could be attributed to the institutional category is 14,954 cm3. No curie breakdown is possible from available sources of information

  16. Review of state licenses for disposal of low-level radioactive waste by shallow land burial. Technical note

    International Nuclear Information System (INIS)

    State licenses for disposal of low-level radioactive wastes at commercial burial sites are reviewed. Information concerning license terms and conditions, and license administration has been obtained from questionnaires sent to those six states with commercial radioactive waste burial sites. The questionnaire information has been supplemented by recent reports of the Task Force on Radioactive Waste Management of the Conference of Radiation Control Program Directors and personal communications with knowledgeable officials in state and Federal agencies. A number of problems associated with licensing and license administration by the states have been identified by the Task Force, by the Federal Government Accounting Office (GAO), and by various state and Federal officials. These are summarized and recommendations are included

  17. Developing expert systems for hazardous and low-level radioactive waste management

    International Nuclear Information System (INIS)

    Information about management of hazardous and low level wastes has been deposited in data bases, text files, graphics files, and other types of computer programs. Integrating such diverse data so that they are easily and quickly retrievable represents a challenge for busy managers who require immediate answers to their problems. Expert programs have been developed using expert shells and artificial intelligence computer languages as the central environment to produce integration

  18. The intrusion of low-level radioactive waste into Dublin Bay

    International Nuclear Information System (INIS)

    Artificial radionuclides principally caesium-137 and caesium-134, derived from Sellafield effluents are present at low concentrations in the marine environment of Dublin Bay. Results of a survey of radioactivity levels in the Western Irish Sea are presented in this report and an estimate is given of the annual dose equivalent to members of the Irish fish consuming population from radiocaesium

  19. Volume reduction and encapsulation process for water containing low level radioactive waste

    International Nuclear Information System (INIS)

    In encapsulating solutions or slurries of radio-active waste within polymeric material for disposal, the water is removed therefrom by adding a water insoluble liquid forming a low boiling azeotrope and evaporating the azeotrope, and then a polymerisable composition is dispersed throughout the dewatered waste and allowed to set. (author)

  20. Expediting the commercial disposal option: Low-level radioactive waste shipments from the Mound Plant

    Energy Technology Data Exchange (ETDEWEB)

    Rice, S.; Rothman, R.

    1995-12-31

    In April, Envirocare of Utah, Inc., successfully commenced operation of its mixed waste treatment operation. A mixed waste which was (a) radioactive, (b) listed as a hazardous waste under the Resource Conservation and Recovery Act (RCRA), and (c) prohibited from land disposal was treated using Envirocare`s full-scale Mixed Waste Treatment Facility. The treatment system involved application of chemical fixation/stabilization technologies to reduce the leachability of the waste to meet applicable concentration-based RCRA treatment standards. In 1988, Envirocare became the first licensed facility for the disposal of naturally occurring radioactive material. In 1990, Envirocare received a RCRA Part B permit for commercial mixed waste storage and disposal. In 1994, Envirocare was awarded a contract for the disposal of DOE mixed wastes. Envirocare`s RCRA Part B permit allows for the receipt, storage, treatment, and disposal of mixed wastes that do not meet the land-disposal treatment standards of 40 CFR (Code of Federal Regulations) 268. Envirocare has successfully received, managed, and disposed of naturally occurring radioactive material, low-activity radioactive waste, and mixed waste from government and private generators.

  1. Geochemical information for the West Chestnut Ridge Central Waste Disposal Facility for low-level radioactive waste

    Energy Technology Data Exchange (ETDEWEB)

    Seeley, F.G.; Kelmers, A.D.

    1984-06-01

    Geochemical support activities for the Central Waste Disposal Facility (CWDF) project included characterization of site materials, as well as measurement of radionuclide sorption and desorption isotherms and apparent concentration limit values under site-relevant laboratory test conditions. The radionuclide sorption and solubility information is needed as input data for the pathways analysis calculations to model expected radioactivity releases from emplaced waste to the accessible environment under various release scenarios. Batch contact methodology was used to construct sorption and desorption isotherms for a number of radionuclides likely to be present in waste to be disposed of at the site. The sorption rates for uranium and europium were rapid (> 99.8% of the total radionuclide present was adsorbed in approx. 30 min). With a constant-pH isotherm technique, uranium, strontium, cesium, and curium exhibited maximum Rs values of 4800 to > 30,000 L/kg throughout the pH range 5 to 7. Sorption ratios were generally lower at higher or lower pH levels. Retardation factors for uranium, strontium, and cesium, explored by column chromatographic tests, were consistent with the high sorption ratios measured in batch tests for these radionuclides. The addition of as little as 0.01 M organic reagent capable of forming strong soluble complexes with metals (e.g., ethylenediaminetetraacetic acid (EDTA) or citric acid) was found to reduce the sorption ratio for uranium by as much as two orders of magnitude. Substitution of an actual low-level waste site trench water for groundwater in these tests was found to give a similar reduction in the sorption ratio.

  2. Geochemical information for the West Chestnut Ridge Central Waste Disposal Facility for low-level radioactive waste

    International Nuclear Information System (INIS)

    Geochemical support activities for the Central Waste Disposal Facility (CWDF) project included characterization of site materials, as well as measurement of radionuclide sorption and desorption isotherms and apparent concentration limit values under site-relevant laboratory test conditions. The radionuclide sorption and solubility information is needed as input data for the pathways analysis calculations to model expected radioactivity releases from emplaced waste to the accessible environment under various release scenarios. Batch contact methodology was used to construct sorption and desorption isotherms for a number of radionuclides likely to be present in waste to be disposed of at the site. The sorption rates for uranium and europium were rapid (> 99.8% of the total radionuclide present was adsorbed in approx. 30 min). With a constant-pH isotherm technique, uranium, strontium, cesium, and curium exhibited maximum Rs values of 4800 to > 30,000 L/kg throughout the pH range 5 to 7. Sorption ratios were generally lower at higher or lower pH levels. Retardation factors for uranium, strontium, and cesium, explored by column chromatographic tests, were consistent with the high sorption ratios measured in batch tests for these radionuclides. The addition of as little as 0.01 M organic reagent capable of forming strong soluble complexes with metals [e.g., ethylenediaminetetraacetic acid (EDTA) or citric acid] was found to reduce the sorption ratio for uranium by as much as two orders of magnitude. Substitution of an actual low-level waste site trench water for groundwater in these tests was found to give a similar reduction in the sorption ratio

  3. Operational and regulatory impacts of regional management on transportation of commercial low-level radioactive waste

    International Nuclear Information System (INIS)

    Results of the analysis indicate that a factor of two reduction in total shipping distance and cost is possible on a national scale if regional disposal sites are employed. Likewise, population risks and the demand for transportation services and equipment would be proportionally reduced because of shorter shipment distances and trip durations. The fate of regionalization of low level waste management and achievement of the cost and risk benefits that it implies is dependent on solving technical problems and resolving the institutional issues which result in multiple levels of regulations

  4. Preliminary state-by-state assessment of low-level radioactive wastes shipped to commercial burial grounds

    International Nuclear Information System (INIS)

    This report provides, on a state-by-state basis, estimates of the quantities and characteristics of low-level radioactive wastes (LLW) generated in the following sectors: commercial nuclear power plants, medical and educational institutions, industry (other than commercial nuclear power plants), and government and military. An estimated 83,800 cm3 of radioactive waste, containing 886,000 Ci of radioactivity were buried in the four US commercial burial grounds in 1978. Data have been reported on wastes generated from reactor, institutional, and government/military sectors but not from industrial users of radioactive materials. The non-industrial sources account for about 76% of all wastes by volume, and 54% of the recorded activity of the wastes buried. There is no survey information available on the producers of radioactive wastes from non-nuclear fuel-cycle industrial sources. In 1978 this segment may have produced an estimated 24% of the volume and as much as 46% of the activity shipped to commercial burial grounds. A significant portion of the estimates of the quantity and distribution of LLW contained in this report have been obtained by extrapolation or estimation from secondary sources of information. Therefore, the data are preliminary and subject to change or confirmation based on the findings of the extensive survey now underway

  5. Environmental surveillance of low-level radioactive waste management areas at Los Alamos during 1985

    International Nuclear Information System (INIS)

    This report was compiled as a part of the DOE-sponsored radioactive waste site surveillance program at Los Alamos National Laboratory. The report is a source document for data collected in 1985. However, an attempt is made to interpret the data as it relates to radionuclide transport to serve in guiding future waste site surveillance activities. This report contains information on one active and 11 inactive radioactive waste management areas at Los Alamos. Sections include the use history, current status, and future stabilization needs for all sites; the results of detailed surveillance activities at Areas G and C; and a dose evaluation based on the waste site and Laboratory environmental surveillance data. 9 refs., 30 figs., 13 tabs

  6. 1983 state-by-state assessment of low-level radioactive wastes shipped to commercial disposal sites

    International Nuclear Information System (INIS)

    The 1983 report uses the volume of low-level waste reported as received at each commercial disposal site as the national baseline figure. A volume of 76,702 m3 of radioactive waste containing 505,340 Ci of activity was reported disposed at the commercial sites in 1983. The distribution of these waste volumes by disposal site is tabulated. Typical radionuclides in low-level wastes by sector are given. Predominant waste forms associated with low-level waste by sector are tabulated. Sometimes the amount of waste reported by power facilities is equal to or exceeds the state volume reported from commercial disposal site operators. Discrepancies may be a result of waste volumes being credited to the home state of the waste broker instead of the actual state location of the generator. Additionally, waste volumes may have been in transit from the generator to the disposal site at year's end. The Low-Level Waste Management Program felt a responsibility to report information accurately from the various sources, so did not alter the figures to make them balance

  7. Study on Method of Asphalt Density Measurement Using Low Level Radioactive Isotope

    International Nuclear Information System (INIS)

    The fundamental cause of damage to road pavement is insufficient management of asphalt density during construction. Currently, asphalt density in Korea is measured in a laboratory by extracting a core sample after construction. This method delays the overall time of measurement and therefore it is difficult to achieve real-time density management. Using a radioactive isotope for measuring asphalt density during construction reduces measuring time thus enabling realtime measurement. Also, it is provided reliable density measurement to achieve effective density management at work sites. However, existing radiological equipment has not been widely used because of management restrictions and regulations due to the high radiation dose. In this study, we employed a non-destructive method for density measurement. Density is measured by using a portable gamma-ray backscatter device having a radioactivity emission of 100 μCi or less (notice No. 2002-23, Ministry of Science and Technology, standards on radiation protection, etc.), a sealed radioactive source subject to declaration

  8. Development of volume reduction treatment techniques for low level radioactive wastes

    International Nuclear Information System (INIS)

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

  9. Applications of the Long-Range Alpha Detector (LRAD) technology to low-level radioactive waste management

    International Nuclear Information System (INIS)

    Long-Range Alpha Detector (LRAD) systems are designed to monitor alpha contamination by measuring the number of ions in the air. Alpha particles are a form of ionizing radiation and a typical 5-MeV alpha particle will create about 150,000 ion pairs in air. Field tests at various DOE sites have shown that LRAD Surface Soil Monitors (SSM), Sample Monitors, and Object Monitors are faster and more sensitive than traditional alpha detectors for measuring alpha contamination. This paper discusses the various applications of LRAD technology to low-level radioactive waste management

  10. Development of radiological impact assessments for the Drigg low-level radioactive waste disposal site

    International Nuclear Information System (INIS)

    The Drigg low-level waste disposal site has developed from simple trenches cut in clay, accepting loosely tipped waste, to an engineered vault constructed of reinforced concrete receiving containerised waste. The paper describes the associated development of the radiological impact assessments and how those assessments have been influenced by the development of legislation and Government policy. The current deterministic risk assessment is described and the major conclusions presented. The successor to this model is based on a 3-D network approach to the representation of site specific engineering and geological features, with compartmental modelling of the biosphere. The development of this model, which will be used in deterministic and probabilistic modes for the next assessment, is described. 12 refs., 1 fig., 2 tabs

  11. Microbial aspects of gas generation from low level radioactive waste simulant

    International Nuclear Information System (INIS)

    This report details the experimental work undertaken to further the understanding of the kinetics of methanogenesis associated with radioactive LLW disposal. A series of treatments were established by inoculating a LLW simulant and investigating the kinetics of methanogenesis in small Wheaton bottles. Treatments were set up to study the effects of waste compaction, the addition of metal to the simulant, the initial aerobic phase, pH and temperature on gas production. A separate experiment was also established to determine whether cellulose in the simulant acted as a biogas precursor. Results are presented from the head space gas analysis and the solid and liquid phase analyses undertaken over a 600 day period. (Author)

  12. Stability of a nanofiltration membrane after contact with a low-level liquid radioactive waste

    Directory of Open Access Journals (Sweden)

    Elizabeth Eugenio de Mello Oliveira

    2013-01-01

    Full Text Available This study investigated the treatment of a liquid radioactive waste containing uranium (235U + 238U using nanofiltration membranes. The membranes were immersed in the waste for 24-5000 h, and their transport properties were evaluated before and after the immersion. Surface of the membranes changed after immersion in the waste. The SW5000 h specimen lost its coating layer of polyvinyl alcohol, and its rejection of sulfate ions and uranium decreased by about 35% and 30%, respectively. After immersion in the waste, the polyamide selective layer of the membranes became less thermally stable than that before immersion.

  13. Vitrification of low level and mixed (radioactive and hazardous) wastes: Lessons learned from high level waste vitrification

    International Nuclear Information System (INIS)

    Borosilicate glasses will be used in the USA and in Europe immobilize radioactive high level liquid wastes (HLLW) for ultimate geologic disposal. Simultaneously, tehnologies are being developed by the US Department of Energy's (DOE) Nuclear Facility sites to immobilize low-level and mixed (radioactive and hazardous) wastes (LLMW) in durable glass formulations for permanent disposal or long-term storage. Vitrification of LLMW achieves large volume reductions (86--97 %) which minimize the associated long-term storage costs. Vitrification of LLMW also ensures that mixed wastes are stabilized to the highest level reasonably possible, e.g. equivalent to HLLW, in order to meet both current and future regulatory waste disposal specifications The tehnologies being developed for vitrification of LLMW rely heavily on the technologies developed for HLLW and the lessons learned about process and product control

  14. Vitrification of low level and mixed (radioactive and hazardous) wastes: Lessons learned from high level waste vitrification

    Energy Technology Data Exchange (ETDEWEB)

    Jantzen, C.M.

    1994-07-01

    Borosilicate glasses will be used in the USA and in Europe immobilize radioactive high level liquid wastes (HLLW) for ultimate geologic disposal. Simultaneously, tehnologies are being developed by the US Department of Energy`s (DOE) Nuclear Facility sites to immobilize low-level and mixed (radioactive and hazardous) wastes (LLMW) in durable glass formulations for permanent disposal or long-term storage. Vitrification of LLMW achieves large volume reductions (86--97 %) which minimize the associated long-term storage costs. Vitrification of LLMW also ensures that mixed wastes are stabilized to the highest level reasonably possible, e.g. equivalent to HLLW, in order to meet both current and future regulatory waste disposal specifications The tehnologies being developed for vitrification of LLMW rely heavily on the technologies developed for HLLW and the lessons learned about process and product control.

  15. Radioactive waste management: a summary of state laws and administration. National Low-Level Radioactive Waste Management Program. Revision 5

    International Nuclear Information System (INIS)

    This updated report covers the administration, the legislature and the laws in the 50 states related to radioactive waste. The report for each state is divided into four sections: Cover Page; Administrative; Legislative; and Applicable Legislation. In general, the information in this report is accurate as of 31 August 1984

  16. A commercial regional incinerator facility for treatment of low-level radioactive waste

    International Nuclear Information System (INIS)

    In 1981, US Ecology, Inc. began studies on the feasibility of constructing and operating a regional radioactive waste incinerator facility. In December, 1982, US Ecology requested turnkey quotations from several vendors for engineering, procurement, and construction of the new facility. After technical and commercial evaluations, a contract was awarded to Associated Technologies, Inc., of Charlotte, North Carolina, in June, 1983. In June, 1984, US Ecology made a public announcement that they were studying two sites in North Carolina for location of the facility. This same month, they submitted their permit application fro a radioactive material license to the North Carolina Department of Human Resources. The facility will accept wastes from power reactors, medical and research institutions and other industrial users, and will incinerate dry solid waste, pathological waste, scintillation fluids, and turbine oils. The incinerator will be a dual chamber controlled air design, rated at 600 lbs/hr, with a venturi scrubber, packed column, HEPA, and charcoal filters for pollution control. The stack will have a continuous monitor

  17. Management of very low level radioactive waste: we need a public debate

    International Nuclear Information System (INIS)

    In France any waste that leaves an area labelled nuclear waste zone by law is considered as a radioactive waste and must be processed and disposed in a dedicated facility but cannot be recycled. This approach is safe but luxurious: a lot of waste that are not contaminated are processed as if they were. IAEA has defined a threshold of 10*10-3 Sievert, below which there is no nuclear risk and the waste can be processed as any other waste, even recycling becomes possible. Countries like Germany allow very low radioactive waste to be dealt with as any other waste, they do not require a specific industrial channel. The French approach is not sustainable in the long run when huge amount of waste will be produced by the dismantling of nuclear power plants. A public debate must be launched as the actual French law is more based on the public acceptance of nuclear activities than on a real management of risks. (A.C.)

  18. Insurance concerns relative to onsite storage of low level radioactive waste

    International Nuclear Information System (INIS)

    ANI and MAELU are voluntary associations made up of approximately 80 stock ampersand 98 mutual insurance companies who insure nuclear risks on a syndicate or pooling basis. The purpose of the pools is to provide for the insurance needs of the nuclear industry in the United States as mandated by the Congress and the NRC. ANI and MAELU provide two types of insurance policies: (1) liability policies - In general, nuclear liability policies provide protection for third party bodily injury and off-site property damage resulting from the nuclear hazard. (2) property policies - The property policies insure against radioactive contamination as the primary peril, but also provide coverage of many conventional property insurance perils. These range from boiler and machinery type losses to fire, extended coverage and vandalism to earthquake and flood coverage

  19. Disposal problems of low-level radioactive wastes and implications for hospitals

    International Nuclear Information System (INIS)

    Medical and pharmaceutical research is in double jeopardy. Not only are they dependent on the radiopharmceutical firms the isotopes they use, but they generate large volumes of wastes which must be shipped off-site at considerable expense. An estimated 283 cubic meters of low-level radwaste is shipped by university and medical school research facilities per year. This contains milliCurie amounts of Tritium and Carbon-14. The medical profession does not advocate speed at the expense of care and safety, but recognizes the value of public education in the ultimate acceptance of a disposal facility wherever one is located. Such a process will take time and needs to be begun soon. Economy is an issue because of new reimbursement mechanisms developed by the federal government and other financial pressures new to the health care industry which will diminish monetary resources for accomplishing health delivery. Indeed, the relative economy of nuclear medicine imaging studies vis a vis those of the CAT scanning NMR may increase dependency upon isotopic methods. Additional disposal costs may cripple this resource. There is some debate as to whether the site should serve only Pennsylvania or should offer disposal to geographically contiguous states. The health care industry does not advocate any particular approach. Some form of interstate cooperation is probably necessary since no large radiopharmaceutical house is based in this state

  20. Low-level radioactive waste management handbook series: corrective measures technology for shallow land burial

    International Nuclear Information System (INIS)

    The purpose of this document is to serve as a handbook to operators of low-level waste burial sites for dealing with conditions which can cause problems in waste isolation. This handbook contains information on planning and applying corrective actions, and is organized in such a way as to assist the operator in associating problems or potential problems with causative conditions. Thus, the operator is encouraged to direct actions at those conditions, rather than the possible temporary expedient of treating symptoms. In Chapter 2 of this handbook, corrective action planning is briefly presented. Chapter 3 discusses the application of corrective measures by addressing, in separate sections, the following conditions which can occur at burial sites: eroding trench cover; permeable trench cover; subsidence of trench; groundwater entering trenches; trench intrusion by deep-rooted plants; and trench intrusion by burrowing animals. In each of these sections, a condition is introduced and related to burial-site problems. It is followed by a discussion of alternative methods for correcting the condition. This discussion includes descriptive information, application considerations for these alternatives, a listing of potential advantages and disadvantages, presentation of generalized cost information, and in conclusion, a statement of recommendations regarding application of corrective action technologies. 66 references, 21 figures, 24 tables

  1. Documentation of currently operating low-level radioactive waste treatment systems: Shredder/compactor report

    International Nuclear Information System (INIS)

    The report documents a volume reduction waste treatment system for dry active waste, a shredder/compactor, and includes specifics on system selection, system descriptions, and detailed system performance data from three operational nuclear power plants. Data gathered from the plants have shown the ability to increase the density (thereby reducing the volume) of dry active waste to /approximately/50 pounds per cubic foot when using shredder/compactors and/approximately/80 to 100 pounds per cubic foot for shredder/high pressure compactors depending on reactor type and plant specific waste characteristics. An economic evaluation of various alternative volume reduction systems for dry active waste is also presented. The report presents a method on calculating the associated costs and paybacks achieved using various volume reduction alternatives. A 10 year cost (operating expenses and capital outlay for equipment) for a shredder/high pressure compactor is 1.85 million dollars for a BWR as compared to /approximately/3 million for a conventional drum compactor. The resulting payback for the shredder/compactor is as low as 1.7 years. The report provides generators of low level waste additional information to understand the nuances of shredder/compactor systems to select a system which best suits their individual needs. 4 refs., 6 figs., 10 tabs

  2. Segregation practices in the management of low-level radioactive wastes

    International Nuclear Information System (INIS)

    A scoping study has been undertaken to determine the state-of-the-art of waste segregation technology as applied to the management of low-level waste (LLW). Present-day waste segregation practices were surveyed through a review of the recent literature and by means of personal interviews with personnel at selected facilities. Among the nuclear establishments surveyed were Department of Energy (DOE) laboratories and plants, nuclear fuel cycle plants, public and private laboratories, institutions, industrial plants, and DOE and commercially operated shallow land burial sites. These survey data were used to analyze the relationship between waste segregation practices and waste treatment/disposal processes, to assess the developmental needs for improved segregation technology, and to evaluate the costs and benefits associated with the implementation of waste segregation controls. For improved processing and disposal of LLW, it is recommended that waste segregation be practiced wherever it is technically feasible and cost-effective to do so. It is noted that LLW management practices are now undergoing rapid change such that the technology and requirements for waste segregation in the near future may differ significantly from those of the present day

  3. Melting of low-level radioactive non-ferrous metal for release

    International Nuclear Information System (INIS)

    Siempelkamp Nukleartechnik GmbH has gained lots of experience from melting ferrous metals for recycling in the nuclear cycle as well as for release to general reuse. Due to the fact that the world market prices for non-ferrous metals like copper, aluminium or lead raised up in the past and will remain on a high level, recycling of low-level contaminated or activated metallic residues from nuclear decommissioning becomes more important. Based on the established technology for melting of ferrous metals in a medium frequency induction furnace, different melt treatment procedures for each kind of non-ferrous metals were developed and successfully commercially converted. Beside different procedures also different melting techniques such as crucibles, gas burners, ladles etc. are used. Approximately 340 Mg of aluminium, a large part of it with a uranium contamination, have been molten successfully and have met the release criteria of the German Radiation Protection Ordinance. The experience in copper and brass melting is based on a total mass of 200 Mg. Lead melting in a special ladle by using a gas heater results in a total of 420 Mg which could be released. The main goal of melting of non-ferrous metals is release for industrial reuse after treatment. Especially for lead, a cooperation with a German lead manufacturer also for recycling of non releasable lead is being planned. (authors)

  4. Conceptual costing study for the long-term management of the Port Hope area low-level radioactive wastes

    International Nuclear Information System (INIS)

    Comparative conceptual cost estimates for several possible options for the long-term management of the Port Hope area low-level radioactive wastes have been developed. Five potentially applicable concepts were considered in the study: shallow land burial, using either unlined trenches, lined trenches or concrete canisters; engineered storage mounds; above-ground concrete vaults; below-ground concrete vaults; and intermediate-depth caverns using either open stopes or shrinkage mining. The objective was to develop comparative estimates. The differences in costs between concepts reflect the differences in handling methodology or costs of additional engineered barriers around the stored waste. An in situ waste volume of 805 000 m3, relatively favorable site conditions, a four-year disposal schedule and a consistent costing basis were assumed for each concept. Limited effort was made to optimize specific facility designs or disposal operations. The projected disposal costs vary from $68/m3 of waste for shallow land burial in unlined trenches, to $312/m3 of waste disposal in concrete canisters in trenches. The results of this study are reasonably consistent with previous estimates prepared for the low-level Radioactive Waste Management Office

  5. Developing a low-level radioactive waste disposal facility in Connecticut: Update on progress and new directions

    Energy Technology Data Exchange (ETDEWEB)

    Gingerich, R.E. [Connecticut Hazardous Waste Management Service, Hartford, CT (United States)

    1993-03-01

    Connecticut is a member of the Northeast Interstate Low-Level Radioactive Waste Management Compact (Northeast LLRW Compact). The other member of the Northeast LLRW Compact is New Jersey. The Northeast Interstate Low-Level Radioactive Waste Commission (Northeast Compact Commission), the Northeast LLRW Compact`s governing body, has designated both Connecticut and New Jersey as host states for disposal facilities. The Northeast Compact Commission has recommended that, for purposes of planning for each state`s facility, the siting agency for the state should use projected volumes and characteristics of the LLW generated in its own state. In 1987 Connecticut enacted legislation that assigns major responsibilities for developing a LLW disposal facility in Connecticut to the Connecticut Hazardous Waste Management Service (CHWMS). The CHWMS is required to: prepare and revise, as necessary, a LLW Management Plan for the state; select a site for a LLW disposal facility; select a disposal technology to be used at the site; select a firm to obtain the necessary approvals for the facility and to develop and operate it; and serve as the custodial agency for the facility. This paper discusses progress in developing a facility.

  6. The social and special effects of siting a low-level radioactive waste disposal facility in rural Texas

    International Nuclear Information System (INIS)

    As part of its assessment of the impacts of a low-level radioactive waste disposal facility in Hudspeth County, the Texas Low-Level Radioactive Waste Disposal Authority (TLLRWDA) sponsored an independent study of the social and special impacts of the facility. These impacts include ''standard'' social impacts (such as impacts on social structures and attitudes, values and perceptions and ''special'' social impacts (such as fear, anxiety, concerns related to equity, the health of future generations, etc.). This paper reports the results of this study. Personal interviews with 71 community leaders and 96 randomly selected county residents were conducted during the summer of 1986. The results suggest that the major concern relates to the contamination of ground water, but that suspicion about the equity of the siting process and about the safe management of wastes is extensive, even among the most knowledgeable respondents. Mitigation concerns center on health and safety issues for residents and on potential forms of mitigation for governmental jurisdictions for leaders. Responses were similar for leaders and residents and for persons in different parts of the county

  7. Alternative methods for dispoal of low-level radioactive wastes. Task 1. Description of methods and assessment of criteria

    International Nuclear Information System (INIS)

    The study reported herein contains the results of Task 1 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 the Nuclear Regulatory Commission (NRC) and the Agreement States. The alternative methods considered are belowground vaults, aboveground vaults, earth mounded concrete bunkers, mined cavities, and augered holes. Each of these alternatives is either being used by other countries for low-level radioactive waste (LLW) disposal or is being considered by other countries or US agencies. In this report the performance requirements are listed, each alternative is described, the experience gained with its use is discussed, and the performance capabilities of each method are addressed. Next, the existing 10 CFR Part 61 Subpart D criteria with respect to paragraphs 61.50 through 61.53, pertaining to site suitability, design, operations and closure, and monitoring are assessed for applicability to evaluation of each alternative. Preliminary conclusions and recommendations are offered on each method's suitability as an LLW disposal alternative, the applicability of the criteria, and the need for supplemental or modified criteria

  8. High-temperature vitrification of low-level radioactive and hazardous wastes

    Energy Technology Data Exchange (ETDEWEB)

    Schumacher, R.F.; Kielpinski, A.L.; Bickford, D.F.; Cicero, C.A.; Applewhite-Ramsey, A.; Spatz, T.L.; Marra, J.C.

    1995-12-01

    The US Department of Energy (DOE) weapons complex has numerous radioactive waste streams which cannot be easily treated with joule-heated vitrification systems. However, it appears these streams could be treated With certain robust, high-temperature, melter technologies. These technologies are based on the use of plasma torch, graphite arc, and induction heating sources. The Savannah River Technology Center (SRTC), with financial support from the Department of Energy, Office of Technology Development (OTD) and in conjunction with the sites within the DOE weapons complex, has been investigating high-temperature vitrification technologies for several years. This program has been a cooperative effort between a number of nearby Universities, specific sites within the DOE complex, commercial equipment suppliers and the All-Russian Research Institute of Chemical Technology. These robust vitrification systems appear to have advantages for the waste streams containing inorganic materials in combination with significant quantities of metals, organics, salts, or high temperature materials. Several high-temperature technologies were selected and will be evaluated and employed to develop supporting technology. A general overview of the SRTC ``High-Temperature Program`` will be provided.

  9. Radiological survey of the low-level radioactive waste burial site at the Palos Forest Preserve, Illinois

    International Nuclear Information System (INIS)

    Two landfill sites containing low-level radioactive waste material, Site A and Plot M, are located 14 miles southwest of Chicago, Illinois in the Palos Forest Preserve. Site A is the former location of the Argonne National Laboratory. Buried at Site A in 1956 were the dismantled reactor shells, building walls, and cooling towers from three of the world's first nuclear reactors. Plot M was used from 1943 to 1949 for burial of low-level radioactive wastes derived from Site A operations and from the University of Chicago Metallurgical Laboratory. Tritiated water was detected in 1973 in some of the Forest Preserve picnic wells located 500 to 1000 yards north of Plot M. An extensive surveillance program was initiated in 1976 to: (1) study the elevated tritium content of some picnic wells and its observed seasonal fluctuations, (2) establish if other radionuclides buried in Plot M or remaining at Site A have migrated, (3) establish the rate of groundwater movement in the glacial till and underlying dolomite aquifer, (4) determine the tritium content of the till and aquifer, and (5) predict future tritium levels in the well water. Several test wells were installed in the soil and dolomite bedrock to monitor radioactivity in groundwater, measure water levels, and provide other geohydrological information. Tritium has migrated from the Plot M burial trenches into the surrounding drift. The tritium plume, the contaminated zone in the drift in which tritium concentrations exceed 10 nanocuries per liter of water (nCi/L), has migrated at least 165 feet horizontally northward and 130 feet vertically downward to the bedrock surface. Small amounts of other radionuclides - uranium, plutonium, and strontium-90 - have been found in boreholes beneath the concrete cap covering Plot M, but not in the subsoil outside of the Plot. The radionuclide concentrations found to date are too low to result in any measureable radiation exposure to the public

  10. The impact of low level radioactive waste on humans and environment the next 100 thousands years

    Energy Technology Data Exchange (ETDEWEB)

    Andersson, E.; Saetre, P.; Lindborg, T.; Norden, S.; Kautsky, U. [Svensk Kaernbraenslehantering AB - SKB (Sweden); Loefgren, A. [Ecoanalytica, Stockholm (Sweden)

    2014-07-01

    A safety assessment for the extension of the low level repository of operational waste (SFR) has been performed (SR-PSU). The repository (both existing and planned extension) is situated c 60 - 120 m below the surface in archaean granitoid rock. SR-PSU evaluates the risk to humans and the environment for the next 100 000 years. During this time period considerable changes are expected in the surface environment due climate change and its effects on shore line displacement, terrestrialisation of lakes and expansion of forest and agricultural land. In this paper specific approaches and results for the surface ecosystems (i.e. biosphere) are presented. The transport and accumulation of radionuclides in marine, lake, and terrestrial ecosystems are modelled and expose of future human populations during present conditions, greenhouse warming, and peri-glacial climate conditions are estimated taking into account different habits and diets of future humans. A new radionuclide transport model was developed to improve the representation of C-14 in the ecosystem modelling. In SR-PSU it is shown that the primary release from the repository via the geosphere to the biosphere is focused to a small area that will be a mire in about 1000 year. The radionuclides can thereafter be transported to downstream lakes and sea ecosystems. The aquatic systems can be utilised for fish and water whereas the mire can either be utilised directly by e.g. collecting, mushroom berries, hay, or hunting, or the mire can be transformed to a small agricultural area and utilised for crops. Important dose contributing radionuclides from SFR are Cl-36, Mo-93, C-14, Ni-59 and I-129 and in some of the scenarios the dose is close to the regulatory limit of 14 μSv/y (i.e. the risk 10{sup -6}). For Non-human biota (NHB) doses are estimated with a novel implementation of the ERICA tool in Ecolego. Generally the same radionuclides contributes to dose to NHB (reference organisms and site -specific organisms) as

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

    Science.gov (United States)

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

    1976-01-01

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

  12. A DEVICE TO MEASURE LOW LEVELS OF RADIOACTIVE CONTAMINANTS IN ULTRA-CLEAN MATERIALS

    International Nuclear Information System (INIS)

    The purpose of this research was to develop a radiation detection device so sensitive that a decay rate of only one atom per 11.57 days per kilogram of material could be detected. Such a detector is needed for screening materials that will be used in exotic high energy physics experiments currently being planned for the near future. The research was performed deep underground at the Underground Mine State Park in Soudan, Minnesota. The overburden there is ∼1800 meters water equivalent. The reason for performing the research at such depth was to vastly reduce the effects of cosmic radiation. The flux of muons and fast neutrons is about 100,000 times lower than at the surface. A small clean room quality lab building was constructed so that work could be performed in such a manner that radioactive contamination could be kept at a minimum. Glove boxes filled with dry nitrogen gas were used to further reduce contamination from dirt and also help reduce the concentration of the radioactive gas 222Ra and daughter radionuclides which are normally present in air. A massive lead shield (about 20 tons) was constructed in such a manner that an eight inch cube of space in the center was available for the sample and detector. The innermost 4 inch thick lead walls were made of ∼460 year old lead previously used in double beta decay experiments and known to be virtually free of 210Pb. A one and one half inch thick shell of active plastic scintillator was imbedded in the center of the 16 inch thick lead walls, ceiling, and floor of the shield and is used to help reduce activity due to the few muons and fast neutrons seen at this depth. The thick lead shielding was necessary to shield the detector from gamma rays emitted by radionuclides in the rock walls of the mine. A sealable chamber was constructed and located on top of the shield that included a device for raising and lowering the detector and samples into and out of the center chamber of the shield. A plastic scintillator

  13. Minimization program of low-level radioactive waste at nuclear power plants in Taiwan

    International Nuclear Information System (INIS)

    This paper reviews the strategy and source/volume reduction practices of the LLRW minimization program implemented in Taiwan over the past decades. The LLRW minimization program in Taiwan includes LLRW minimization regulation/strategy, source reduction and volume reduction. The Radioactive Waste Management Policy was promulgated by the Executive Yuan on September 16, 1988 and revised on September 2, 1997. In accordance with the policy, radwaste producers shall endeavor to minimize the amounts and volumes of radwaste productions. Several activities of source reduction and volume reduction have already done, such as adapted equipment change to improve the liquid filter performance in radwaste treatment system, good housekeeping and administration control in radiation control area to reduce the dry radwaste generation, a high efficiency solidification technology (HEST) was developed by the Institute of the Nuclear Energy Research (INER) and successfully implemented at the MSNPP, The Volume Reduction Center (VRC) located at the KSNPP site was put in operation. As a result of persistent efforts over the past two decades, the annual solidified radwaste generated has been reduced from a high level at 12,258 drums per year in 1983 to less than 5,000 drums in 1992 and further down to 259 drums in 2007. The amount of annual solidified radwaste generated currently has been significantly reduced to 2% of the peak. In addition, the annual dry radwaste generated has been reduced from a high level at 7,571 drums per year in 1990 to less than 2,125 drums in 2007. The amount of annual dry radwaste generated also has significantly reduced to 28% of the peak. (author)

  14. Remediation of the low-level radioactive waste tailing pond in Kowary

    International Nuclear Information System (INIS)

    The town of Kowary was the centre of uranium mining activities in Poland. The headquarters of the uranium mining company ZPR-1 (Zaklady Przemyslowe R-1) were located there, as it was the only uranium processing plant in Poland. Mining in Uranium in Poland ceased in 1963, but processing of low-grade dumps was continued in Kowary until 1972. As a result of these processing activities, a significant volume of wastes was produced and the tailings pond in Kowary was constructed to accommodate these wastes. The tailings pond covers an area of 1,3 ha. It is a hydrotechnical construction closed on three sides by a dam, which has been modified a number of times over the years. It is now 300 m long (the sum of the three sides)m with a maximum height of 12 m, and is at the limits of the geotechnical stability. As a result of the uranium processing activities, the tailings pond was filled with about 2,5 x 105 t of disposed fine-grained gneisses and schists containing about 4,5 t of uranium and about 440 GBq of radium (from processing of uranium ores). A prompt remedial action in this case is particularly necessary because the tailings pond is located in a steep mountainous valley where the local climate involves rapid summer rains with heavy erosion. The nearest buildings in the town of Kowary are located literally at the foot of the 12 m high dam and private gardens extend onto the dam slope. The urgency has recently been demonstrated during the flood of summer 1997 when the base of the dam eroded. In the early seventies, Wroclaw University of Technology (WUT) received, by a governmental decision, ownership of both the area and the facilities of the former uranium mining company ZPR-1. Subsequently, the company Hydromet, Ltd., owned by WUT, has continued to use the existing chemical plant for the various experimental processes of rare (radioactive) metals, chemical production and galvanic processes. As a result, 30 t of mixed heavy metals and 300 t of the remnants from the

  15. Remediation of the low-level radioactive waste tailing pond at Kowary, Poland

    International Nuclear Information System (INIS)

    The last remaining uranium mining tailing pond in Poland, situated at Kowary, was the subject of the Kowary Tailing Pond Remediation Programme financed by Polish public bodies (70%) and by the European Commission (30%) within the framework of its programme of co-operation on radioactive waste issues with candidate countries. The EC-part of the project comprised investigations of the site, project management duties and large-scale civil works following the initial remediation planning performed by the Wroclaw University of Technology (WUT) in 1998-2000. The EC-part was contracted to G.E.O.S. Freiberg Ingenieurgesellschaft mbH following an Open Call for Tender launched by the European Commission in 1999. The following general tasks were performed in close co-operation with WUT, with the construction works subcontracted to local companies, as proposed in the Terms of Reference (TOR) of the EC-part: review of General Remediation Plan (GRP), technical design of the pond cover, construction work: internal drainage system, pond cover and site reclamation. From the information in the TOR, the following aims of remediation were defined: minimise the detrimental impact of the tailing pond on the environment, provide long-term stability of the slopes surrounding the pond, ensure the remediated site is in harmony with the surrounding natural scenery. Based on the experience gathered in similar projects, which had been running under PHARE-MCE or which belonged to the WISMUT-remediation programme in Germany, cost efficient remediation solutions were designed in close co-operation with all involved parties. They were delineated in the detailed planning documents approved in the overall remediation programme managed by WUT. The planned remediation works were prepared and performed successfully according to Polish law and in agreement with the competent local authorities. The aims of remediation were met. However, some additional tasks have been recommended in zones adjacent to the

  16. In-situ grouting of the low-level radioactive waste disposal silos at ORNL's Solid Waste Storage Area Six

    International Nuclear Information System (INIS)

    At Oak Ridge National Laboratory (ORNL), one method of solid low-level radioactive waste disposal has been disposed of in below-grade cylindrical concrete silos. Located in Solid Waste Storage Area 6 (SWSA 6), each silo measures 8 ft in diameter and 20 ft deep. Present day operations involve loading the silos with low-level radioactive waste and grouting the remaining void space with a particulate grout of low viscosity. Initial operations involving the disposal of wastes into the below-grade silos did not include the grouting process. Grouting was stated as a standard practice (in late 1988) after discovering that ∼75% of the silos accumulated water in the bottom of the silos in the ∼2 years after capping. Silo water (leachate) contained a wide range of types and concentrations of radionuclides. The migration of contaminated leachate out of the silo into adjoining soil and groundwater was considered to be a serious environmental concern. This report describes how a specially designed particulate-base grout was used to grout 54 silos previously filled with low-level radioactive waste. Grouting involved three steps: (1) silo preparation, (2) formulation and preparation of the grout mixture, and (3) injection of the grout into the silos. Thirty-five of the 54 silos grouted were equipped with a 3-in.-diam Polyvinyl Chloride (PVC) pipe used to monitor water levels in the silos. A method for rupturing the bottom section of these PVC wells was developed so that grout could be pumped to the bottom of those silos. Holes (2-in. diam) were drilled through the ∼18 in. thick concrete to fill the remaining 19 wells without the PVC monitoring wells. The formulation of grout injected into the silos was based on a Portland Type I cement, flyash, sand, and silica fume admixture. Compressive strength of grout delivered to SWSA6 during grouting operations averaged 1,808 lb/in2 with a bulk density of 3,549 lb/yd3

  17. Study on the evaluation methods to determine the radioactivity concentration in low-level radioactive wastes generated from JPDR facilities. Part 2

    International Nuclear Information System (INIS)

    It is necessary to establish practical evaluation methods to determine radioactivity concentrations of the important nuclides for safety assessment on disposal of radioactive wastes in order to dispose of low-level radioactive wastes generated from various nuclear facilities in JAEA. In this report, it has been studied that the practical evaluation methods such as the scaling factor method or the mean activity concentration method are applied for the important nuclides (H-3, C-14, Cl-36, Ni-59, Co-60, Ni-63, Sr-90, Mo-93, Nb-94, Tc-99, Ag-108m, Cs-137, Eu-152, Eu-154, Ho-166m, α nuclides) of radioactive wastes generated from JPDR facilities. As a result, it has been found that the appropriate methods to determine radioactivity concentrations such as the scaling factor method (Ni-63, Nb-94), the mean activity concentration method (H-3, C-14, Cl-36, Sr-90, Mo-93, Tc-99, Eu-152, Eu-154, Ho-166m, α nuclides) and the theoretical method (Ni-59) can be applied and Co-60, Ag-108m and Cs-137 will be evaluated by gamma measurements from outside of the waste package. (author)

  18. Laboratory scale vitrification of low-level radioactive nitrate salts and soils from the Idaho National Engineering Laboratory

    International Nuclear Information System (INIS)

    INEL has radiologically contaminated nitrate salt and soil waste stored above and below ground in Pad A and the Acid Pit at the Radioactive Waste Management Complex. Pad A contain uranium and transuranic contaminated potassium and sodium nitrate salts generated from dewatered waste solutions at the Rocky Flats Plant. The Acid Pit was used to dispose of liquids containing waste mineral acids, uranium, nitrate, chlorinated solvents, and some mercury. Ex situ vitrification is a high temperature destruction of nitrates and organics and immobilizes hazardous and radioactive metals. Laboratory scale melting of actual radionuclides containing INEL Pad A nitrate salts and Acid Pit soils was performed. The salt/soil/additive ratios were varied to determine the range of glass compositions (resulted from melting different wastes); maximize mass and volume reduction, durability, and immobilization of hazardous and radioactive metals; and minimize viscosity and offgas generation for wastes prevalent at INEL and other DOE sites. Some mixtures were spiked with additional hazardous and radioactive metals. Representative glasses were leach tested and showed none. Samples spiked with transuranic showed low nuclide leaching. Wasteforms were two to three times bulk densities of the salt and soil. Thermally co-processing soils and salts is an effective remediation method for destroying nitrate salts while stabilizing the radiological and hazardous metals they contain. The measured durability of these low-level waste glasses approached those of high-level waste glasses. Lab scale vitrification of actual INEL contaminated salts and soils was performed at General Atomics Laboratory as part of the INEL Waste Technology Development and Environmental Restoration within the Buried Waste Integrated Demonstration Program

  19. Standard Review Plan for the review of a license application for a low-level radioactive waste disposal facility

    International Nuclear Information System (INIS)

    The Standard Review Plan (SRP) (NUREG-1200) provides guidance to staff reviewers in the Office of Nuclear Material Safety and Safeguards who perform safety reviews of applications to construct and operate low-level radioactive waste disposal facilities. The SRP ensures the quality and uniformity of the staff reviews and presents a well-defined base from which to evaluate proposed changes in the scope and requirements of the staff reviews. The SRP makes information about the regulatory licensing process widely available and serves to improve the understanding of the staff's review process by interested members of the public and the industry. Each individual SRP addresses the responsibilities of persons performing the review, the matters that are reviewed, the Commission's regulations and acceptance criteria necessary for the review, how the review is accomplished, the conclusions that are appropriate, and the implementation requirements

  20. Low-level radioactive waste from commercial nuclear reactors. Volume 2. Treatment, storage, disposal, and transportation technologies and constraints

    International Nuclear Information System (INIS)

    The overall task of this program was to provide an assessment of currently available technology for treating commercial low-level radioactive waste (LLRW), to initiate development of a methodology for choosing one technology for a given application, and to identify research needed to improve current treatment techniques and decision methodology. The resulting report is issued in four volumes. Volume 2 discusses the definition, forms, and sources of LLRW; regulatory constraints affecting treatment, storage, transportation, and disposal; current technologies used for treatment, packaging, storage, transportation, and disposal; and the development of a matrix relating treatment technology to the LLRW stream as an aid for choosing methods for treating the waste. Detailed discussions are presented for most LLRW treatment methods, such as aqueous processes (e.g., filtration, ion exchange); dewatering (e.g., evaporation, centrifugation); sorting/segregation; mechanical treatment (e.g., shredding, baling, compaction); thermal processes (e.g., incineration, vitrification); solidification (e.g., cement, asphalt); and biological treatment

  1. Evaluation of uranium and arsenic retention by soil from a low level radioactive waste management site using sequential extraction

    Energy Technology Data Exchange (ETDEWEB)

    Evans, G.J.; Dhoum, R.T. [Department of Chemical Engineering and Applied Chemistry, University of Toronto, 200 College St. Toronto (Canada)

    1998-06-01

    The European Communities Bureau of Reference (BCR) and Chunguo sequential extraction procedures were employed to evaluate the retention of U and As by a soil contaminated with low level radioactive waste. Modifications were made to both procedures to optimize the measurement of soil and extractant samples using epithermal neutron activation analysis. Based on the BCR procedure, approximately 20% of the U appeared to be bound to the carbonate fraction, 10% to the mineral oxide fraction and 20% to the organic fraction. In the case of As, the majority was strongly bound in the residue fraction. The results obtained with the Chunguo procedure supported these conclusions to some extent, in that the majority of the U and As was found to be strongly bound to thesoil in a manner consistent with its presence in the residue fraction. (Copyright (c) 1998 Elsevier Science B.V., Amsterdam. All rights reserved.)

  2. Environmental monitoring report for commercial low-level radioactive waste disposal sites (1960`s through 1990`s)

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-11-01

    During the time period covered in this report (1960`s through early 1990`s), six commercial low-level radioactive waste (LLRW) disposal facilities have been operated in the US. This report provides environmental monitoring data collected at each site. The report summarizes: (1) each site`s general design, (2) each site`s inventory, (3) the environmental monitoring program for each site and the data obtained as the program has evolved, and (4) what the program has indicated about releases to off-site areas, if any, including a statement of the actual health and safety significance of any release. A summary with conclusions is provided at the end of each site`s chapter. The six commercial LLRW disposal sites discussed are located near: Sheffield, Illinois; Maxey Flats, Kentucky; Beatty, Nevada; West Valley, New York; Barnwell, South Carolina; Richland, Washington.

  3. Evaluation of uranium and arsenic retention by soil from a low level radioactive waste management site using sequential extraction

    International Nuclear Information System (INIS)

    The European Communities Bureau of Reference (BCR) and Chunguo sequential extraction procedures were employed to evaluate the retention of U and As by a soil contaminated with low level radioactive waste. Modifications were made to both procedures to optimize the measurement of soil and extractant samples using epithermal neutron activation analysis. Based on the BCR procedure, approximately 20% of the U appeared to be bound to the carbonate fraction, 10% to the mineral oxide fraction and 20% to the organic fraction. In the case of As, the majority was strongly bound in the residue fraction. The results obtained with the Chunguo procedure supported these conclusions to some extent, in that the majority of the U and As was found to be strongly bound to the soil in a manner consistent with its presence in the residue fraction. (Copyright (c) 1998 Elsevier Science B.V., Amsterdam. All rights reserved.)

  4. Evaluation of Department of Energy-Held Potential Greater-Than-Class C Low-Level Radioactive Waste. Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1994-09-01

    A number of commercial facilities have generated potential greater-than-Class C low-level radioactive waste (GTCC LLW), and, through contractual arrangements with the US Department of Energy (DOE) or for health and safety reasons, DOE is storing the waste. This report presents the results of an assessment conducted by the GTCC LLW Management Program to consider specific circumstances under which DOE accepted the waste, and to determine whether disposal in a facility licensed by the US Nuclear Regulatory Commission, or by DOE in a nonlicensed facility, is appropriate. Input from EG&G Idaho, Inc., and DOE Idaho Operations Office legal departments concerning the disposal requirements of this waste were the basis for the decision process used in this report.

  5. Evaluation of Department of Energy-Held Potential Greater-Than-Class C Low-Level Radioactive Waste. Revision 1

    International Nuclear Information System (INIS)

    A number of commercial facilities have generated potential greater-than-Class C low-level radioactive waste (GTCC LLW), and, through contractual arrangements with the US Department of Energy (DOE) or for health and safety reasons, DOE is storing the waste. This report presents the results of an assessment conducted by the GTCC LLW Management Program to consider specific circumstances under which DOE accepted the waste, and to determine whether disposal in a facility licensed by the US Nuclear Regulatory Commission, or by DOE in a nonlicensed facility, is appropriate. Input from EG ampersand G Idaho, Inc., and DOE Idaho Operations Office legal departments concerning the disposal requirements of this waste were the basis for the decision process used in this report

  6. Very low level radioactive wastes. Must the doctrine evolve? Reflections by the IRSN for a perennial, fair and liable management

    International Nuclear Information System (INIS)

    As large programmes of dismantling of nuclear installations are to be elaborated and implemented during the next decades, it appears the Cires (industrial centre for gathering, warehousing and storage), the single solution for very low level radioactive wastes in France, will be saturated on the short term. Therefore, this report aims at reviewing the present policy of waste management in order to make it more perennial, fairer and more liable. First, it identifies strengths and weaknesses of the present doctrine. It examines the kind of governance necessary to decide how this doctrine should evolve, by taking societal stakes, and debate places and modalities into account. While referring to technological options, it examines the possible orientations for an evolution of management modalities: material valorisation, diversification of storage options, and limitation of waste production

  7. Environmental monitoring report for commercial low-level radioactive waste disposal sites (1960's through 1990's)

    International Nuclear Information System (INIS)

    During the time period covered in this report (1960's through early 1990's), six commercial low-level radioactive waste (LLRW) disposal facilities have been operated in the US. This report provides environmental monitoring data collected at each site. The report summarizes: (1) each site's general design, (2) each site's inventory, (3) the environmental monitoring program for each site and the data obtained as the program has evolved, and (4) what the program has indicated about releases to off-site areas, if any, including a statement of the actual health and safety significance of any release. A summary with conclusions is provided at the end of each site's chapter. The six commercial LLRW disposal sites discussed are located near: Sheffield, Illinois; Maxey Flats, Kentucky; Beatty, Nevada; West Valley, New York; Barnwell, South Carolina; Richland, Washington

  8. Preliminary design of a biological treatment facility for trench water from a low-level radioactive waste disposal area

    International Nuclear Information System (INIS)

    A New York State Energy and Research Development Authority (the Authority) funded treatability study identified biotreatment as the best technology to reduce the hazardous constituent concentrations below discharge criteria. Ion exchange resins were shown to reduce strontium-90 and cesium-137 concentrations of a low-level radioactive waste disposal trench leachate below release limits. Based on the results of this treatability study, the Authority has funded the design of a leachate treatment system. An activated sludge bioreactor and ion exchange resin columns will be components of the treatment train. A discussion of the design and the design criteria for the treatment facility will be provided. Particular emphasis will be placed on the availability of the off-the-shelf equipment and the modifications that will be required. Other issues which will be discussed are: Tritium concentration concerns, secondary waste generation and processing, design codes, site layout and schedule

  9. Low-level radioactive waste from commercial nuclear reactors. Volume 2. Treatment, storage, disposal, and transportation technologies and constraints

    Energy Technology Data Exchange (ETDEWEB)

    Jolley, R.L.; Dole, L.R.; Godbee, H.W.; Kibbey, A.H.; Oyen, L.C.; Robinson, S.M.; Rodgers, B.R.; Tucker, R.F. Jr.

    1986-05-01

    The overall task of this program was to provide an assessment of currently available technology for treating commercial low-level radioactive waste (LLRW), to initiate development of a methodology for choosing one technology for a given application, and to identify research needed to improve current treatment techniques and decision methodology. The resulting report is issued in four volumes. Volume 2 discusses the definition, forms, and sources of LLRW; regulatory constraints affecting treatment, storage, transportation, and disposal; current technologies used for treatment, packaging, storage, transportation, and disposal; and the development of a matrix relating treatment technology to the LLRW stream as an aid for choosing methods for treating the waste. Detailed discussions are presented for most LLRW treatment methods, such as aqueous processes (e.g., filtration, ion exchange); dewatering (e.g., evaporation, centrifugation); sorting/segregation; mechanical treatment (e.g., shredding, baling, compaction); thermal processes (e.g., incineration, vitrification); solidification (e.g., cement, asphalt); and biological treatment.

  10. Hydrogeology, ground-water flow, and tritium movement at low-level radioactive-waste disposal site near Sheffield, Illinois

    Science.gov (United States)

    Garklavs, George; Healy, R.W.

    1986-01-01

    Groundwater flow and tritium movement are described at and near a low-level radioactive waste disposal site near Sheffield, Illinois. Flow in the shallow aquifer is confined to three basins that ultimately drain into a stripmine lake. Most of the flow from the site is through a buried, pebbly sandfilled channel. Remaining flow is toward alluvium of an existing stream. Conceptual flow models for the two largest basins are used to improve definition of flow velocity and direction. Flow velocities range from about 25 to 2,500 ft/yr. Tritium was found in all three basins. The most extensive migration of tritium is coincident with buried channel. Tritium concentrations ranged from detection level to more than 300 nanocuries/L. (USGS)

  11. Siting of a low-level radioactive waste management facility - environmental assessment experiences of the Canadian siting task force

    Energy Technology Data Exchange (ETDEWEB)

    Gorber, D.M.; Story, V.A. [SENES-Consultants Ltd. (Canada)

    1995-12-01

    After public opposition to the plans for a low-level radioactive waste facility at one of two candidate areas at Port Hope, Canada the Environmental Assessment process was postponed, and an independent Siting Process Task Force was set-up to assess the most suitable technologies for LLRW disposal, the areas with the best potential in the province to use these technologies, and the most promising approaches to site selection. The Task Force recommended a five-phased siting process known as the `Co-operative Siting Process`, which was based on the voluntary participation of local communities and a collaborative, joint-planning style of decision making. An independent Siting Task Force was to be established to ensure that the principles of the recommended process was upheld. This siting process is still underway, and problems and successes that have been encountered are summarized in this contribution.

  12. Melting behavior of low-level radioactive miscellaneous solid waste and characteristics of solidified products

    Energy Technology Data Exchange (ETDEWEB)

    Nakashio, Nobuyuki; Isobe, Motoyasu; Wakui, Takuji [Department of Decommissioning and Waste Management, Tokai Research Establishment, Japan Atomic Energy Research Institute, Tokai, Ibaraki (Japan)] (and others)

    2001-02-01

    Melting tests of simulated miscellaneous solid wastes were conducted to clarify melting behavior of wastes and to characterize solidified products. Two heating modes were adopted in the tests: hybrid heating and induction heating modes. In the former, wastes were heated with both an induction furnace and a plasma torch, and in the latter, an electrical-conductive crucible was used with the induction furnace. The solidified products with no void, which may reduce the mechanical strength of them, were obtained by addition of deoxidizer. It was found that slag and metallic layers of the solidified products were almost homogeneous from the results of measurement of chemical composition and specific gravity. It was confirmed that the solidified products possessed compressive strength required for disposal. Chemical composition of solidified products was changed by corrosion of crucible or refractory material. Cobalt and cesium tracers were uniformly distributed in metallic and slag layers, respectively. It was found that the residual fraction of cesium is influenced by the heating mode. (author)

  13. Durability of particulate grouts: For isolation of low-level radioactive wastes

    International Nuclear Information System (INIS)

    Over the years particulate grouts have been used for isolating low-concerns that over time and following exposure to adverse environmental conditions, durability of the grouts may become grossly affected and contamination of groundwater system may result. To address some of these problems, a detailed laboratory study was conducted to characterize the fabric and performance of particulate grouts. Before and after exposure to several wet-dry and freeze-thaw cycles, pore size distribution measurements via mercury intrusion porosimetry, unconfined compressive strength, permeability and pulse velocity tests were performed on the studied grouts. Prediction equations were developed for assessing grout durability. Formulation factors: water/solid ratio; mix composition, and interaction between these were found to have significant statistical effect on both wet-dry and freeze-thaw durability of the studied grouts. Fly ash in excess of 30% by weight of total solids present, was found to lower durability considerably. Addition of 7 grams of fiber to the high fly ash grout mix improved durability. Silica fume caused considerable reduction in pore sizes and initial grain in strength, but appear to lower durability particularly under wet-dry conditions. Latex, showed a potential for use as an additive for formulating durable grout mixes. Statistically based design procedures were developed to aid the waste management practitioner to select a range of formulation factors that will assure a desired magnitude of behavior over a specified service period

  14. Low level radioactive waste disposal in the absence of a disposal site

    International Nuclear Information System (INIS)

    This paper describes a six-step strategy to dispose of the large quantity and diverse waste types produced at Port Hope uranium conversion facility. The strategy provides a logical step-by-step process to first characterize a waste, then identify and access feasible options and select a preferred disposal or recycle route. Regulatory and financial approvals are obtained and, finally, implementation of the preferred route takes place. A total of 29 waste types have been identified at the facility. By employing the waste disposal strategy, some 16 wastes are now disposed of or routinely recycled. This represents about 3000 tons of waste material annually. The waste disposal strategy is currently being applied to another ten of the wastes: oils, non-usable drums, scrap metal, zirconium tetrafluoride (ZrF4), PCB liquids, PCB solids, magnesium fluoride, miscellaneous chemicals, waste solvents and calcium fluoride. The strategy is described for three of these: non-usable drums, scrap metal and ZrF4

  15. Selection Criteria of Sites Suitable for Low- Level Radioactive U-mining and Milling wastes Disposal at Al-Missikat-Al-Aradiya District, Eastern Desert, Egypt

    International Nuclear Information System (INIS)

    Uranium mining and milling tailings are U-depleted but contain 230TH and 226Ra. These low-level radioactive wastes are disposed of in the near surface environment. Hydro geologically, suitable sites for disposal of these wastes should be characterized by:1) deep water-level,2) minimal precipitation,3) minimal exposure to flooding and 4) circular- shaped basins. Al-Missikat-Al-Aradiya District with future potential of U-mining and milling operations, a geomorphologic analysis led to the selection of four sites (sub basins) having the geomorphologic characteristics:1)elongation and circularity ratio≡1, 2) high track drainage density (limited infiltration),3) high stream frequency (deep water-table) and 4) moderate to low bifurcation ratio. These sites are further characterized geologically and structurally

  16. Remote Sensing Analysis of the Sierra Blanca (Faskin Ranch) Low-Level Radioactive Waste Disposal Site, Hudspeth County, Texas

    Energy Technology Data Exchange (ETDEWEB)

    LeMone, D. V.; Dodge, R.; Xie, H.; Langford, R. P.; Keller, G. R.

    2002-02-26

    Remote sensing images provide useful physical information, revealing such features as geological structure, vegetation, drainage patterns, and variations in consolidated and unconsolidated lithologies. That technology has been applied to the failed Sierra Blanca (Faskin Ranch) shallow burial low-level radioactive waste disposal site selected by the Texas Low-Level Radioactive Waste Disposal Authority. It has been re-examined using data from LANDSAT satellite series. The comparison of the earlier LANDSAT V (5/20/86) (30-m resolution) with the later new, higher resolution ETM imagery (10/23/99) LANDSAT VII data (15-m resolution) clearly shows the superiority of the LANDSAT VII data. The search for surficial indications of evidence of fatal flaws at the Sierra Blanca site utilizing was not successful, as it had been in the case of the earlier remote sensing analysis of the failed Fort Hancock site utilizing LANDSAT V data. The authors conclude that the tectonic activity at the Sierra Blanca site is much less recent and active than in the previously studied Fort Hancock site. The Sierra Blanca site failed primarily on the further needed documentation concerning a subsurface fault underneath the site and environmental justice issues. The presence of this fault was not revealed using the newer LANDSAT VII data. Despite this fact, it must be remembered that remote sensing provides baseline documentation for determining future physical and financial remediation responsibilities. On the basis of the two sites examined by LANDSAT remote sensing imaging, it is concluded that it is an essential, cost-effective tool that should be utilized not only in site examination but also in all nuclear-related facilities.

  17. Summary of expenditures of rebates from the low-level radioactive waste surcharge escrow account for calendar year 1995

    International Nuclear Information System (INIS)

    This report is submitted in response to Title 1 of the 1980 Low-Level Radioactive Waste Policy Act, as amended, (the Act). The report summarizes expenditures made by compact regions and unaffiliated states during calendar year 1995 of surcharge rebates from the July 1, 1986, January 1, 1988, and January 1, 1990, milestones, and the January 1, 1993, deadline. Section 5(d)(2)(A) of the Act requires the Department of Energy (DOE) to administer a surcharge escrow account. This account consists of a portion of the surcharge fees paid by generators of low-level radioactive waste in nonsited compact regions (compact regions currently without disposal sites) and nonmember states (states without disposal sites that are not members of compact regions) to the three sited states (states with operating disposal facilities--Nevada, South Carolina, and Washington) for the use of facilities in sited states through the end of 1992. In administering the surcharge escrow account, the Act requires DOE to: (1) Invest the funds in interest-bearing United States Government securities with the highest available yield; (2) Determine eligibility for rebates of the funds by evaluating compact region and state progress toward developing new disposal sites against the milestone requirements set forth in the Act; (3) Disburse the collected rebates and accrued interest to eligible compact regions, states, or generators; (4) Assess compliance of rebate expenditures in accordance with the conditions and limitations prescribed in the Act; and (5) Submit a report annually to Congress summarizing rebate expenditures by state and compact region and assessing the compliance of each such state or compact region with the requirement for expenditure of the rebates as provided in section 5(d)(2)(E) of the Act

  18. NRC`s proposed rulemaking on the documentation and reporting of low-level radioactive waste shipment manifest information

    Energy Technology Data Exchange (ETDEWEB)

    Lahs, W.R.; Haisfield, M.F. [Nuclear Regulatory Commission, Washington, DC (United States)

    1991-12-31

    Since the 1982 promulgation of regulations for the land disposal of low-level radioactive waste (LLW), requirements have been in place to control transfers of LLW intended for disposal at licensed land disposal facilities. These requirements established a manifest tracking system and defined processes to control transfers of LLW intended for disposal at a land disposal facility. Because the regulations did not specify the format for the LLW shipment manifests, it was not unexpected that the two operators of the three currently operating disposal sites should each have developed their own manifest forms. The forms have many similarities and the collected information, in many cases, is identical; however, these manifests incorporate unique operator preferences and also reflect the needs of the Agreement State regulatory authority in the States where the disposal sites are located. Since Agreement State regulations must be compatible with, but need not always be identical to, those of the Nuclear Regulatory Commission (NRC), the possibility of a proliferation of different manifest forms containing variations in collected information could be envisioned. If these manifests were also to serve a shipping paper purpose, effective integration of the Department of Transportations` (DOT) requirements would also have to be addressed. This wide diversity in uses of manifest information by Federal and State regulatory authorities, other State or Compact entities, and disposal site operators, suggested a single consolidated approach to develop a uniform manifest format with a baseline information content and to define recordkeeping requirements. The NRC, in 1989, had embarked on a rulemaking activity to establish a base set of manifest information needs for regulatory purposes. In response to requests from State and Regional Compact organizations who are attempting to design, develop and operate LLW disposal facilities, and with the general support of Agreement State regulatory

  19. Consideration of alternatives regarding shallow land disposal of low-level radioactive waste for a developing country

    International Nuclear Information System (INIS)

    The Turkish Atomic Energy Authority (TAEA) is developing plans for improved control of low-level wastes (LLW) in Turkey. The present generation rate of radioactive waste in Turkey can be compared to the early days of the United States, i.e., waste is principally generated in hospitals, biological research centers, universities, and industry. Because the volume of the waste is small, most institutions dispose of their waste. Storage and incineration are the methods of management for the existing wastes. Recently, a Western European country approached TAEA regarding sending their LLW to Turkey for disposal. This certainly has added another dimension to the LLWD efforts of TAEA. If accepted, much needed technology as well as financial support may be directed to Turkey with the LLW of some of the European nations. With this new dimension, LLWD within Turkey becomes a unique international issue. In this study, the authors discuss application of two screening methodologies to develop estimates of human exposure and health risks from shallow-land burial of low-level wastes in central Turkey

  20. Safety assessment on the human intrusion scenarios of near surface disposal facility for low and very low level radioactive waste

    Energy Technology Data Exchange (ETDEWEB)

    Hong, Sung Wook; Park, Jin Baek [Korea Radioactive Waste Agency, Daejeon (Korea, Republic of); Park, Sang Ho [Chungnam National University, Daejeon (Korea, Republic of)

    2016-03-15

    The second-stage near surface disposal facility for low and very low level radioactive waste's permanent disposal is to be built. During the institutional control period, the inadvertent intrusion of the general public is limited. But after the institutional control period, the access to the general public is not restricted. Therefore human who has purpose of residence and resource exploration can intrude the disposal facility. In this case, radioactive effects to the intruder should be limited within regulatory dose limits. This study conducted the safety assessment of human intrusion on the second-stage surface disposal facility through drilling and post drilling scenario. Results of drilling and post drilling scenario were satisfied with regulatory dose limits. The result showed that post-drilling scenario was more significant than drilling scenario. According to the human intrusion time and behavior after the closure of the facility, dominant radionuclide contributing to the intruder was different. Sensitivity analyses on the parameters about the human behavior were also satisfied with regulatory dose limits. Especially, manual redistribution factor was the most sensitive parameter on exposure dose. A loading plan of spent filter waste and dry active waste was more effective than a loading plan of spent filter waste and other wastes for the radiological point of view. These results can be expected to provide both robustness and defense in depth for the development of safety case further.

  1. Decommissioning of a uranium conversion plant and a low level radioactive waste for a long term disposal - 16071

    International Nuclear Information System (INIS)

    A decommissioning project for a uranium conversion plant was conducted to restore it to a safe environmental condition and minimal low level radioactive wastes which were converted to stable chemical forms for a long term disposal. In the middle of 2004, a decommissioning program for a conversion plant, which was constructed in 1982, and treated about 300 tons of natural uranium until it was shut down in 1992, obtained its approval from the regulatory body. Actual dismantling and decontaminating activities have been performed since July 2004 and will be finished by December 2009. The decommissioning works were mainly divided into two parts: the inside of the building containing the process equipment; the lagoon sludge generated during the plant operation. The decommissioning of the inside of the building was carried out by dismantling the process equipment, which were firstly segmented and decontaminated by polishing and washing with steam and chemicals or melting, and then decontamination for the surfaces inside the building by excavating or grinding the concrete walls. The decontamination goals were below 0.2 Bq/g for the metallic segments and below 0.4 Bq/cm2 for the concrete walls. Decontamination methods were selected according to the degree of contamination and a minimization of the low level radioactive wastes was conducted throughout the decommissioning work. The lagoon sludge waste had two types, one was an various inorganic nitrate salt mixture containing a very low concentration of uranium, about 200∼300 ppm, in Lagoon-II and the other was an inorganic nitrate salt mixture containing a few percent of uranium in Lagoon-I. To treat these sludge wastes a thermal decomposition facility was constructed and operated to produce stable sludge wastes containing uranium oxides which are stable in the air. The final sludge wastes after a thermal treating for the sludge waste of Lagoon-I could be reused. The final residual radioactivity for the inside of the

  2. Using Geographic Information Systems to Determine Site Suitability for a Low-Level Radioactive Waste Storage Facility.

    Science.gov (United States)

    Wilson, Charles A; Matthews, Kennith; Pulsipher, Allan; Wang, Wei-Hsung

    2016-02-01

    Radioactive waste is an inevitable product of using radioactive material in education and research activities, medical applications, energy generation, and weapons production. Low-level radioactive waste (LLW) makes up a majority of the radioactive waste produced in the United States. In 2010, over two million cubic feet of LLW were shipped to disposal sites. Despite efforts from several states and compacts as well as from private industry, the options for proper disposal of LLW remain limited. New methods for quickly identifying potential storage locations could alleviate current challenges and eventually provide additional sites and allow for adequate regional disposal of LLW. Furthermore, these methods need to be designed so that they are easily communicated to the public. A Geographic Information Systems (GIS) based method was developed to determine suitability of potential LLW disposal (or storage) sites. Criteria and other parameters of suitability were based on the Code of Federal Regulation (CFR) requirements as well as supporting literature and reports. The resultant method was used to assess areas suitable for further evaluation as prospective disposal sites in Louisiana. Criteria were derived from the 10 minimum requirements in 10 CFR Part 61.50, the Nuclear Regulatory Commission's Regulatory Guide 0902, and studies at existing disposal sites. A suitability formula was developed permitting the use of weighting factors and normalization of all criteria. Data were compiled into GIS data sets and analyzed on a cell grid of approximately 14,000 cells (covering 181,300 square kilometers) using the suitability formula. Requirements were analyzed for each cell using multiple criteria/sub-criteria as well as surrogates for unavailable datasets. Additional criteria were also added when appropriate. The method designed in this project proved to be sufficient for initial screening tests in determining the most suitable areas for prospective disposal (or storage

  3. Using Geographic Information Systems to Determine Site Suitability for a Low-Level Radioactive Waste Storage Facility.

    Science.gov (United States)

    Wilson, Charles A; Matthews, Kennith; Pulsipher, Allan; Wang, Wei-Hsung

    2016-02-01

    Radioactive waste is an inevitable product of using radioactive material in education and research activities, medical applications, energy generation, and weapons production. Low-level radioactive waste (LLW) makes up a majority of the radioactive waste produced in the United States. In 2010, over two million cubic feet of LLW were shipped to disposal sites. Despite efforts from several states and compacts as well as from private industry, the options for proper disposal of LLW remain limited. New methods for quickly identifying potential storage locations could alleviate current challenges and eventually provide additional sites and allow for adequate regional disposal of LLW. Furthermore, these methods need to be designed so that they are easily communicated to the public. A Geographic Information Systems (GIS) based method was developed to determine suitability of potential LLW disposal (or storage) sites. Criteria and other parameters of suitability were based on the Code of Federal Regulation (CFR) requirements as well as supporting literature and reports. The resultant method was used to assess areas suitable for further evaluation as prospective disposal sites in Louisiana. Criteria were derived from the 10 minimum requirements in 10 CFR Part 61.50, the Nuclear Regulatory Commission's Regulatory Guide 0902, and studies at existing disposal sites. A suitability formula was developed permitting the use of weighting factors and normalization of all criteria. Data were compiled into GIS data sets and analyzed on a cell grid of approximately 14,000 cells (covering 181,300 square kilometers) using the suitability formula. Requirements were analyzed for each cell using multiple criteria/sub-criteria as well as surrogates for unavailable datasets. Additional criteria were also added when appropriate. The method designed in this project proved to be sufficient for initial screening tests in determining the most suitable areas for prospective disposal (or storage

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1986-05-01

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

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

    International Nuclear Information System (INIS)

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

  6. Eleventh annual Department of Energy low-level waste management conference. Volume 3: Waste characterization, waste reduction and minimization, prototype licensing application

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1989-11-01

    Thirteen papers are presented in volume 3. The seven papers on waste characterization discuss sampling, analysis, and certification techniques for low-level radioactive wastes. Three papers discuss US DOE waste minimization policies and regulations, Y-12 Plant`s reduction of chlorinated solvents, and C-14 removal from spent resins. The last three papers discuss the licensing studies for earth-mounded concrete bunkers for LLW disposal. Papers have been processed separately for inclusion on the data base.

  7. Summarization of Safety Assessment on Disposal of Low Level Radioactive Wastes%极低放核废物处置安全评价概述

    Institute of Scientific and Technical Information of China (English)

    谢云

    2011-01-01

    Attention was highly paid on disposal of low level radioactive wastes.The quantitative forecast of low level radioactive nuclear waste needs safety assessment.In this paper,the present status of safety assessment on disposal field for low level radioactive wastes was summarized.The analysis method of scene-consequences was introduced,which is now popular in China.%放射性废物处置受到很高程度的关注和重视;极低放核废物处置系统的定量预测需要对其进行安全评价;本文就极低放处置场的安全评价现状进行了概述,主要介绍了目前我国主要采用的景象后果分析方法。

  8. Low-Level Radioactive Waste Management in the United States: What Have We Wrought? The Richard S. Hodes, M.D. Honor Lecture Award - 12222

    International Nuclear Information System (INIS)

    In 1979, radioactive waste disposal was an important national issue. State governors were closing the gates on the existing low-level radioactive waste disposal sites and the ultimate disposition of spent fuel was undecided. A few years later, the United States Congress thought they had solved both problems by passing the Low-Level Radioactive Waste Policy Act of 1981, which established a network of regional compacts for low-level radioactive waste disposal, and by passing the Nuclear Waste Policy Act of 1982 to set out how a final resting place for high-level waste would be determined. Upon passage of the acts, State, Regional and Federal officials went to work. Here we are some 30 years later with little to show for our combined effort. The envisioned national repository for high-level radioactive waste has not materialized. Efforts to develop the Yucca Mountain high-level radioactive waste disposal facility were abandoned after spending $13 billion on the failed project. Recently, the Blue Ribbon Commission on America's Nuclear Future issued its draft report that correctly concludes the existing policy toward high-level nuclear waste is 'all but completely broken down'. A couple of new low-level waste disposal facilities have opened since 1981, but neither were the result of efforts under the act. What the Act has done is interject a system of interstate compacts with a byzantine interstate import and export system to complicate the handling of low-level radioactive waste, with attendant costs. As this paper is being written in the fourth-quarter of 2011, after 30 years of political and bureaucratic turmoil, a new comprehensive low-level waste disposal facility at Andrews Texas is approaching its initial operating date. The Yucca Mountain project might be completed or it might not. The US Nuclear Regulatory Commission is commencing a review of their 1981 volume reduction policy statement. The Department of Energy after 26 years has yet to figure out how to

  9. Hydrologic evaluation methodology for estimating water movement through the unsaturated zone at commercial low-level radioactive waste disposal sites

    International Nuclear Information System (INIS)

    This report identifies key technical issues related to hydrologic assessment of water flow in the unsaturated zone at low-level radioactive waste (LLW) disposal facilities. In addition, a methodology for incorporating these issues in the performance assessment of proposed LLW disposal facilities is identified and evaluated. The issues discussed fall into four areas: estimating the water balance at a site (i.e., infiltration, runoff, water storage, evapotranspiration, and recharge); analyzing the hydrologic performance of engineered components of a facility; evaluating the application of models to the prediction of facility performance; and estimating the uncertainty in predicted facility performance. To illustrate the application of the methodology, two examples are presented. The first example is of a below ground vault located in a humid environment. The second example looks at a shallow land burial facility located in an arid environment. The examples utilize actual site-specific data and realistic facility designs. The two examples illustrate the issues unique to humid and arid sites as well as the issues common to all LLW sites. Strategies for addressing the analytical difficulties arising in any complex hydrologic evaluation of the unsaturated zone are demonstrated

  10. Set-up and first operation of a plasma oven for treatment of low level radioactive wastes

    Directory of Open Access Journals (Sweden)

    Nachtrodt Frederik

    2014-01-01

    Full Text Available An experimental device for plasma treatment of low and intermediate level radioactive waste was built and tested in several design variations. The laboratory device is designed with the intention to study the general effects and difficulties in a plasma incineration set-up for the further future development of a larger scale pilot plant. The key part of the device consists of a novel microwave plasma torch driven by 200 W electric power, and operating at atmospheric pressure. It is a specific design characteristic of the torch that a high peak temperature can be reached with a low power input compared to other plasma torches. Experiments have been carried out to analyze the effect of the plasma on materials typical for operational low-level wastes. In some preliminary cold tests the behavior of stable volatile species e. g., caesium was investigated by TXRF measurements of material collected from the oven walls and the filtered off-gas. The results help in improving and scaling up the existing design and in understanding the effects for a pilot plant, especially for the off-gas collection and treatment.

  11. Sediments, fauna, and the dispersal of radionuclides at the N.E. Atlantic dumpsite for low-level radioactive waste

    International Nuclear Information System (INIS)

    The seafloor at the NEA dumpsite for low-level radioactive waste has been investigated by geochemical and biological techniques. Evidence of local turbidities and slumping is recorded in the sediment, probably related to the steep local topography. Slumping events could be triggered by dumping operations. The CaCO3 content is the principle variable that accounts for most of the variation in the elemental composition and cation exchange capacity of the sediment. Diagenetic modeling is used to explain the interrelationships between: (1) mineralization of organic material and (2) redox transitions, (3) cation exchange, and (4) carbonate dissolution and recrystallization. These diagenetic processes are discussed in terms of their effects on the redistribution and transport of trace elements and radionuclides within the sediment and between sediment and overlying water. Composition, density, biomass, vertical and horizontal distribution has been studied of benthic meio- as well as macrofauna of the NEA-dumpsite. The processes that have been shown to influence the fate of radionuclides that are released from the waste packages are: transport from bottom water to sediment; transport within the sediment; and transformation of radionuclides within the sediment. 194 refs.; 58 figs.; 40 tabs

  12. Greater-than-Class C low-level radioactive waste shipping package/container identification and requirements study

    International Nuclear Information System (INIS)

    This report identifies a variety of shipping packages (also referred to as casks) and waste containers currently available or being developed that could be used for greater-than-Class C (GTCC) low-level waste (LLW). Since GTCC LLW varies greatly in size, shape, and activity levels, the casks and waste containers that could be used range in size from small, to accommodate a single sealed radiation source, to very large-capacity casks/canisters used to transport or dry-store highly radioactive spent fuel. In some cases, the waste containers may serve directly as shipping packages, while in other cases, the containers would need to be placed in a transport cask. For the purpose of this report, it is assumed that the generator is responsible for transporting the waste to a Department of Energy (DOE) storage, treatment, or disposal facility. Unless DOE establishes specific acceptance criteria, the receiving facility would need the capability to accept any of the casks and waste containers identified in this report. In identifying potential casks and waste containers, no consideration was given to their adequacy relative to handling, storage, treatment, and disposal. Those considerations must be addressed separately as the capabilities of the receiving facility and the handling requirements and operations are better understood

  13. Determination of {sup 93}Zr in medium and low level radioactive wastes from Brazilian nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Oliveira, Thiago C.; Oliveira, Arno H., E-mail: oliveiratco2010@gmail.com, E-mail: heeren@nuclear.ufmg.br [Universidade Federal de Minas Gerais (DEN/UFMG), Belo Horizonte, MG (Brazil). Departamento de Engenharia Nuclear; Kastner, Geraldo F.; Monteiro, Roberto Pellacani G., E-mail: rpgm@cdtn.br, E-mail: gfk@cdtn.br [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil)

    2015-07-01

    The majority of long-lived radionuclides produced in the nuclear power plants can be regarded as difficult-to-measure radionuclides (RDM), hence chemical separation is necessary before the nuclear measurement of them. The zirconium isotope {sup 93}Zr is a long-lived pure β-particle-emitting radionuclide produced from {sup 235}U fission and from neutron activation of the stable isotope {sup 92}Zr and thus occurring as one of the radionuclides found in nuclear reactors. Due to its long half-life, {sup 93}Zr is one of the radionuclides of interest for the performance of assessment studies of waste storage or disposal. Two different methodologies based on extractive resins and LSC and ICP-MS techniques that enables the {sup 93}Zr determination in medium (ILW) and low level (LLW) radioactive wastes samples from Brazilian nuclear power plants has been developed in our laboratory. Analyzing real samples 65% and 75% chemical yields for {sup 93}Zr recovery were achieved for ICP-MS and LSC techniques, respectively. The detection limits were 0.045 μg.L{sup -1} for ICP-MS and 0.05 Bq.L{sup -1} for LSC techniques. (author)

  14. Summary of expenditures of rebates from the low-level radioactive waste surcharge escrow account for calendar year 1990

    International Nuclear Information System (INIS)

    This is the fifth report submitted to Congress under Title 1, section 5(d)(2)(E) of Public Law 99--240, ''The Low-Level Radioactive Waste Policy Amendments Act of 1985'' (the Act). This section of the Act requests the Department of Energy (DOE) to summarize the annual expenditures of funds disbursed from the DOE surcharge escrow account and to assess compliance of these expenditures with the specified limitations. The Act places limitations on the use of these funds and requires the nonsited compact regions and nonmember States to provide DOE with an itemized report of their expenditures on December 31 of each year in which funds are expended. Within 6 months after receiving the individual reports, DOE is to furnish Congress a summary of the reported expenditures and an assessment of compliance with the limitations on the use of these funds specified in the Act. This report fulfills that requirements. DOE disbursed funds totaling $15,006,587.76 to the States and compact regions following the July 1, 1986, January 1, 1988, and January 1, 1990, milestones. Of this amount, $4,328,340.44 was expended during calendar year 1990 and $2,239,205.80 was expended during the prior 4 years. At the end of December 1990, $8,439,041.52 was unexpended. 5 tabs

  15. Calcium sulfoaluminate cement blended with OPC: A potential binder to encapsulate low-level radioactive slurries of complex chemistry

    International Nuclear Information System (INIS)

    Investigations were carried out in order to solidify in cement a low-level radioactive waste of complex chemistry obtained by mixing two process streams, a slurry produced by ultra-filtration and an evaporator concentrate with a salinity of 600 gxL-1. Direct cementation with Portland cement (OPC) was not possible due to a very long setting time of cement resulting from borates and phosphates contained in the waste. According to a classical approach, this difficulty could be solved by pre-treating the waste to reduce adverse cement-waste interactions. A two-stage process was defined, including precipitation of phosphates and sulfates at 60 deg. C by adding calcium and barium hydroxide to the waste stream, and encapsulation with a blend of OPC and calcium aluminate cement (CAC) to convert borates into calcium quadriboroaluminate. The material obtained with a 30% waste loading complied with specifications. However, the pre-treatment step made the process complex and costly. A new alternative was then developed: the direct encapsulation of the waste with a blend of OPC and calcium sulfoaluminate cement (CSA) at room temperature. Setting inhibition was suppressed, which probably resulted from the fact that, when hydrating, CSA cement formed significant amounts of ettringite and calcium monosulfoaluminate hydrate which incorporated borates into their structure. As a consequence, the waste loading could be increased to 56% while keeping acceptable properties at the laboratory scale.

  16. Surveillance and maintenance of the West Valley state licensed low level radioactive waste disposal area 1983-1987

    International Nuclear Information System (INIS)

    The New York State Energy Research and Development Authority is the current custodian of the State-owned, closed, commercial low-level radioactive waste disposal area (SDA) at the Western New York Nuclear Service Center in West Valley, New York. From 1963 to 1975 that facility was operated by Nuclear Fuel Services, Inc. Packaged waste was placed in long trenches excavated in the highly impermeable, silty till soil native to the site, and covered with four to eight feet of excavated soil. Due to the character of the soil and the wet climate, water management problems were experienced from the very early years of operation. Water accumulated in the open, uncompleted trenches and in covered, completed trenches. Water continued to accumulate in several of the original trenches until March 1975 when it crested the original terrain and began to seep through the cover of two trenches. Redesigning and reworking the covers have thus far reduced but not eliminated the problem of water accumulation in the trenches. In its present condition, the closed disposal area will continue to require active and continuous maintenance for the foreseeable future

  17. Radionuclide Concentrations in Soils and Vegetation at Low-Level Radioactive Waste Disposal Area G during the 1997 Growing Season

    Energy Technology Data Exchange (ETDEWEB)

    L. Naranjo, Jr.; P. R. Fresquez; R. J. Wechsler

    1998-08-01

    Soil and overstory and understory vegetation (washed and unwashed) collected at eight locations within and around Area G-a low-level radioactive solid-waste disposal facility at Los Alamos National Laboratory-were analyzed for 3H, 238Pu, 239Pu, 137CS, 234U, 235U, 228AC, Be, 214Bi, 60Co, 40& 54Mn, 22Na, 214Pb and 208Tl. In general, most radionuclide concentrations, with the exception of 3Ef and ~9Pu, in soils and overstory and understory vegetation collected from within and around Area G were within upper (95'%) level background concentrations. Although 3H concentrations in vegetation from most sites were significantly higher than background (>2 pCi mL-l), concentrations decreased markedly in comparison to last year's results. The highest `H concentration in vegetation was detected from a juniper tree that was growing over tritium shaft /+150; it contained 530,000 pCi 3H mL-l. Also, as in the pas~ the transuranic waste pad area contained the highest levels of 239Pu in soils and in understory vegetation as compared to other areas at Area G.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2005-10-01

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

  19. The volume reduction of low level solid radioactive waste using a mobile supercompactor at Winfrith Technology Centre

    International Nuclear Information System (INIS)

    Studies have shown that the most cost effective method presently available to reduce the volume of low level radioactive waste (LLW) sent to Drigg is by high force mechanical compaction. High force compaction or supercompaction is a process by which whole containers of LLW (normally 200 litre drums) are reduced significantly in volume by mechanical compaction in a mould using a force of up to 2000 tonnes. The product is often referred to as a hockepuck . The supercompactor can be either a fixed installation or mounted on two or more trailers so that it can be moved to different sites. The Central Electricity Generating Board (CEGB) and the Winfrith Technology Centre (WTC) agreed to carry out demonstration campaigns at Trawsfyndd and Hinkley Point Nuclear Power Stations and at the WTC during the period August to October 1989. The CEGB placed a contract with Hansa Projekt Anlagentechnik GmbH of Hamburg in the Federal Republic of Germany (FRG) for the use of a commercial high force supercompactor, together with the necessary key staff. The purpose of the demonstration trial was to show that a mobile system is operationally satisfactory whilst also conforming to all the relevant safety requirements, both at the nuclear sites and during transport. A subsidiary aim was to generate technical data in an experimental programme designed to investigate the force-volume relationship. (Author)

  20. Processing of low-level and intermediate-level radioactive wastes from the nuclear power plant Muehleberg at Mol

    International Nuclear Information System (INIS)

    Between October 1986 and April 1987 two contracts were concluded between the nuclear power plant Muehleberg and the German firm Transnuklear GmbH for the processing of low-level and intermediate-level radioactive wastes from Muehleberg in the incineration facility at Mol in Belgium. In the contracts, transport of the wastes to Mol and back was included. According to the contracts the maximum admissible surface dose rate of the containers enclosing the wastes was 3000 mR/h. The actual maximum value of the surface dose rate was 1800 mR/h. On January 8, 1988, Swiss press published a statement to the effect that those wastes having a surface dose rate of more than 200 mR/h cannot be processed at Mol and must be transported back to Switzerland. Three representatives of Muehleberg visited Mol to discuss the conflicting information. The result of their inquiries was that the processing and transport of foreign wastes at Mol are currently suspended due to the irregularities associated with Transnuklear. Neither the safety nor the operation of the Muehleberg facility are jeopardized through the incident

  1. In-situ stabilization of radioactively contaminated low-level solid wastes buried in shallow trenches: an assessment

    International Nuclear Information System (INIS)

    The potential effectiveness of materials for in-situ encapsulation of low-level, radioactively contaminated solid waste buried in shallow trenches is enumerated. Cement, clay materials, and miscellaneous sorbents, aqueous and nonaqueous gelling fluids and their combinations are available to solidify contaminated free water in trenches, to fill open voids, and to minimize radionuclide mobility. The success of the grouting technique will depend on the availability of reliable geohydrologic data and laboratory development of a mix with enhanced sorption capacity for dominant radionuclides present in the trenches. A cement-bentonite-based grout mix with low consistency for pumping, several hours controlled rate of hardening, negligible bleeding, and more than 170 kPa (25 psi) compressive strength are a few of the suggested parameters in laboratory mix development. Cost estimates of a cement-bentonite-based grout mix indicate that effective and durable encapsulation can be accomplished at a reasonable cost (about $113 per cubic meter). However, extensive implementation of the method suggests the need for a field demonstration of the method. 53 references

  2. Simulations of long-term health risk from shallow land burial of low-level radioactive waste

    Energy Technology Data Exchange (ETDEWEB)

    Little, C.A.; Fields, D.E.

    1982-01-01

    PRESTO (Prediction of Radiation Effects from Shallow Trench Operations) is a computer code developed under U.S. Environmental Protection Agency (EPA) funding to evaluate possible health effects from shallow land burial of low-level radioactive wastes. The model is intended to assess radionuclide transport, ensuing exposure, and health impact to a static local population for up to 1000 years following the end of burial operations. Human exposure scenarios that may be considered by model include normal releases (including leaching and operational spillage), human intrusion, and near site farming. Pathways and processes of transit from the trench to an individual or population include:groundwater transport, overland flow, erosion, surface water dilution, resuspension, atmospheric transport, overland flow, erosion, surface water dilution, resuspension, atmospheric transport, deposition, inhalation, and ingestion of contaminated beef, milk, crops, and water. Off-site population and individual doses and cancer risks may be calculated as well as doses and risks to the intruder and farmer. Data have been compiled for three extant shallow land burial sites: Barnwell, South Carolina; Beatty, Nevada; and West Valley, New York. Some simulation results for the Barnwell site are presented. 13 references, 3 figures, 3 tables.

  3. Using a very low level radioactive steel from decommissioning of nuclear installation for the construction of railway structures

    International Nuclear Information System (INIS)

    During the operation, but especially during decommissioning (SW) of operation, there is a large amount of radioactive waste, whose activity only slightly exceeds the limits for unrestricted use, or for the unconditional release into the environment. In particular, metal and concrete debris. Processing, treatment and disposal of such waste would require considerable funds, and also storage space would be quickly filled up. A convenient way to use a large number of low-activity materials seems to be conditional release, which will reuse the materials for a particular purpose. The paper deals with use of a very low level of steel from decommissioning of nuclear installations for construction of the railway bridge. The task of the present paper is to review the impact of conditionally released steel on population and to determine what level of mass activity of the steel meets the limits prescribed by law. For impact assessment of conditionally released steel on population there was selected computing resource VISIPLAN 3D ALARA Planning Tool. (author)

  4. Simulations of long-term health risk from shallow land burial of low-level radioactive waste

    International Nuclear Information System (INIS)

    PRESTO (Prediction of Radiation Effects from Shallow Trench Operations) is a computer code developed under U.S. Environmental Protection Agency (EPA) funding to evaluate possible health effects from shallow land burial of low-level radioactive wastes. The model is intended to assess radionuclide transport, ensuing exposure, and health impact to a static local population for up to 1000 years following the end of burial operations. Human exposure scenarios that may be considered by model include normal releases (including leaching and operational spillage), human intrusion, and near site farming. Pathways and processes of transit from the trench to an individual or population include:groundwater transport, overland flow, erosion, surface water dilution, resuspension, atmospheric transport, overland flow, erosion, surface water dilution, resuspension, atmospheric transport, deposition, inhalation, and ingestion of contaminated beef, milk, crops, and water. Off-site population and individual doses and cancer risks may be calculated as well as doses and risks to the intruder and farmer. Data have been compiled for three extant shallow land burial sites: Barnwell, South Carolina; Beatty, Nevada; and West Valley, New York. Some simulation results for the Barnwell site are presented. 13 references, 3 figures, 3 tables

  5. Experience and related research and development in applying corrective measures at the major low-level radioactive waste disposal sites

    International Nuclear Information System (INIS)

    A review was conducted of experience in responding to problems encountered in shallow land burial of low-level radioactive waste and in research and development related to these problems. The operating histories of eleven major disposal facilities were examined. Based on the review, it was apparent that the most effective corrective measures administered were those developed from an understanding of the site conditions which caused the problems. Accordingly, the information in this document has been organized around the major conditions which have caused problems at existing sites. These include: (1) unstable trench cover, (2) permeable trench cover, (3) subsidence, (4) ground water entering trenches, (5) intrusion by deep-rooted plants, (6) intrusion by burrowing animals, and (7) chemical and physical conditions in trench. Because the burial sites are located in regions that differ in climatologic, geologic, hydrologic, and biologic characteristics, there is variation in the severity of problems among the sites and in the nature of information concerning corrective efforts. Conditions associated with water-related problems have received a great deal of attention. For these, corrective measures have ranged from the creation of diversion systems for reducing the contact of surface water with the trench cover to the installation of seals designed to prevent infiltration from reaching the buried waste. On the other hand, corrective measures for conditions of subsidence or of intrusion by burrowing animals have had limited application and are currently under evaluation or are subjects of research and development activities. 50 references, 20 figures, 10 tables

  6. Summary of expenditures of rebates from the low-level radioactive waste surcharge escrow account for calendar year 1991

    International Nuclear Information System (INIS)

    This is the sixth report submitted to Congress under section 5(d)(2)(E)(ii)(II) of the Low-Level Radioactive Waste Policy Act of 1985 (the Act). This section of the Act directs the Department of Energy (DOE) to summarize the annual expenditures of funds disbursed from the DOE surcharge escrow account and to assess compliance of these expenditures with the limitations specified in the Act. In addition to placing limitations on the use of these funds, the Act also requires the nonsited compact regions and nonmember States to provide DOE with an itemized report of their expenditures on December 31 of each year in which funds are expended. Within 6 months after receiving the individual reports, the Act requires the Secretary to furnish Congress with a summary of the reported expenditures and an assessment of compliance with the specified usage limitations. This report fulfills that requirement. DOE disbursed funds totaling $15,037,778.91 to the States and compact regions following the July 1, 1986, January 1, 1988, and January 1, 1990, milestones specified in the Act. Of this amount, $3,517,020.56 was expended during calendar year 1991 and $6,602,546.24 was expended during the prior 5 years. At the end of December 1991, $4,918,212.11 was unexpended. DOE has reviewed each of the reported expenditures and concluded that all reported expenditures comply with the spending limitations stated in section 5(d)(2)(E)(i) of the Act

  7. Distribution of gases in the unsaturated zone at a low-level radioactive-waste disposal site near Sheffield, Illinois

    Science.gov (United States)

    Striegl, Robert G.

    1988-01-01

    The unsaturated zone is a medium that provides pneumatic communication for the movement of gases from wastes buried in landfills to the atmosphere, biota, and groundwater. Gases in unsaturated glacial and eolian deposits near a waste-disposal trench at the low-level radioactive-waste disposal site near Sheffield, Bureau County, Illinois, were identified, and the spatial and temporal distributions of the partial pressures of those gases were determined for the period January 1984 through January 1986. Methods for the collection and analyses of the gases are described, as are geologic and hydrologic characteristics of the unsaturated zone that affect gas transport. The identified gases, which are of natural and of waste origin, include nitrogen, oxygen, and argon, carbon dioxide, methane, propane, butane, tritiated water vapor, 14carbon dioxide, and 222 radon. Concentrations of methane and 14carbon dioxide originated at the waste, as shown by partial-pressure gradients of the gases; 14carbon dioxide partial pressures exceeded natural background partial pressures by factors greater than 1 million at some locations. Variations in partial pressures of oxygen and carbon dioxide were seasonal among piezometers because of increased root and soil-microbe respiration during summer. Variations in methane and 14carbon dioxide partial pressures were apparently related to discrete releases from waste sources at unpredictable intervals of time. No greater than background partial pressures for tritiated water vapor or 222 radon were measured. (USGS)

  8. Hydrologic evaluation methodology for estimating water movement through the unsaturated zone at commercial low-level radioactive waste disposal sites

    Energy Technology Data Exchange (ETDEWEB)

    Meyer, P.D.; Rockhold, M.L.; Nichols, W.E.; Gee, G.W. [Pacific Northwest Lab., Richland, WA (United States)

    1996-01-01

    This report identifies key technical issues related to hydrologic assessment of water flow in the unsaturated zone at low-level radioactive waste (LLW) disposal facilities. In addition, a methodology for incorporating these issues in the performance assessment of proposed LLW disposal facilities is identified and evaluated. The issues discussed fall into four areas: estimating the water balance at a site (i.e., infiltration, runoff, water storage, evapotranspiration, and recharge); analyzing the hydrologic performance of engineered components of a facility; evaluating the application of models to the prediction of facility performance; and estimating the uncertainty in predicted facility performance. To illustrate the application of the methodology, two examples are presented. The first example is of a below ground vault located in a humid environment. The second example looks at a shallow land burial facility located in an arid environment. The examples utilize actual site-specific data and realistic facility designs. The two examples illustrate the issues unique to humid and arid sites as well as the issues common to all LLW sites. Strategies for addressing the analytical difficulties arising in any complex hydrologic evaluation of the unsaturated zone are demonstrated.

  9. Safety Evaluation Report for the Tennessee Valley Authority's Plan to Decommission its Low-Level Radioactive Waste Burial Site at Muscle Shoals, Alabama

    Energy Technology Data Exchange (ETDEWEB)

    Gant, K.S.; Kettelle, R.H.

    1998-11-01

    From 1966 to 1981, the Tennessee Valley Authority (TVA) operated a burial site, licensed under the former 10 CFR 20.304, for low-level radioactive waste on its Muscle Shoals, Alabama, reservation. TVA submitted a decommissioning plan for the burial site and requested approval for unrestricted use of the site. The Nuclear Regulatory Commission requested Oak Ridge National Laboratory (ORNL) to evaluate this plan to determine if the site meets the radiological requirements for unrestricted use as specified in 10 CFR 20.1402; that is, an average member of the critical group would not receive more than 25 mrem/y from residual radioactivity at the TVA Low-Level Radioactive Waste Burial Site and the radioactivity has been reduced to levels as low as reasonably achievable (ALARA).

  10. Survey of statistical and sampling needs for environmental monitoring of commercial low-level radioactive waste disposal facilities

    International Nuclear Information System (INIS)

    This project was designed to develop guidance for implementing 10 CFR Part 61 and to determine the overall needs for sampling and statistical work in characterizing, surveying, monitoring, and closing commercial low-level waste sites. When cost-effectiveness and statistical reliability are of prime importance, then double sampling, compositing, and stratification (with optimal allocation) are identified as key issues. If the principal concern is avoiding questionable statistical practice, then the applicability of kriging (for assessing spatial pattern), methods for routine monitoring, and use of standard textbook formulae in reporting monitoring results should be reevaluated. Other important issues identified include sampling for estimating model parameters and the use of data from left-censored (less than detectable limits) distributions

  11. Hydrology of the low-level radioactive solid waste burial site and vicinity near Barnwell, South Carolina

    Science.gov (United States)

    Cahill, James M.

    1982-01-01

    Geologic and hydrologic conditions at a burial site for low-level radioactive waste were studied, and migration of leachates from the buried waste into surrounding unconsolidated sediments were evaluated. The burial site and vicinity are underlain by a sequence of unconsolidated sediments of Late Cretaceous, Tertiary, and Quaternary age. These sediments are deposited over a graben which has been filled with sedimentary rocks of Triassic age. Hydraulic properties of the sediments beneath the burial site were determined by laboratory and field tests. Laboratory hydraulic conductivity values ranged from about 10^-7 to 10^-1 feet per day for the clayey sediments to nearly 22 feet per day for aquifer sands. Field aquifer tests indicate a transmissivity of about 22,000 feet squared per day for Cretaceous sediments and about 6,000 feet squared per day for Tertiary sediments. Aquifer tests indicate heterogeneity in the upper 200 feet of the Tertiary sediments. Water samples were analyzed from 51 wells, 5 streams, a Carolina bay, and rainfall at the burial site. The total dissolved solids of the ground water ranged from about 7 to 40 milligrams per liter in the upper clayey sediments to about 150 milligrams per liter in the water in the deeper calcareous sediments. The pH of the ground water ranges from 4.8 to 6.5. This slightly acidic water is corrosive to buried metal. Tritium activity greater than background was detected in sediment cores taken from drill holes adjacent to the burial trenches. High tritium activity occurred at depths above the trench floor. This indicates upward movement of water or vapor to the land surface. Tritium and organic constituents greater than background concentrations were observed in a monitoring well about 10 feet from a trench, indicating lateral migration of radionuclides from the buried waste. Traces of cobalt-60 and tritium greater than background activity were observed in sediment cores collected 5.8 feet beneath the trench floor at

  12. An Updated Performance Assessment For A New Low-Level Radioactive Waste Disposal Facility In West Texas - 12192

    International Nuclear Information System (INIS)

    This Performance Assessment (PA) submittal is an update to the original PA that was developed to support the licensing of the Waste Control Specialists LLC Low-Level Radioactive Waste (LLRW) disposal facility. This update includes both the Compact Waste Facility (CWF) and the Federal Waste Facility (FWF), in accordance with Radioactive Material License (RML) No. R04100, License Condition (LC) 87. While many of the baseline assumptions supporting the initial license application PA were incorporated in this update, a new transport code, GoldSim, and new deterministic groundwater flow codes, including HYDRUS and MODFLOWSURFACTTM, were employed to demonstrate compliance with the performance objectives codified in the regulations and RML No. R04100, LC 87. A revised source term, provided by the Texas Commission on Environmental Quality staff, was used to match the initial 15 year license term. This updated PA clearly confirms and demonstrates the robustness of the characteristics of the site's geology and the advanced engineering design of the disposal units. Based on the simulations from fate and transport models, the radiation doses to members of the general public and site workers predicted in the initial and updated PA were a small fraction of the criterion doses of 0.25 mSv and 50 mSv, respectively. In a comparison between the results of the updated PA against the one developed in support of the initial license, both clearly demonstrated the robustness of the characteristics of the site's geology and engineering design of the disposal units. Based on the simulations from fate and transport models, the radiation doses to members of the general public predicted in the initial and updated PA were a fraction of the allowable 25 mrem/yr (0.25 m sievert/yr) dose standard for tens-of-thousands of years into the future. Draft Texas guidance on performance assessment (TCEQ, 2004) recommends a period of analysis equal to 1,000 years or until peak doses from the more mobile

  13. Summary of expenditures of rebates from the low-level radioactive waste surcharge escrow account for calendar year 1992

    International Nuclear Information System (INIS)

    This is the seventh report submitted to Congress in accordance with section 5(d)(2)(E)(ii)(II) of Title I--Low-Level Radioactive Waste Policy Amendments Act of 1985 (the Act). This section of the Act directs the Department of Energy (DOE) to summarize the annual expenditures of funds disbursed from the DOE surcharge escrow account and to assess compliance of these expenditures with the limitations specified in the Act. In addition to placing limitations on the use of these funds, the Act also requires the nonsited compact regions and nonmember States to provide DOE with an itemized report of their expenditures on December 31 of each year in which funds are expended. Within 6 months after receiving the individual reports, the Act requires the Secretary to furnish Congress with a summary of the reported expenditures and an assessment of compliance with the specified usage limitations. This report fulfills that requirement. DOE disbursed funds totaling $15,037,778.91 to the States and compact regions following the July 1, 1986, January 1, 1988, and January 1, 1990, milestones specified in the Act. Of this amount, $1,445,701.61 was expended during calendar year 1992 and $10,026,763.87 was expended during the prior 6 years. At the end of December 1992, $3,565,313.43 was unexpended. DOE has reviewed each of the reported expenditures and concluded that all reported expenditures comply with the spending limitations stated in section 5(d)(2)(E)(i) of the Act

  14. Efficient removal of cesium from low-level radioactive liquid waste using natural and impregnated zeolite minerals

    International Nuclear Information System (INIS)

    The objective of the proposed work was focused to provide promising solid-phase materials that combine relatively inexpensive and high removal capacity of some radionuclides from low-level radioactive liquid waste (LLRLW). Four various zeolite minerals including natural clinoptilolite (NaNCl), natural chabazite (NaNCh), natural mordenite (NaNM) and synthetic mordenite (NaSM) were investigated. The effective key parameters on the sorption behavior of cesium (Cs-134) were investigated using batch equilibrium technique with respect to the waste solution pH, contacting time, potassium ion concentration, waste solution volume/sorbent weight ratio and Cs ion concentration. The obtained results revealed that natural chabazite (NaNCh) has the higher distribution coefficients and capacity towards Cs ion rather than the other investigated zeolite materials. Furthermore, novel impregnated zeolite material (ISM) was prepared by loading Calix [4] arene bis(-2,3 naphtho-crown-6) onto synthetic mordenite to combine the high removal uptake of the mordenite with the high selectivity of Calix [4] arene towards Cs radionuclide. Comparing the obtained results for both NaSM and the impregnated synthetic mordenite (ISM-25), it could be observed that the impregnation process leads to high improvement in the distribution coefficients of Cs+ ion (from 0.52 to 27.63 L/g). The final objective in all cases was aimed at determining feasible and economically reliable solution to the management of LLRLW specifically for the problems related to the low decontamination factor and the effective recovery of monovalent cesium ion.

  15. Radionuclide Concentrations in soils an Vegetation at Low-Level Radioactive Waste Disposal Area G During 2004

    Energy Technology Data Exchange (ETDEWEB)

    P.R. Fresquez; E.A. Lopez

    2004-11-01

    Soil samples were collected at 15 locations and unwashed overstory and understory vegetation samples were collected at nine locations within and around the perimeter of Area G, the primary disposal facility for low-level radioactive solid waste at Los Alamos National Laboratory (LANL). These samples were analyzed for {sup 3}H, {sup 238}Pu, {sup 239,240}Pu, {sup 90}Sr, {sup 241}Am, {sup 137}Cs, {sup 234}U, {sup 235}U, and {sup 238}U. Soil samples collected at Area G contained detectable concentrations of 3H (27%), {sup 239,240}Pu (60%), {sup 238}Pu (40%), and {sup 241}Am (47%) above regional statistical reference levels (RSRLs). In contrast, the levels of {sup 137}Cs, {sup 90}Sr, and U in all of the soil samples at Area G were either nondetectable or within RSRLs. The highest levels of {sup 3}H in soils were detected in the southwestern portion of Area G near the {sup 3}H shafts, whereas the highest concentrations of the Pu isotopes were detected in the northern and northeastern portions. All concentrations of {sup 3}H and Pu in soils, however, were far below LANL screening action levels. As for vegetation, most radionuclides in/on plants were either nondetectable or within RSRLs. The exceptions were {sup 3}H in overstory and some understory vegetation, particularly in the southwestern portion of Area G, which correlated very well with the soils data in that area. Also, there was some foliar contamination from {sup 241}Am and Pu isotopes in/on a few plant samples--the highest concentrations occurring in the northern section of Area G.

  16. Characterization of radioactive hazardous waste

    International Nuclear Information System (INIS)

    The characterization of radioactive hazardous waste, also known as transuranic 'mixed waste' has to be completed before it can be classified for proper treatment (incinerator, mechanical compaction or thermal treatment), packing, and transport. The characterization of the TRU mixed waste is not only complex process but rather an expensive undertaking. The process knowledge is the basic foundation of characterization. It is the documented knowledge of processes and materials that generated the waste. The transuranic waste Quality Assurance Program Plan (QAPP) defines the Data Quality Objectives (DQO's) and provides the scope of analytical parameters and methods required to accurately characterize the radioactive mixed waste. Based on the historical data and process knowledge a sampling and analysis plan can be developed to characterize the radioactive hazardous waste. Based on the characterization, an assessment of the regulatory status can be made before the waste could be accepted for disposal at the WIPP facility. The Waste Acceptance Criteria (WAC) developed by WIPP defines the parameters for receiving and final disposal of the TRU waste. The sets of criteria, such as: heat generated, fissile gram equivalent (FGE), plutonium-equivalent (PE) curies, and specifications of a dose rate have to be met before the waste is accepted for deep geological disposal. The characterization of radioactive waste becomes even more complex due to the presence of iron base metals/alloys, aluminum base metals/alloys, organic, chelating agents that are mixed with plastic, rubber, cellulose, soils and cement. Some of the modern characterization technologies that are under development and currently used for TRU mixed wastes are: nondestructive examination, nondestructive assay, headspace gas analysis, and drum coring for Resources Conservation Recovery Act (RCRA) sampling. (author)

  17. The Site Investigation Of Low-Level Radioactive Waste For Sub-Surface Disposal Facility In Japan

    Science.gov (United States)

    Hosoya, S.; Sasaki, T.

    2006-12-01

    [1.Concept of the sub-surface disposal facility] In Japan, the facilities of Low-Level Radioactive West (LLW) for near-surface disposal have already been in operation. Japan Nuclear Fuel Limited (JNFL) has a plan of a new facility of LLW for sub-surface disposal with engineered barrier, for short "the sub-surface disposal facility".This facility can accept the relatively higher low-level waste from unclear power plant operation and in core materials from the decommissioning, estimated about 20 thousands cubic meter in total.In addition, this will accept transuranim (TRU) slightly contaminated waste from reprocessing plant operation and decommissioning. It shall be located at a sufficient depth enough to avoid normal human activities in future. [2.Site investigation] From 2001 to 2006,the site investigation on geology and hydrogeology has been performed in order to acquire the basic data for the design and the safety assessment for the sub-surface disposal facility.The candidate area is located at the site of JNFL, where Rokkasho-mura, Aomori Prefecture in the northern area of the Mainland of Japan.To confirm geology hydraulic conditions and geo-chemistry, 22 boring survey including 6 holes in swamp and marsh have been performed. The 1km long access tunnel (the entrance level EL 8.0m, incline of 1/10) to the altitude of EL -86m underground, around 100m depth from surface, has excavated. During excavating the tunnel, observation of geology, permeability tests, pore water pressure measurements and so on has been performed in situ.And the large size test cavern of 18m diameters was constructed at the end of the tunnel to demonstrate stability of the tunnel. Prior to the excavation, 3 measuring tunnels were excavated surrounding the test cavern to examine the excavation. [3.Geological features] The sedimentary rock called Takahoko formation at the Neogene period is distributed upper than EL-500m in the candidate area.The quaternary stratum about 10m in thickness is

  18. Chemical characterization, leach, and adsorption studies of solidified low-level wastes

    International Nuclear Information System (INIS)

    Laboratory and field leaching experiments are beig conducted by Pacific Northwest Laboratory (PNL) to investigate the performance of solidified low-level nuclear waste in a typical, arid, near-surface disposal site. Under PNL's Special Waste Form Lysimeters-Arid Program, a field test facility was constructed to monitor the leaching of commercial solidified waste. Laboratory experiments were conducted to investigate the leaching and adsorption characteristics of the waste forms in contact with soil. Liquid radioactive wastes solidified in cement, vinyl ester-styrene, and bitumen were obtained from commercial boiling water and pressurized water reactors, and buried in a field leaching facility on the Hanford site in southeastern Washington State. Batch leaching, soil column adsorption, and soil/waste form column experiments were conducted in the laboratory, using small-scale cement waste forms and Hanford site ground water. The purpose of these experiments is to evaluate the ability of laboratory leaching tests to predict leaching under actual field conditions and to determine which mechanisms (i.e., diffusion, solubility, adsorption) actually control the concentration of radionuclides in the soil surrounding the waste form. Chemical and radionuclide analyses performed on samples collected from the field and laboratory experiments indicate strong adsorption of /sup 134,137/Cs and 85Sr onto the Hanford site sediment. Small amounts of 60Co are leached from the waste forms as very mobile species. Some 60Co migrated through the soil at the same rate as water. Chemical constituents present in the reactor waste streams also found at elevated levels in the field and laboratory leachates include sodium, sulfate, magnesium, and nitrate. Plausible solid phases that could be controlling some of the chemical and radionuclide concentrations in the leachate were identified using the MINTEQ geochemical computer code

  19. Chemical characterization, leach, and adsorption studies of solidified low-level wastes

    Energy Technology Data Exchange (ETDEWEB)

    Walter, M.B.; Serne, R.J.; Jones, T.L.; McLaurine, S.B.

    1986-12-01

    Laboratory and field leaching experiments are beig conducted by Pacific Northwest Laboratory (PNL) to investigate the performance of solidified low-level nuclear waste in a typical, arid, near-surface disposal site. Under PNL's Special Waste Form Lysimeters-Arid Program, a field test facility was constructed to monitor the leaching of commercial solidified waste. Laboratory experiments were conducted to investigate the leaching and adsorption characteristics of the waste forms in contact with soil. Liquid radioactive wastes solidified in cement, vinyl ester-styrene, and bitumen were obtained from commercial boiling water and pressurized water reactors, and buried in a field leaching facility on the Hanford site in southeastern Washington State. Batch leaching, soil column adsorption, and soil/waste form column experiments were conducted in the laboratory, using small-scale cement waste forms and Hanford site ground water. The purpose of these experiments is to evaluate the ability of laboratory leaching tests to predict leaching under actual field conditions and to determine which mechanisms (i.e., diffusion, solubility, adsorption) actually control the concentration of radionuclides in the soil surrounding the waste form. Chemical and radionuclide analyses performed on samples collected from the field and laboratory experiments indicate strong adsorption of /sup 134,137/Cs and /sup 85/Sr onto the Hanford site sediment. Small amounts of /sup 60/Co are leached from the waste forms as very mobile species. Some /sup 60/Co migrated through the soil at the same rate as water. Chemical constituents present in the reactor waste streams also found at elevated levels in the field and laboratory leachates include sodium, sulfate, magnesium, and nitrate. Plausible solid phases that could be controlling some of the chemical and radionuclide concentrations in the leachate were identified using the MINTEQ geochemical computer code.

  20. Site characterization techniques used at a low-level waste shallow land burial field demonstration facility

    International Nuclear Information System (INIS)

    The Environmental Sciences Division of the Oak Ridge National Laboratory has been investigating improved shallow land burial technology for application in the humd eastern United States. As part of this effort, a field demonstration facility (Engineered Test Facility, or ETF) has been established in Solid Waste Storage Area 6 for purposes of investigatig the ability of two trench treatments (waste grouting prior to cover emplacement and waste isolation with trench liners) to prevent water-waste contact and thus minimize waste leaching. As part of the experimental plan, the ETF site has been characterized for purposes of constructing a hydrologic model. Site characterization is an extremely important component of the waste disposal site selection process; during these activities, potential problems, which might obviate the site from further consideration, may be found. This report describes the ETF site characterization program and identifies and, where appropriate, evaluates those tests that are of most value in model development. Specific areas covered include site geology, soils, and hydrology. Each of these areas is further divided into numerous subsections, making it easy for the reader to examine a single area of interest. Site characterization is a multidiscipliary endeavor with voluminous data, only portions of which are presented and analyzed here. The information in this report is similar to that which will be required of a low-level waste site developer in preparing a license application for a potential site in the humid East, (a discussion of licensing requirements is beyond its scope). Only data relevant to hydrologic model development are included, anticipating that many of these same characterization methods will be used at future disposal sites with similar water-related problems

  1. Characterization of polyurethane systems which contain low levels of free TDI

    Energy Technology Data Exchange (ETDEWEB)

    Myers, R.L.; Thomas, E.V.

    1995-04-01

    EN-7, EN-8, and EN-9 are polyurethane systems that are used in numerous applications in the Department of Energy complex. These systems contain high levels of toluene diisocyanate (TDI). Currently, TDI is being treated as a suspect human carcinogen within the Department of Energy complex. This report documents the results of a material characterization study of three polyurethane systems that contain low levels of free (potentially airborne) TDI. The characterization has been accomplished by performing a set of statistically designed experiments. The purpose of these experiments is to explore the effects of formulation and cure schedule on various material properties. In general, the material properties (pot life, glass transition temperature, hardness, and tear strength) were relatively insensitive to variation in the cure schedule. On the other hand, variation in curative level had measurable effects on material properties for the polyurethane systems studied. Furthermore, the material properties of the three low-free-TDI polyurethane systems were found to be comparable or superior (for certain curative levels) to commonly-used polyurethane systems. Thus, these low-free-TDI systems appear to be viable candidates for applications where a polyurethane is needed.

  2. The environment agency's assessment of BNGSL'S 2002 post-closure safety case for the low-level radioactive waste repository at drigg

    International Nuclear Information System (INIS)

    The Environment Agency regulates radioactive waste disposal in accordance with the Radioactive Substances Act 1993. British Nuclear Group Sellafield Ltd (BNGSL) is currently authorised to dispose of solid low-level radioactive waste (LLW) at a repository near the village of Drigg, in North-west England. We review authorizations for the disposal of radioactive waste periodically. We assessed BNGSL 2002 Post-Closure Safety Case (PCSC) for the LLW repository (LLWR) to inform the recent review of the LLWR Authorization. The paper presents an overview of our assessment of the 2002 PCSC for the LLWR, with particular emphasis on the process, rather than on specific review findings and recommendations. We have noted, in particular, some important lessons that are relevant to the consideration of any future applications for new near-surface or deep geological disposal facilities. (authors)

  3. Genesis and continuity of quaternary sand and gravel in glacigenic sediment at a proposed low-level radioactive waste disposal site in east-central Illinois

    Science.gov (United States)

    Troost, K.G.; Curry, B. Brandon

    1991-01-01

    The Illinois Department of Nuclear Safety has characterized the Martinsville Alternative Site (MAS) for a proposed low-level radioactive waste disposal facility. The MAS is located in east-central Illinois approximately 1.6 km (1 mi) north of the city of Martinsville. Geologic investigation of the 5.5-km2 (1380-acre) site revealed a sequence of chiefly Illinoian glacigenic sediments from 6 to 60 m (20-200 ft) thick overlying two major bedrock valleys carved in Pennsylvanian strata. Relatively permeable buried units include basal, preglacial alluvium; a complex of intraglacial and subglacial sediment; englacial deposits; and supraglacial fluvial deposits. Postglacial alluvium underlies stream valleys on and adjacent to the site. In most areas, the buried sand units are confined by low-permeability till, lacustrine sediment, colluvium, and loess. The distribution and thickness of the most extensive and continuous buried sand units have been modified considerably by subglacial erosion, and their distributions have been influenced by the buried bedrock valleys. The most continuous of the various sand units were deposited as preglacial and postglacial alluvium and are the uppermost and lowermost stratigraphic units at the alternative site. Sand units that were deposited in englacial or ice-marginal environments are less continuous. Aquifer pumping tests, potentiometric head data, and groundwater geochemistry analyses indicate minimal interaction of groundwater across localized interconnections of the permeable units. ?? 1991 Springer-Verlag New York Inc.

  4. Ground-water levels and precipitation data at the Maxey Flats low-level radioactive waste disposal site near Morehead, Kentucky, October 1988-September 2000

    Science.gov (United States)

    Zettwoch, Douglas D.

    2002-01-01

    The U.S. Geological Survey, in cooperation with the Kentucky Natural Resources and Environmental Protection Cabinet--Department for Environmental Protection--Division of Waste Management, has an ongoing program to monitor water levels at the Maxey Flats low-level radioactive waste disposal site near Morehead, Kentucky. Ground-water-level and precipitation data were collected from 112 wells and 1 rain gage at the Maxey Flats low-level radioactive waste disposal site during October 1988-September 2000. Data were collected on a semi-annual basis from 62 wells, continuously from 6 wells, and monthly or bimonthly from 44 wells (13 of which had continuous recorders installed for the period October 1998-September 2000). One tipping-bucket rain gage was used to collect data at the Maxey Flats site for the period October 1988-September 2000.

  5. Successful characterization of radioactive waste at the Savannah River Site

    International Nuclear Information System (INIS)

    Characterization of the low-level radioactive waste generated by forty five independent operating facilities at The Savannah River Site (SRS) experienced a slow start. However, the site effectively accelerated waste characterization based on findings of an independent assessment that recommended several changes to the existing process. The new approach included the development of a generic waste characterization protocol and methodology and the formulation of a technical board to approve waste characterization. As a result, consistent, detailed characterization of waste streams from SRS facilities was achieved in six months

  6. Review of the microbiological, chemical and radiolytic degradation of organic material likely to be present in intermediate level and low level radioactive wastes

    International Nuclear Information System (INIS)

    A review has been made of the microbiological, chemical and radiolytic degradation of the solid organic materials likely to be present in intermediate-level and low-level radioactive wastes. Possible interactions between the three routes for degradation are also discussed. Attention is focussed on the generation of water-soluble degradation products which may form complexes with radioelements. The effects of complexation on radioelement solubility and sorption are considered. Recommendations are made for areas of further research. (author)

  7. Characterization of Mesoscale Variability in WRF - a Coastal Low-Level Jet Case Study

    Science.gov (United States)

    Tay, K.; Lundquist, J. K.; Skote, M.; Koh, T. Y.

    2014-12-01

    Mesoscale weather models have increasingly been featured in wind resource assessment development. The incorporation of real meteorological conditions into such assessments allow a more realistic, physical determination of the wind loads that will be experienced within a wind farm site. Large-Eddy Simulation (LES) confers the advantage of representing finer scale turbulence, such as wake effects. However, nesting LES within real mesoscale simulations is still in the nascent stage of development. One of the difficulties lies in providing accurate mesoscale forcing boundaries for the LES domain. This study aims to characterize the mesoscale variability in WRF to lay the groundwork for future mesoscale-LES nested simulations. A low-level jet (LLJ) event that was observed during the CBLAST-Low 2001 campaign (07 Aug to 09 Aug) provides a robust case study to test the capabilities of and characterize the mesoscale variabilities in WRF. The dynamical interaction of a frontal passage with a stable boundary layer over a coastal region makes this an interesting and challenging case for real mesoscale simulation and future LES nested simulations. Sensitivities to vertical resolution, PBL schemes and initial forcing datasets were tested. This presentation will describe and explain the factors that influence the simulation of this frontal passage and the resulting LLJ. The initial forcing datasets have a major influence on spatial and temporal characteristics, as seen in Figure 1, introducing larger differences than the PBL schemes do. Furthermore, the mesoscale simulation also showed a strong dependence on the vertical resolution: increasing the vertical resolution within the atmospheric boundary layer resulted in a more accurate vertical profile for wind speed. Lastly, the simulations did show a dependency on the PBL scheme selected however, the variability between PBL schemes were not large, especially compared to the variability introduced by the boundary and initial

  8. The Environmental Protection Agency`s proposed regulation of low level radioactive waste (40 CFR Part 193): A Department of Energy overview

    Energy Technology Data Exchange (ETDEWEB)

    Frangos, T.G. [Dept. of Energy, Washington, DC (United States)

    1989-11-01

    The Department of Energy (DOE) manages one of the world`s largest programs for storage, treatment, and disposal of low-level radioactive wastes. This system with facilities located at sites across the nation has evolved over some forty years in response to changing needs, technologies, and increasing public awareness and concerns for environmental protection. The DOE has operated in a self regulatory mode in most aspects of its low-level waste (LLW) programs. It has been DOE`s policy and practice to provide at least the same level of safety and protection for the public, DOE and contractor employees, and the general environment, as that required by the Nuclear Regulatory Commission for commercial operations. DOE`s policies have been implemented through a management system that historically has been highly decentralized so as to be responsive to the needs of DOE sites which generate a wide variety of wastes at some 25 locations. In addition to concerns with the LLW that it manages, DOE has an interest in the US Environmental Protection Agency`s (EPA) promulgation of 40 CFR Part 193 because of its responsibilities under the Low Level Radioactive Waste Policy Amendments Act (LLRWPAA) to manage certain classes of waste and to assist and encourage the development of interstate compact-managed regional low-level waste disposal sites.

  9. Geochemical information for sites contaminated with low-level radioactive wastes: II. St. Louis Airport Storage Site

    International Nuclear Information System (INIS)

    The St. Louis Airport Storage Site (SLASS) became radioactively contaminated as a result of wastes that were being stored from operations to recover uranium from pitchblende ores in the 1940s and 1950s. The US Department of Energy is considering various remedial action options for the SLASS under the Formerly Utilized Site Remedial Action Program (FUSRAP). This report describes the results of geochemical investigations, carried out to support the FUSRAP activities and to aid in quantifying various remedial action options. Soil and groundwater samples from the site were characterized, and sorption ratios for uranium and radium and apparent concentration limit values for uranium were measured in soil/groundwater systems by batch contact methodology. The uranium and radium concentrations in soil samples were significantly above background near the old contaminated surface horizon (now at the 0.3- to 0.9-m depth); the maximum values were 1566 μg/g and 101 pCi/g, respectively. Below about the 6-m depth, the concentrations appeared to be typical of those naturally present in soils of this area (3.8 +- 1.2 μg/g and 3.1 +- 0.6 pCi/g). Uranium sorption ratios showed stratigraphic trends but were generally moderate to high (100 to 1000 L/kg). The sorption isotherm suggested an apparent uranium concentration limit of about 200 mg/L. This relatively high solubility can probably be correlated with the carbonate content of the soil/groundwater systems. The lower sorption ratio values obtained from the sorption isotherm may have resulted from changes in the experimental procedure or the groundwater used. The SLASS appears to exhibit generally favorable behavior for the retardation of uranium solubilized from waste in the site. Parametric tests were conducted to estimate the sensitivity of uranium sorption and solubility to the pH and carbonate content of the system

  10. Evaluation of low-level solid radioactive waste generated by a large hospital and disposed of with ordinary refuse

    International Nuclear Information System (INIS)

    In the Lombardy region some hospitals have recently been reported to the local authorities because of the presence of radioactivity in hospital refuse sent to the municipal tips for incineration. On various occasions the refuse collectors coming from the hospitals had to return with their refuse as traces of radioactivity were detected at the entrance to the tips equipped with monitoring systems. Hospitals administering radioactive substances for diagnostic or therapeutic purposes produce radioactive waste mainly in solid and liquid form. This waste is principally present in patient excreta and in contaminated materials. Radioactive waste present in patient excreta is normally disposed of through the sewage system provided that the concentration limits and annual activity stipulated by law are respected. The contaminated materials coming from the departments that carry out radioisotopic investigations and therapy with unsealed sources can be collected separately and sent to a tip after a period of storage to permit radioactive decay. However, part of the radioactive waste escapes all checks and inevitably mixes with normal refuse or with special hospital refuse that is not considered radioactive. This occurs in the case of: 1. excreta from patients who are not hospitalised after a radioisotopic investigation and materials contaminated by the excreta; 2. excreta from hospitalised patients which are eliminated outside the nuclear medicine and radiotherapy departments; 3. contaminated materials produced with unsealed sources in hospital departments other than those of nuclear medicine and radiotherapy; The waste indicated in point 1 is probably the main problem in ecological terms as the patients who are not hospitalised eliminate radioactive excreta into domestic sewage systems and can also contaminate materials that are disposed of with normal household refuse. In this case any solution to the problem would seriously affect diagnostic activities carried out in the

  11. IMPROVEMENTS IN CONTAINER MANAGEMENT OF TRANSURANIC (TRU) AND LOW LEVEL RADIOACTIVE WASTE STORED AT THE CENTRAL WASTE COMPLEX (CWC) AT HANFORD

    Energy Technology Data Exchange (ETDEWEB)

    UYTIOCO EM

    2007-11-14

    The Central Waste Complex (CWC) is the interim storage facility for Resource Conservation & Recovery Act (RCRA) mixed waste, transuranic waste, transuranic mixed waste, low-level and low-level mixed radioactive waste at the Department of Energy's (DOE'S) Hanford Site. The majority of the waste stored at the facility is retrieved from the low-level burial grounds in the 200 West Area at the Site, with minor quantities of newly generated waste from on-site and off-site waste generators. The CWC comprises 18 storage buildings that house 13,000 containers. Each waste container within the facility is scanned into its location by building, module, tier and position and the information is stored in a site-wide database. As waste is retrieved from the burial grounds, a preliminary non-destructive assay is performed to determine if the waste is transuranic (TRU) or low-level waste (LLW) and subsequently shipped to the CWC. In general, the TRU and LLW waste containers are stored in separate locations within the CWC, but the final disposition of each waste container is not known upon receipt. The final disposition of each waste container is determined by the appropriate program as process knowledge is applied and characterization data becomes available. Waste containers are stored within the CWC based on their physical chemical and radiological hazards. Further segregation within each building is done by container size (55-gallon, 85-gallon, Standard Waste Box) and waste stream. Due to this waste storage scheme, assembling waste containers for shipment out of the CWC has been time consuming and labor intensive. Qualitatively, the ratio of containers moved to containers in the outgoing shipment has been excessively high, which correlates to additional worker exposure, shipment delays, and operational inefficiencies. These inefficiencies impacted the LLW Program's ability to meet commitments established by the Tri-Party Agreement, an agreement between the State

  12. Eleventh annual U.S. DOE low-level radioactive waste management conference: Executive summary, opening plenary, technical session summaries, and attendees

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1990-01-01

    The conference consisted of ten technical sessions, with three sessions running simultaneously each day. Session topics included: regulatory updates; performance assessment;understanding remedial action efforts; low-level waste strategy and planning (Nuclear Energy); low-level waste strategy and planning (Defense); compliance monitoring; decontamination and decommissioning; waste characterization; waste reduction and minimization; and prototype licensing application workshop. Summaries are presented for each of these sessions.

  13. Management of Discharge of Low Level Liquid Radioactive Waste Generated in Medical, Educational, Research and Industrial Facilities

    International Nuclear Information System (INIS)

    Although published information on management technologies suitable for radioactive effluents is readily available, smaller facilities such as hospitals, universities and research laboratories in some countries can benefit from more detailed guidance on identifying optimal arrangements for effectively managing their radioactive liquid effluents. A wide range of circumstances exist globally, given that the generation of radioactive liquid effluents may be regular or irregular, and the liquid effluents may be suitable for direct discharge to the environment, or may require a period of decay storage prior to discharge. Countries typically fit into one of the four following categories with respect to the status of their arrangements for the management of radioactive liquid effluents: (1) The country does not have sufficient technical, regulatory and organizational infrastructure to effectively manage its radioactive liquid effluents; (2) The country's technical infrastructure for effectively managing its radioactive liquid effluents is almost sufficient, but it is not supported by an acceptable level of regulatory and organizational capacity (e.g. legal infrastructure, administrative infrastructure); (3) The country has sufficient technical, regulatory and organizational capacity, but it is known that the application of the requirements for proper management of radioactive liquid effluents is, in many cases, not being carried out to the standard indicated by official reports; (4) The country has well developed and established regulatory and organizational capacity, which is complemented by an acceptable level of relevant technical infrastructure such that the radioactive liquid effluents can be properly managed. Facilities, as well as countries, in the first three categories will find information in this publication to assist their further development. Even countries that already have the necessary infrastructure to properly manage their liquid radioactive effluents may

  14. Application of advanced radiographic imaging techniques for characterizing low level nuclear waste

    International Nuclear Information System (INIS)

    BIR is currently investigating the use of two advanced x-ray imaging techniques for characterizing containers of solidified nuclear waste. These techniques, digital radiography (DR) and computed tomography (CT), are performed by computerized imaging systems that can automatically inspect containers using a set of imaging parameters chosen by the operator. Both inspection techniques can be performed by the same imaging system. The inspection result is a computer image, or series of images, that can be manipulated by the operator to show a wide variety of features within the inspected object. For the inspections performed so far, we have used the ACTIS CT/DR system that BIR designed and built for NASA's Marshall Space Flight Center. The inspections are being performed as part of a continuing Phase I/Phase II SBIR program for the U.S. Department of Energy. This paper discusses inspections performed on three types of waste containers: (1) a simulated waste drum imaged in Phase 1; (2) 55 gallon drums of assorted waste items supplied by the DOE'S EG and G Rocky Flats plant and by Westinghouse Hanford; and (3) several containers of glass used for solidifying radioactive substances, supplied by the DOE'S Westinghouse Savannah River site. The Phase II work also includes investigating dual energy CT imaging and designing a mechanically simplified ACTIS system and mobile trailer specifically for waste inspection. (author)

  15. The Environmental Agency's Assessment of the Post-Closure Safety Case for the BNFL DRIGG Low Level Radioactive Waste Disposal Facility

    International Nuclear Information System (INIS)

    The Environment Agency is responsible, in England and Wales, for authorization of radioactive waste disposal under the Radioactive Substances Act 1993. British Nuclear Fuels plc (BNFL) is currently authorized by the Environment Agency to dispose of solid low level radioactive waste at its site at Drigg, near Sellafield, NW England. As part of a planned review of this authorization, the Environment Agency is currently undertaking an assessment of BNFL's Post-Closure Safety Case Development Programme for the Drigg disposal facility. This paper presents an outline of the review methodology developed and implemented by the Environment Agency specifically for the planned review of BNFL's Post-Closure Safety Case. The paper also provides an overview of the Environment Agency's progress in its on-going assessment programme

  16. The Environmental Agency's Assessment of the Post-Closure Safety Case for the BNFL DRIGG Low Level Radioactive Waste Disposal Facility

    Energy Technology Data Exchange (ETDEWEB)

    Streatfield, I. J.; Duerden, S. L.; Yearsley, R. A.

    2002-02-26

    The Environment Agency is responsible, in England and Wales, for authorization of radioactive waste disposal under the Radioactive Substances Act 1993. British Nuclear Fuels plc (BNFL) is currently authorized by the Environment Agency to dispose of solid low level radioactive waste at its site at Drigg, near Sellafield, NW England. As part of a planned review of this authorization, the Environment Agency is currently undertaking an assessment of BNFL's Post-Closure Safety Case Development Programme for the Drigg disposal facility. This paper presents an outline of the review methodology developed and implemented by the Environment Agency specifically for the planned review of BNFL's Post-Closure Safety Case. The paper also provides an overview of the Environment Agency's progress in its on-going assessment programme.

  17. The NEA research and environmental surveillance programme related to sea disposal of low-level radioactive waste

    Science.gov (United States)

    Rugger, B.; Templeton, W. L.; Gurbutt, P.

    1983-05-01

    Sea dumping operations of certain types of packaged low and medium level radioactive wastes have been carried out since 1967 in the North-East Atlantic under the auspices of the OECD Nuclear Energy Agency. On the occasion of the 1980 review of the continued suitability of the North-East Atlantic site used for the disposal of radioactive waste, it was recommended that an effort should be made to increase the scientific data base relating to the oceanographic and biological characteristics of the dumping area. In particular, it was suggested that a site specific model of the transfer of radionuclides in the marine environment be developed, which would permit a better assessment of the potential radiation doses to man from the dumping of radioactive waste. To fulfill these objectives a research and environmental surveillance program related to sea disposal of radioactive waste was set up in 1981 with the participation of thirteen Member countries and the International Laboratory for Marine Radioactivity of the IAEA in Monaco. The research program is focused on five research areas which are directly relevant to the preparation of more site specific assessments in the future. They are: model development; physical oceanography; geochemistry; biology; and radiological surveillance. Promising results have already been obtained and more are anticipated in the not too distant future. An interim description of the NEA dumping site has been prepared which provides an excellent data base for this area.

  18. Field demonstration of in situ treatment of buried low-level radioactive solid waste with caustic soda and soda ash to immobilize 90Sr

    International Nuclear Information System (INIS)

    A low-level radioactive solid waste disposal trench was injected on four occasions with solutions of caustic soda, soda ash, caustic soda, and lime/soda ash, respectively. Because investigations had indicated that 90Sr could be coprecipitated with soil calcium carbonate by treatment with soda ash, this demonstration was undertaken as a test of its technical feasibility. After concentrations of 90Sr and water hardness decreased within the intratrench monitoring wells; one well at the foot of the trench decreased from over 100 to a persistent level of less than 10 kBq of 90Sr per liter. Recharge of 90Sr from the trench to a sump immediately below was reduced by about 90%. Water hardness and 90Sr concentrations were strongly correlated through time within each monitoring well, indicating that 90Sr behaved as a tracer for soil calcium and magnesium. The disappearance of 90Sr from the trench water, therefore, was an in situ water softening. Soil samples retrieved from the trench indicated that as much as 98% of the total 90Sr was present as a coprecipitate with calcium carbonate. The hydrologic characterization of this trench indicated an average void space of 41% and an average trench-wall hydraulic conductivity of 3.4 x 10-7 m/s. Sampling of the trench's discharge contamination plume indicated that it had resulted from a combination of subsurface seepage and bathtub overflow during infrequent periods of intense precipitation. A generic assessment of soda ash treatment indicated that treatment would be most effective for soils of high cation exchange capacity with either low ( 80%) basic cation saturation of that cation exchange capacity

  19. Integration of US Department of Energy contractor installations for the purpose of optimizing treatment, storage, and disposal of low-level radioactive waste (LLW)

    Energy Technology Data Exchange (ETDEWEB)

    Lucas, M.; Gnoose, J.; Coony, M.; Martin, E.; Piscitella, R.

    1998-02-01

    The US Department of Energy (DOE) manages a multibillion dollar environmental management (EM) program. In June 1996, the Assistant Secretary of Energy for EM issued a memorandum with guidance and a vision for a ten year planning process for the EM Program. The purpose of this process, which became known as the Accelerated Cleanup: Focus on 2006, is to make step changes within the DOE complex regarding the approach for making meaningful environmental cleanup progress. To augment the process, Assistant Secretary requested the site contractors to engage in an effort to identify and evaluate integration alternatives for EM waste stream treatment, storage, and disposal (TSD) that would parallel the 2006 Plan. In October 1996, ten DOE contractor installations began the task of identifying alternative opportunities for low level radioactive waste (LLW). Cost effective, efficient solutions were necessary to meet all requirements associated with storing, characterizing, treating, packaging, transporting, and disposing of LLW while protecting the workers` health and safety, and minimizing impacts to the environment. To develop these solutions, a systems engineering approach was used to establish the baseline requirements, to develop alternatives, and to evaluate the alternatives. Key assumptions were that unique disposal capabilities exist within the DOE that must be maintained; private sector disposal capability for some LLW may not continue to exist into the foreseeable future; and decisions made by the LLW Team must be made on a system or complex wide basis to fully realize the potential cost and schedule benefits. This integration effort promoted more accurate waste volume estimates and forecasts; enhanced recognition of existing treatment, storage, and disposal capabilities and capacities; and improved identification of cost savings across the complex.

  20. Reduction of radioactive low-level liquid wastes in a reprocessing plant. Application of electrolysis to nitric acid decomposition -(2)-

    International Nuclear Information System (INIS)

    NOx gas generation by electrolysis of HNO3 has been extensively examined to drastically reduce the quantity of low-level liquid waste from a PUREX reprocessing plant. In this study, benchmark experiments used an electrolysis cell with 700-cm2 electrodes and auxiliary equipment for oxidation and distillation to concentrate a portion of the cathode loop depleted nitric acid, which contained HNO2. The material balance for the NOx-HNO2-HNO3 chemical equilibrium was clarified by the electrolysis. Further, a basic flow diagram was developed for a total system to effectively produce NOx gas. (authors)