WorldWideScience

Sample records for chemical disposal superfund

  1. Chemical Stockpile Disposal Program

    Energy Technology Data Exchange (ETDEWEB)

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

    1990-10-01

    As part of the Chemical Stockpile Disposal Program mandated by Public Law 99--145 (Department of Defense Authorization Act), an independent review is presented of the US Army Phase I environmental report for the disposal program at the Pine Bluff Arsenal (PBA) in Arkansas. The Phase I report addressed new and additional concerns not incorporated in the final programmatic environmental impact statement (FPEIS). Those concerns were addressed by examining site-specific data for the PBA and by recommending the scope and content of a more detailed site- specific study. This dependent review evaluates whether the new site-specific data presented in the Phase I report would alter the decision in favor of on-site disposal that was reached in the FPEIS, and whether the recommendations for the scope and content of the site-specific study are adequate. Based on the methods and assumptions presented in the FPEIS, the inclusion of more detailed site-specific data in the Phase I report does not change the decision reached in the FPEIS (which favored on-site disposal at PBA). It is recommended that alternative assumptions about meteorological conditions be considered and that site-specific data on water, ecological, socioeconomic, and cultural resources, and emergency planning and preparedness be considered explicitly in the site-specific EIS decision-making process. 13 refs., 1 fig.

  2. Chemical Stockpile Disposal Program

    Energy Technology Data Exchange (ETDEWEB)

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

    1990-10-01

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

  3. Chemical dechlorination of pesticides at a superfund site in Region II

    International Nuclear Information System (INIS)

    Selecting technologies for cleaning up hazardous waste sites is a complex task, due in part to the rapidly changing nature of the state-of-the-art in technology. There is strong support for use of innovative technologies as specified in Section 121(b) of CERCLA. However, use of an innovative technology requires overcoming a variety of challenges. These challenges include: Screening potentially appropriate technologies, including innovative technologies, and selecting one or more potential innovative technologies for which preliminary results are promising; however, site-specific data are needed prior to technology evaluation. Evaluating the effectiveness of the proposed technology for the site through the use of treatability studies. Gaining acceptance for the innovative technology, which may employ new or unfamiliar concepts. Determining optimal design and operating parameters for full-scale remediation. This paper discusses the technology evaluation process and how that process supported the selection of an innovative technology for the Myers Property site, a Superfund site in Region II. A case study is presented showing how technology screening and laboratory treatability studies were used to evaluate an innovative technology (chemical dechlorination), which was selected as the technology for remediation of soils and sediments contaminated with pesticides at this environmentally sensitive site in New Jersey. The remedy selected by the U.S. EPA for this site designates chemical dechlorination as the selected technology, but does not specify any particular vendor or process. Rather, the remedy sets forth technology performance standards and recommends certain design tasks which may be used to select a particular chemical process. This paper discusses he of these design tasks as they might apply to innovative technologies, using chemical dechlorination as a model

  4. Superfund Query

    Data.gov (United States)

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

  5. Health Aspects of the Disposal of Waste Chemicals.

    Science.gov (United States)

    Grisham, Joe W., Ed.

    Intended to be a source of information on the nature and significance of health effects related to chemical disposal, this document is the final report of the Executive Scientific Panel on Health Aspects of the Disposal of Waste Chemicals. The panel, which was organized by the Universities Associated for Research and Education in Pathology…

  6. Chemical reagent and process for refuse disposal

    International Nuclear Information System (INIS)

    A process for treating refuse by mixing them with a reactive chemical and a puzzolana-type material. Said chemical includes a retarding agent which modifies the viscosity and an accelerating agent. (author)

  7. Pilot demonstration for containment using in situ soil mixing techniques at a chemical disposal superfund site

    International Nuclear Information System (INIS)

    Kiber Environmental Services, Inc. (Kiber), under contract to McLaren-Hart Corporation and the site PRP group, performed technical oversight and on-site sampling and analyses at the confidential site located in Texas. The site consists of 15,000 cubic meters (20,000 cubic yards) of contaminated materials that were to be solidified on-site. The contaminants included heavy metals, PAHs, oil and grease, and volatile organics. Groundwater is less than 1 meter from the surface. Kiber was retained after several unsuccessful efforts to find on-site containment methods that effectively solidified the waste pits while achieving the performance goals. The PRP group then contracted with Kiber to perform the treatability and pilot oversight studies. The full-scale pilot demonstration was performed by Geo-Con. Pilot-scale treatment was performed to evaluate the effectiveness of in situ solidification treatment at achieving the site specific performance criteria, including an unconfined compressive strength of greater than 170 kPa (25 psi) and a permeability of less than 1x10-6 cm/sec. Technical oversight and on-site sampling and analysis were provided to evaluate pilot-scale application of the selected technology and verify treatment effectiveness. The project was divided into several subtasks. First, laboratory treatability testing was conducted to verify that performance specifications were achievable using the proposed reagent formulations. Next, a pilot demonstration was performed by Geo-Con using a Manotowoc 4000 crane equipped with a 1.5-meter diameter auger to evaluate shallow soil mixing. The final task included a comparative study between the performance of test specimens collected using wet sampling techniques versus in situ post-treatment coring

  8. Pilot demonstration for containment using in situ soil mixing techniques at a chemical disposal superfund site

    Energy Technology Data Exchange (ETDEWEB)

    Zarlinski, S.J.; Kingham, N.W.; Semenak, R. [Kiber Environmental Services, Inc., Atlanta, GA (United States)

    1997-12-31

    Kiber Environmental Services, Inc. (Kiber), under contract to McLaren-Hart Corporation and the site PRP group, performed technical oversight and on-site sampling and analyses at the confidential site located in Texas. The site consists of 15,000 cubic meters (20,000 cubic yards) of contaminated materials that were to be solidified on-site. The contaminants included heavy metals, PAHs, oil and grease, and volatile organics. Groundwater is less than 1 meter from the surface. Kiber was retained after several unsuccessful efforts to find on-site containment methods that effectively solidified the waste pits while achieving the performance goals. The PRP group then contracted with Kiber to perform the treatability and pilot oversight studies. The full-scale pilot demonstration was performed by Geo-Con. Pilot-scale treatment was performed to evaluate the effectiveness of in situ solidification treatment at achieving the site specific performance criteria, including an unconfined compressive strength of greater than 170 kPa (25 psi) and a permeability of less than 1x10{sup -6} cm/sec. Technical oversight and on-site sampling and analysis were provided to evaluate pilot-scale application of the selected technology and verify treatment effectiveness. The project was divided into several subtasks. First, laboratory treatability testing was conducted to verify that performance specifications were achievable using the proposed reagent formulations. Next, a pilot demonstration was performed by Geo-Con using a Manotowoc 4000 crane equipped with a 1.5-meter diameter auger to evaluate shallow soil mixing. The final task included a comparative study between the performance of test specimens collected using wet sampling techniques versus in situ post-treatment coring.

  9. 40 CFR 35.6340 - Disposal of CERCLA-funded property.

    Science.gov (United States)

    2010-07-01

    ... ASSISTANCE STATE AND LOCAL ASSISTANCE Cooperative Agreements and Superfund State Contracts for Superfund Response Actions Personal Property Requirements Under A Cooperative Agreement § 35.6340 Disposal of...

  10. Assessment of Soil Solution Chemicals after Tannery Effluents Disposal

    Directory of Open Access Journals (Sweden)

    Célia A.   Surita

    2007-01-01

    Full Text Available Knowledge about soil solution chemicals is important for assessing their mobility, availability, migration to groundwater and toxicity to plants. The objective of this study was to apply factor analysis to data obtained on soil solution chemicals during a one-year monitoring program in a controlled experiment with tannery effluents disposed on the soil surface, to extract information on their relationship and identify the main contaminants. Seventeen chemical parameters were monitored at six different depths on soil profile, focusing on metals and nitrate in soil solution. Four Factors accounted for 79.20% of the total variance, of which the most important were: Factor 1 (48.35% showed significant loadings for Mn2+, Na+, K+, Ca2+, Mg2+, Cl-, Pb2+ and electric conductivity, strongly influenced by high load effluent disposal; Factor 2 (12.21% was related with SO42+, Factor 3 (10.16% associated with Cu2+ and Zn2+ and Factor 4 (8.49% associated with nitrogen mineralization dynamics after high disposal.

  11. CERCLA/superfund orientation manual

    International Nuclear Information System (INIS)

    The manual serves as a program orientation guide and reference document, and it is designed to assist EPA and State personnel involved with hazardous waste remediation, emergency response, and chemical and emergency preparedness. The Manual describes the organizational and operational components of the Superfund Program

  12. Views on chemical safety information and influences on chemical disposal behaviour in the UK

    International Nuclear Information System (INIS)

    This study examined how groups representing four tiers in the chemical supply chain (manufacturers, vendors, workers and consumers) understood safety information, and the factors that influenced disposal behaviour. Data from seven, semi-structured, focus groups was analysed both qualitatively (textual analysis) and quantitatively (network analysis). Such combined analytical methods enabled us to achieve both detailed insights into perceptions and behaviour and an objective understanding of the prevailing opinions that occurred within and between the focus group discussions. We found issues around awareness, trust, access and disposal behaviours differed between groups within the supply chain. Participants from the lower tiers perceived chemical safety information to be largely inaccessible. Labels were the main source of information on chemical risks for the middle and bottom tiers of the supply chain. Almost all of the participants were aware of the St Andrew's Cross and skull and crossbones symbols but few were familiar with the Volatile Organic Compound logo or the fish and tree symbol. Both the network and thematic analysis demonstrated that whilst frequent references to health risks associated with chemicals were made environmental risks were usually only articulated after prompting. It is clear that the issues surrounding public understanding of chemical safety labels are highly complex and this is compounded by inconsistencies in the cognitive profiles of chemical users. Substantially different cognitive profiles are likely to contribute towards communication difficulties between different tiers of the supply chain. Further research is needed to examine the most effective ways of communicating chemical hazards information to the public. The findings demonstrate a need to improve and simplify disposal guidance to members of the public, to raise public awareness of the graphic symbols in the CHIP 3.1, 2005 regulations and to improve access to disposal guidance

  13. Views on chemical safety information and influences on chemical disposal behaviour in the UK

    Energy Technology Data Exchange (ETDEWEB)

    Hinks, J. [Enviresearch Ltd., Nanotechnology Centre, Herschel Building, Newcastle University, Newcastle upon Tyne, NE1 7RU (United Kingdom); Bush, J. [Institute for Health and Society, Newcastle University, William Leech Building, NE2 4HH (United Kingdom)], E-mail: Judith.bush@ncl.ac.uk; Andras, P. [School of Computing Science, Newcastle University, Claremont Tower, Newcastle University, NE1 7RU (United Kingdom); Garratt, J. [Institute for Health and Society, Newcastle University, William Leech Building, NE2 4HH (United Kingdom); Pigott, G. [NuFarm UK, Wyke, Bradford, West Yorkshire, BD12 9EJ (United Kingdom); Kennedy, A. [Enviresearch Ltd., Nanotechnology Centre, Herschel Building, Newcastle University, Newcastle upon Tyne, NE1 7RU (United Kingdom); Pless-Mulloli, T. [Institute for Health and Society, Newcastle University, William Leech Building, NE2 4HH (United Kingdom)

    2009-02-01

    This study examined how groups representing four tiers in the chemical supply chain (manufacturers, vendors, workers and consumers) understood safety information, and the factors that influenced disposal behaviour. Data from seven, semi-structured, focus groups was analysed both qualitatively (textual analysis) and quantitatively (network analysis). Such combined analytical methods enabled us to achieve both detailed insights into perceptions and behaviour and an objective understanding of the prevailing opinions that occurred within and between the focus group discussions. We found issues around awareness, trust, access and disposal behaviours differed between groups within the supply chain. Participants from the lower tiers perceived chemical safety information to be largely inaccessible. Labels were the main source of information on chemical risks for the middle and bottom tiers of the supply chain. Almost all of the participants were aware of the St Andrew's Cross and skull and crossbones symbols but few were familiar with the Volatile Organic Compound logo or the fish and tree symbol. Both the network and thematic analysis demonstrated that whilst frequent references to health risks associated with chemicals were made environmental risks were usually only articulated after prompting. It is clear that the issues surrounding public understanding of chemical safety labels are highly complex and this is compounded by inconsistencies in the cognitive profiles of chemical users. Substantially different cognitive profiles are likely to contribute towards communication difficulties between different tiers of the supply chain. Further research is needed to examine the most effective ways of communicating chemical hazards information to the public. The findings demonstrate a need to improve and simplify disposal guidance to members of the public, to raise public awareness of the graphic symbols in the CHIP 3.1, 2005 regulations and to improve access to disposal

  14. Challenges to Superfund Community Nutrition Programs in Kentucky

    OpenAIRE

    Gaetke, Lisa; Gaetke, Kara; Bowen, Christa

    2008-01-01

    Since 2000, the University of Kentucky's (UK's) Superfund Basic Research Program (SBRP) Community Outreach Core has provided support and guidance through Superfund Community Action through Nutrition (SCAN) programs, which meet the needs of individuals and communities affected by environmental contaminants. It has been shown that nutrition may modulate the toxicity of Superfund chemicals. SCAN programs integrate nutrition education, nutrition science research, and health communication to incre...

  15. 40 CFR 35.6350 - Disposal of federally owned property.

    Science.gov (United States)

    2010-07-01

    ... FEDERAL ASSISTANCE STATE AND LOCAL ASSISTANCE Cooperative Agreements and Superfund State Contracts for Superfund Response Actions Personal Property Requirements Under A Cooperative Agreement § 35.6350 Disposal... Cooperative Agreement...

  16. Groundwater hydrology study of the Ames Chemical Disposal Site

    International Nuclear Information System (INIS)

    The Ames Laboratory Chemical Disposal Site is located in northwestern Ames, Iowa west of Squaw Creek. From 1957 to 1966, Ames Laboratory conducted research to develop processes to separate uranium and thorium from nuclear power fuel and to separate yttrium from neutron shielding sources. The wastes from these processes, which contained both hazardous and radiological components, were placed into nine burial pits. Metal drums, plywood boxes, and steel pails were used to store the wastes. Uranium was also burned on the ground surface of the site. Monitoring wells were placed around the waste burial pits. Groundwater testing in 1993 revealed elevated levels of Uranium 234, Uranium 238, beta and alpha radiation. The north side of the burial pit had elevated levels of volatile organic compounds. Samples in the East Ravine showed no volatile organics; however, they did contain elevated levels of radionuclides. These analytical results seem to indicate that the groundwater from the burial pit is flowing down hill and causing contamination in the East Ravine. Although there are many avenues for the contamination to spread, the focus of this project is to understand the hydrogeology of the East Ravine and to determine the path of groundwater flow down the East Ravine. The groundwater flow data along with other existing information will be used to assess the threat of chemical migration down the East Ravine and eventually off-site. The primary objectives of the project were as follows: define the geology of the East Ravine; conduct slug tests to determine the hydraulic conductivity of both oxidized and unoxidized till; develop a three-dimensional mathematical model using ModIME and MODFLOW to simulate groundwater flow in the East Ravine

  17. Chemical analyses of dredged spoil disposal sites at the Belgian part of the North Sea.

    Science.gov (United States)

    De Witte, Bavo; Ruttens, Ann; Ampe, Bart; Waegeneers, Nadia; Gauquie, Johanna; Devriese, Lisa; Cooreman, Kris; Parmentier, Koen

    2016-08-01

    The chemical status of five dredged spoil disposal sites in the Belgian Part of the North Sea is evaluated. A linear mixed-effect model was applied to PCB, PAH and heavy metal data from 2005 to 2014. No decrease in PCB concentrations was found, with even an increase at two disposal sites. Hg/AL ratios increased with 62% at one disposal site (BR&WS2) from 2005 to 2006 to 2013-2014. Cu and Zn concentrations increased at two disposal sites. Additional harbour sampling suggests that the latter is possibly linked to antifouling paints. Based on OSPAR environmental assessment criteria, the current chemical status of the sites suggests no chronic effect of dredged spoil disposal. However, increasing time trend data for PCB, Hg, Cu and Zn demonstrate the importance of monitoring to identify adverse trends. PMID:27176939

  18. Superfund Site Information

    Data.gov (United States)

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

  19. Superfund Technical Assistance Grants

    Data.gov (United States)

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

  20. JOHNSTON ATOLL CHEMICAL AGENT DISPOSAL SYSTEM (JACADS) CLOSURE PLAN DEVELOPMENT

    Science.gov (United States)

    The JACADS project consists of four incinerators including a liquid chemical agent waste processor, an explosives treatment incinerator and a batch metal parts treatment unit. Its mission was to disassemble and destroy chemcial weapons and bulk chemical agent. This prototypical...

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1990-09-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1991-09-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1993-02-01

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

  4. Chemical hazard evaluation of material disposal area (MDA) B closure project

    Energy Technology Data Exchange (ETDEWEB)

    Laul, Jagdish C [Los Alamos National Laboratory

    2010-04-19

    TA-21, MDA-B (NES) is the 'contaminated dump,' landfill with radionuclides and chemicals from process waste disposed in 1940s. This paper focuses on chemical hazard categorization and hazard evaluation of chemicals of concern (e.g., peroxide, beryllium). About 170 chemicals were disposed in the landfill. Chemicals included products, unused and residual chemicals, spent, waste chemicals, non-flammable oils, mineral oil, etc. MDA-B was considered a High hazard site. However, based on historical records and best engineering judgment, the chemical contents are probably at best 5% of the chemical inventory. Many chemicals probably have oxidized, degraded or evaporated for volatile elements due to some fire and limited shelf-life over 60 yrs, which made it possible to downgrade from High to Low chemical hazard site. Knowing the site history and physical and chemical properties are very important in characterizing a NES site. Public site boundary is only 20 m, which is a major concern. Chemicals of concern during remediation are peroxide that can cause potential explosion and beryllium exposure due to chronic beryllium disease (CBD). These can be prevented or mitigated using engineering control (EC) and safety management program (SMP) to protect the involved workers and public.

  5. Superfund Record of Decision (EPA Region 4): Agrico Chemical, Escambia County, Pensacola, FL. (First remedial action), September 1992

    Energy Technology Data Exchange (ETDEWEB)

    1992-09-29

    The 35-acre Agrico Chemical site is a former fertilizer manufacturing facility located in Pensacola, Escambia County, Florida. In 1920, the production of superphosphate fertilizer began. The source rock used in the process was fluorapatite, which also contained silica and trace levels of aluminum and uranium. The ROD addresses a final remedy for contaminated soil and sludge at the site as OU1 to prevent current or future exposure. The primary contaminants of concern affecting the soil and sludge are VOCs; other organics including PAHs and pesticide residues; metals, including arsenic and lead; and radioactive materials.

  6. The value of superfund cleanups : evidence from U.S. Environmental Protection Agency decisions

    OpenAIRE

    Gupta, Shreekant; Van Houtven, George; Cropper, Maureen L.; DEC

    1994-01-01

    Under the Superfund law, the U.S. Environmental Protection Agency (EPA) is responsible for inspecting hazardous waste sites and for putting those with the most serious contamination problems on a national priorities list. The EPA then oversees the cleanup of these sites, suing potentially responsible parties for the costs of cleanup when possible, and funding the cleanup of"orphaned"sites out of the Superfund, money raised taxing chemical and petroleum products. The Superfund program is contr...

  7. SITE COMPREHENSIVE LISTING (CERCLIS) (Superfund)

    Data.gov (United States)

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

  8. Time-lapse camera studies of sea-disposed chemical munitions in Hawaii

    Science.gov (United States)

    Edwards, Margo H.; Fornari, Daniel J.; Rognstad, Mark R.; Kelley, Christopher D.; Mah, Christopher L.; Davis, Logan K.; Flores, Kyle R. M.; Main, Erin L.; Bruso, Natalie L.

    2016-06-01

    The interactions between fauna and sea-disposed munitions provide important evidence regarding whether munitions constituents affect the health of the ocean environment and its inhabitants. To date few studies of these interactions have been conducted at deep-water disposal sites; typically observations of fauna in the vicinity of sea-disposed munitions are limited to the few minutes or hours required to collect physical samples at a specific location. During the 2012 Hawaii Undersea Military Munitions Assessment (HUMMA) field program we deployed two deep-sea time-lapse camera systems with the objectives of cataloging the diversity of fauna visiting sea-disposed chemical munitions and observing faunal behavior and physiology. Over the 1- and 3-day deployments we recorded 28 different species of fishes, crustaceans, mollusks, cnidarians, and echinoderms at the two sites. Both cameras captured the previously undocumented behavior of brisingid sea stars repositioning themselves along chemical munitions casings. Despite the fact that brisingid sea stars are able to move, for the duration of both time-lapse experiments they remained on chemical munitions casings. We interpret this result to indicate that the advantages of residing on a hard substrate slightly elevated above the seafloor outweigh the effects of chemical munitions constituents for brisingid sea stars. One type of physiological anomaly observed on several arms of the brisingid sea stars at the time-lapse sites led to the collection and examination of six specimens. As reported by Mah (2015. Deep Sea Res. II, 2015, XX-XX), these physiological features are the result of parasitic crustaceans and are not caused by chemical munitions constituents.

  9. Chemical modelling studies in support of radiological risk assessments of radioactive waste disposal 1984-86

    International Nuclear Information System (INIS)

    This report describes the testing of computer programs identified as being capable of modelling chemical processes in radioactive waste disposal systems. The functions, limitations and data requirements of the programs assembled at UWIST are discussed and the organisation of an extensive thermodynamic database compiled to support the codes described. The role of chemical models in DoE probabilistic radiological assessment (PRA) methodology, is outlined. Their potential for radiological assessment purposes has been addressed through a series of case studies on existing and potential low- and intermediate-level radioactive waste disposal sites. Results to date suggest them to be capable of fulfilling their intended role within the constraints of model assumptions. A number of collaborative projects designed to verify, validate and improve the models have been established. (author)

  10. 75 FR 49414 - Cooperative Agreements and Superfund State Contracts for Superfund Response Actions

    Science.gov (United States)

    2010-08-13

    ... AGENCY 40 CFR Part 35 RIN 2050-AG58 Cooperative Agreements and Superfund State Contracts for Superfund... Superfund Cooperative Agreements and Superfund State Contracts. DATES: This rule is effective October 12... requirements shall apply to all new Cooperative Agreements and Superfund State Contracts, funded under...

  11. Chemical toxicity in final disposal of spent nuclear fuel; Kemiallinen myrkyllisyys kaeytetyn ydinpolttoaineen loppusijoituksessa

    Energy Technology Data Exchange (ETDEWEB)

    Raiko, E. [Posiva Oy, Helsinki (Finland); Nordman, H. [VTT Energy, Espoo (Finland)

    1999-03-01

    This report studies the chemical long-term environmental effects of the substances released from the canisters of spent nuclear fuel. An overall inventory has been made of all the chemical elements contained in the canister materials and spent fuel. The release and transport of the most toxic and abundant elements have been studied with calculations using the solubilities of elements or with analyses carried out by computer codes. The resulting concentrations of elements in groundwater have been compared to the concentration limits defined in the pertinent authority requirements for drinking water. The results show that the chemical toxicity is not a significant factor as regards the safety of the final disposal of spent nuclear fuel. (orig.) 26 refs. Working report

  12. Development of land disposal restrictions for military chemical agent-associated waste

    Energy Technology Data Exchange (ETDEWEB)

    Kimmell, T.A.; Anderson, A.W.; Rosenblatt, D.H. [and others

    1997-04-01

    In July 1988, the State of Utah, Department of Solid and Hazardous Waste (DSHW) listed certain military chemical agents as hazardous waste, as well as residues resulting from the demilitarization, treatment, and testing of these chemicals. These materials are listed as hazardous waste in Utah, but are not listed as hazardous wastes under the Federal Resource Conservation and Recovery Act (RCRA), the primary law governing management of hazardous waste in the United States. Pursuant to the 1984 Hazardous and Solid Waste Amendments (HSWA) to RCRA, the U.S. Environmental Protection Agency (EPA) has established Land Disposal Restriction (LDR) treatment standards for most categories of hazardous wastes. However, considering that EPA has not listed chemical agent-associated wastes as hazardous waste under RCRA, LDR treatment standards have not been established specifically for these wastes. In February 1995, the DSHW announced a regulatory initiative to develop LDRs for chemical agent-associated wastes and solicited data and information from the U.S. Army to support a rulemaking effort. The Army`s Chemical and Biological Defense Command (CBDCOM) was designated the lead agency for the Army to assist the DSHW in developing the rule. CBDCOM established the U.S. Army Land Disposal Restrictions Utah Group (LDRUG) and initiated a project with Argonne National Laboratory to support the LDRUG. The focus is on providing the state with accurate and up-to-date data and information to support the rulemaking and the establishment of LDRs. The purpose of this paper is to review the general direction of the proposed rule and to discuss overall progress. Potential impacts of the imposition of LDRs on the management of agent-associated wastes are also reviewed.

  13. Superfund list adds Pantex

    International Nuclear Information System (INIS)

    While Congress crafts Superfund reauthorization to see that more money is spent on cleanups instead of legal fees, the U.S. Environmental Protection Agency added 24 federal facilities to the National Priorities List of the worst pollution problems. Three Department of Energy sites were added on May 31, despite objections from state and other officials about how sites were selected. The Pantex nuclear weapon plant in Amarillo, Texas, was included despite protests by state officials, while environmentalists claim that open-quotes political gamesmanshipclose quotes kept a Portsmouth, Ohio, uranium enrichment plant off the list. Other DOE sites listed were the Paducah (Kentucky) Gaseous Diffusion Plant and the Laboratory for Energy Related Health Research in Davis, California

  14. Online data sources for regulation and remediation of chemical production, distribution, use and disposal

    International Nuclear Information System (INIS)

    Environmental awareness is essential for todays corporation. Corporations have been held liable for the short-term and long-term effects of such chemicals as pharmaceuticals, agrochemicals and petrochemicals to name a few. Furthermore, corporations have been held accountable for disposal of wastes or by-products of chemical production. Responsibility for the environment either mandated by government agencies or done voluntarily is an economic factor for business operations. Remediation of environmental hazards on a voluntary basis has often created goodwill and a payoff for being socially responsible. Remediation also can result in new business opportunities or savings in production costs. To be environmentally aware and socially responsible, the chemist should know where to find regulatory information for countries worldwide. Using online data sources is an efficient method of seeking this information

  15. Solid waste disposal in the soil: effects on the physical, chemical, and organic properties of soil

    Directory of Open Access Journals (Sweden)

    Vanessa Regina Lasaro Mangieri

    2015-04-01

    Full Text Available Currently, there is growing concern over the final destination of the solid waste generated by society. Landfills should not be considered the endpoint for substances contained or generated in solid waste. The sustainable use of natural resources, especially soil and water, has become relevant, given the increase in anthropogenic activities. Agricultural use is an alternative to solid waste (leachate, biosolid disposal, considering the hypothesis that the agricultural use of waste is promising for reducing waste treatment costs, promoting nutrient reuse and improving the physical and chemical conditions of soil. Thus, this literature review, based on previously published data, seeks to confirm or disprove the hypothesis regarding the promising use of solid waste in agriculture to decrease the environmental liability that challenges public administrators in the development of efficient management. The text below addresses the following subtopics after the introduction: current solid waste disposal and environmental issues, the use of solid waste in agriculture, and the effect on the physical and chemical properties of soil and on organic matter, ending with final considerations.

  16. Features of the process of drilling sludge’s disposal with the chemical method using a phosphogypsum

    OpenAIRE

    Аблєєва, Ірина Юріївна; Пляцук, Леонід Дмитрович; Коцюба, Ірина Григорівна

    2014-01-01

    A negative impact on the environment while drilling for oil has been characterized. It is proved that the drilling sludge creates environmental burden and reduces the stability of the territories. Therefore, to solve this problem it is necessary to disposal it with the use of environmentally safe and cost-effective technology. The chemical method of disposal of this type of waste using phosphogypsum has been proposed. It was determined that the process of interaction will largely influence th...

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1991-09-01

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

  18. Environmental contaminants in fish and mussels from Meddybemps Lake, the Dennys River, and East Machias River - Eastern Surplus Superfund Site, Meddybemps, Maine

    Data.gov (United States)

    US Fish and Wildlife Service, Department of the Interior — From 1946 to the early 1980s, the 3-acre Eastern Surplus Superfund Site in Meddybemps, Maine, was used for the disposal and storage of surplus military equipment...

  19. Inhibition of hydrogen sulfide generation from disposed gypsum drywall using chemical inhibitors

    International Nuclear Information System (INIS)

    Disposal of gypsum drywall in landfills has been demonstrated to elevate hydrogen sulfide (H2S) concentrations in landfill gas, a problem with respect to odor, worker safety, and deleterious effect on gas-to-energy systems. Since H2S production in landfills results from biological activity, the concept of inhibiting H2S production through the application of chemical agents to drywall during disposal was studied. Three possible inhibition agents - sodium molybdate (Na2MoO4), ferric chloride (FeCl3), and hydrated lime (Ca(OH)2) - were evaluated using flask and column experiments. All three agents inhibited H2S generation, with Na2MoO4 reducing H2S generation by interrupting the biological sulfate reduction process and Ca(OH)2 providing an unfavorable pH for biological growth. Although FeCl3 was intended to provide an electron acceptor for a competing group of bacteria, the mechanism found responsible for inhibiting H2S production in the column experiment was a reduction in pH. Application of both Na2MoO4 and FeCl3 inhibited H2S generation over a long period (over 180 days), but the impact of Ca(OH)2 decreased with time as the alkalinity it contributed was neutralized by the generated H2S. Practical application and potential environmental implications need additional exploration.

  20. Inhibition of hydrogen sulfide generation from disposed gypsum drywall using chemical inhibitors.

    Science.gov (United States)

    Xu, Qiyong; Townsend, Timothy; Bitton, Gabriel

    2011-07-15

    Disposal of gypsum drywall in landfills has been demonstrated to elevate hydrogen sulfide (H(2)S) concentrations in landfill gas, a problem with respect to odor, worker safety, and deleterious effect on gas-to-energy systems. Since H(2)S production in landfills results from biological activity, the concept of inhibiting H(2)S production through the application of chemical agents to drywall during disposal was studied. Three possible inhibition agents - sodium molybdate (Na(2)MoO(4)), ferric chloride (FeCl(3)), and hydrated lime (Ca(OH)(2)) - were evaluated using flask and column experiments. All three agents inhibited H(2)S generation, with Na(2)MoO(4) reducing H(2)S generation by interrupting the biological sulfate reduction process and Ca(OH)(2) providing an unfavorable pH for biological growth. Although FeCl(3) was intended to provide an electron acceptor for a competing group of bacteria, the mechanism found responsible for inhibiting H(2)S production in the column experiment was a reduction in pH. Application of both Na(2)MoO(4) and FeCl(3) inhibited H(2)S generation over a long period (over 180 days), but the impact of Ca(OH)(2) decreased with time as the alkalinity it contributed was neutralized by the generated H(2)S. Practical application and potential environmental implications need additional exploration. PMID:21592650

  1. Disposal of chemical agents and munitions stored at Umatilla Depot Activity, Hermiston, Oregon. Final Phase 1 environmental report

    Energy Technology Data Exchange (ETDEWEB)

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

    1993-02-01

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

  2. Chemical Decomposition of High-Level Nuclear Waste Storage/Disposal Glasses Under Irradiation

    International Nuclear Information System (INIS)

    The objective of this project is to employ the technique of electron spin resonance (ESR), in conjunction with other experimental methods, to study radiation-induced decomposition of vitreous compositions proposed for immobilization/disposal of high-level nuclear wastes (HLW) or excess weapons plutonium. ESR is capable of identifying, even at the parts-per-million level, displaced atoms, ruptured bonds, and free radicals created by radiation in such glassy forms. For example, one of the scientific goals is to search for ESR-detectable superoxide (O2 -) and ozonide (O3 -) ions, which could be precursors of radiation-induced oxygen gas bubbles reported by other investigators via the disproportionation reaction, 2O2 - : O2 2- + O2. The fundamental understandings obtained in this study will enable reliable predictions of the long-term effects of a and B decays of the immobilized radionuclides on the chemical integrity of HLW glasses

  3. Chemical Decomposition of High-Level Nuclear Waste Storage/Disposal Glasses Under Irradiation

    Energy Technology Data Exchange (ETDEWEB)

    Griscom, David L.

    1999-06-01

    The objective of this project is to employ the technique of electron spin resonance (ESR), in conjunction with other experimental methods, to study radiation-induced decomposition of vitreous compositions proposed for immobilization/disposal of high-level nuclear wastes (HLW) or excess weapons plutonium. ESR is capable of identifying, even at the parts-per-million level, displaced atoms, ruptured bonds, and free radicals created by radiation in such glassy forms. For example, one of the scientific goals is to search for ESR-detectable superoxide (O2 -) and ozonide (O3 -) ions, which could be precursors of radiation-induced oxygen gas bubbles reported by other investigators via the disproportionation reaction, 2O2 - : O2 2- + O2. The fundamental understandings obtained in this study will enable reliable predictions of the long-term effects of a and B decays of the immobilized radionuclides on the chemical integrity of HLW glasses.

  4. Disposal of chemical agents and munitions stored at Pueblo Depot Activity, Colorado. Final, Phase 1: Environmental report

    Energy Technology Data Exchange (ETDEWEB)

    Terry, J.W.; Blasing, T.J.; Ensminger, J.T.; Johnson, R.O.; Schexnayder, S.M.; Shor, J.T.; Staub, W.P.; Tolbert, V.R.; Zimmerman, G.P.

    1995-04-01

    Under the Chemical Stockpile Disposal Program (CSDP), the US Army proposes to dispose of lethal chemical agents and munitions stored at eight existing Army installations in the continental United States. In 1988, the US Army issued the final programmatic environmental impact statement (FPEIS) for the CSDP. The FPEIS and the subsequent Record of Decision (ROD) identified an on-site disposal process as the preferred method for destruction of the stockpile. That is, the FPEIS determined the environmentally preferred alternative to be on-site disposal in high-temperature incinerators, while the ROD selected this alternative for implementation as the preferred method for destruction of the stockpile. In this Phase I report, the overall CSDP decision regarding disposal of the PUDA Stockpile is subjected to further analyses, and its validity at PUDA is reviewed with newer, more detailed data than those providing the basis for the conclusions in the FPEIS. The findings of this Phase I report will be factored into the scope of a site-specific environmental impact statement to be prepared for the destruction of the PUDA stockpile. The focus of this Phase I report is on those data identified as having the potential to alter the Army`s previous decision regarding disposal of the PUDA stockpile; however, several other factors beyond the scope of this Phase I report must also be acknowledged to have the potential to change or modify the Army`s decisions regarding PUDA.

  5. 'Geo'chemical research: a key building block for nuclear waste disposal safety cases.

    Science.gov (United States)

    Altmann, Scott

    2008-12-12

    Disposal of high level radioactive waste in deep underground repositories has been chosen as solution by several countries. Because of the special status this type waste has in the public mind, national implementation programs typically mobilize massive R&D efforts, last decades and are subject to extremely detailed and critical social-political scrutiny. The culminating argument of each program is a 'Safety Case' for a specific disposal concept containing, among other elements, the results of performance assessment simulations whose object is to model the release of radionuclides to the biosphere. Public and political confidence in performance assessment results (which generally show that radionuclide release will always be at acceptable levels) is based on their confidence in the quality of the scientific understanding in the processes included in the performance assessment model, in particular those governing radionuclide speciation and mass transport in the geological host formation. Geochemistry constitutes a core area of research in this regard. Clay-mineral rich formations are the subjects of advanced radwaste programs in several countries (France, Belgium, Switzerland...), principally because of their very low permeabilities and demonstrated capacities to retard by sorption most radionuclides. Among the key processes which must be represented in performance assessment models are (i) radioelement speciation (redox state, speciation, reactions determining radionuclide solid-solution partitioning) and (ii) diffusion-driven transport. The safety case must therefore demonstrate a detailed understanding of the physical-chemical phenomena governing the effects of these two aspects, for each radionuclide, within the geological barrier system. A wide range of coordinated (and internationally collaborated) research has been, and is being, carried out in order to gain the detailed scientific understanding needed for constructing those parts of the Safety Case

  6. Restoration principles and criteria: Superfund programme policy for cleanup at radiation contaminated sites

    International Nuclear Information System (INIS)

    The Environmental Protection Agency (EPA) Office of Solid Waste and Emergency Response is responsible for implementing two key US laws regulating waste management and cleanup: the Resource Conservation and Recovery Act, and the Comprehensive Environmental Response, Compensation and Liability Act, CERCLA, nicknamed ''Superfund''. The purpose of the Superfund programme is to protect human health and the environment over the long term from releases or potential releases of hazardous substances from abandoned or uncontrolled hazardous waste sites. The focus of this paper is on Superfund, including how radiation is addressed by the Superfund programme. This paper provides a brief overview of the approach used by EPA to conduct Superfund cleanups at contaminated sites, including those that are contaminated with radionuclides, to ensure protection of human health and the environment. The paper addresses how EPA Superfund determines if a site poses a risk to human health and the framework used to determine cleanup levels. The theme emphasized throughout the paper is that within the Superfund remediation framework, radioactive contamination is dealt with in the identical way as chemical contamination. (author)

  7. 40 CFR 35.6800 - Superfund State Contract.

    Science.gov (United States)

    2010-07-01

    ... ASSISTANCE STATE AND LOCAL ASSISTANCE Cooperative Agreements and Superfund State Contracts for Superfund Response Actions Requirements for Administering A Superfund State Contract (ssc) § 35.6800 Superfund State... 40 Protection of Environment 1 2010-07-01 2010-07-01 false Superfund State Contract....

  8. Chemical stability and adsorption of atracurium besylate injections in disposable plastic syringes.

    Science.gov (United States)

    Pramar, Y V; Loucas, V A; Word, D

    1996-06-01

    Atracurium besylate (AB) is supplied as a sterile, non-pyrogenic aqueous solution for intravenous use. Hospitals pre-fill disposable plastic syringes with these solutions so that they are ready for immediate use when required. Drug loss due to potential adsorption on to the plastic material of the syringes has not been studied. Atracurium is also administered by intravenous infusion using a diluted solution in either 5% dextrose injection (USP) or 0.9% sodium chloride injection USP. Drug solutions not used within 24 h are usually discarded, resulting in tremendous waste. The purpose of these investigations was to determine the adsorption behaviour of atracurium when stored in plastic syringes, and to study the degradation of atracurium in i.v. fluids. For the adsorption study, 10 mg/ml solutions were used, whereas the diluted infusion solutions were prepared to contain 0.5 mg/ml of atracurium. Drug degradation was monitored using a stability-indicating high-performance liquid chromatography method. Degradation studies were conducted at 5 degrees C, 25 degrees C and 40 degrees C. Refrigeration was observed to improve drug stability. The manufacturer's recommended expiry period was too conservative. Storage at room temperature for up to 6 weeks can be safely recommended, without significant loss of chemical stability.

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

    Data.gov (United States)

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

  10. CERCLIS (Superfund) ASCII Text Format - CPAD Database

    Data.gov (United States)

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

  11. Superfund Site Information - Site Sampling Data

    Data.gov (United States)

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

  12. Construction of a technique plan repository and evaluation system based on AHP group decision-making for emergency treatment and disposal in chemical pollution accidents

    Energy Technology Data Exchange (ETDEWEB)

    Shi, Shenggang [College of Environmental Science and Engineering, Beijing Forestry University, Beijing 100083 (China); College of Chemistry, Baotou Teachers’ College, Baotou 014030 (China); Cao, Jingcan; Feng, Li; Liang, Wenyan [College of Environmental Science and Engineering, Beijing Forestry University, Beijing 100083 (China); Zhang, Liqiu, E-mail: zhangliqiu@163.com [College of Environmental Science and Engineering, Beijing Forestry University, Beijing 100083 (China)

    2014-07-15

    Highlights: • Different chemical pollution accidents were simplified using the event tree analysis. • Emergency disposal technique plan repository of chemicals accidents was constructed. • The technique evaluation index system of chemicals accidents disposal was developed. • A combination of group decision and analytical hierarchy process (AHP) was employed. • Group decision introducing similarity and diversity factor was used for data analysis. - Abstract: The environmental pollution resulting from chemical accidents has caused increasingly serious concerns. Therefore, it is very important to be able to determine in advance the appropriate emergency treatment and disposal technology for different types of chemical accidents. However, the formulation of an emergency plan for chemical pollution accidents is considerably difficult due to the substantial uncertainty and complexity of such accidents. This paper explains how the event tree method was used to create 54 different scenarios for chemical pollution accidents, based on the polluted medium, dangerous characteristics and properties of chemicals involved. For each type of chemical accident, feasible emergency treatment and disposal technology schemes were established, considering the areas of pollution source control, pollutant non-proliferation, contaminant elimination and waste disposal. Meanwhile, in order to obtain the optimum emergency disposal technology schemes as soon as the chemical pollution accident occurs from the plan repository, the technique evaluation index system was developed based on group decision-improved analytical hierarchy process (AHP), and has been tested by using a sudden aniline pollution accident that occurred in a river in December 2012.

  13. Development of biological and chemical methods for environmental monitoring of DOE waste disposal and storage facilities. Final report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1989-04-01

    Hazardous chemicals in the environment have received ever increasing attention in recent years. In response to ongoing problems with hazardous waste management, Congress enacted the Resource Conservation and Recovery Act (RCRA) in 1976. In 1980, Congress adopted the Comprehensive Environmental Response Compensation, and Liability Act (CERCLA), commonly called Superfund to provide for emergency spill response and to clean up closed or inactive hazardous waste sites. Scientists and engineers have begun to respond to the hazardous waste challenge with research and development on treatment of waste streams as well as cleanup of polluted areas. The magnitude of the problem is just now beginning to be understood. The U.S. Environmental Protection Agency (USEPA) National Priorities List as of September 13 1985, contained 318 proposed sites and 541 final sites (USEPA, 1985). Estimates of up to 30,000 sites containing hazardous wastes (1,200 to 2,000 of which present a serious threat to public health) have been made (Public Law 96-150). In addition to the large number of sites, the costs of cleanup using available technology are phenomenal. For example, a 10-acre toxic waste site in Ohio is to be cleaned up by removing chemicals from the site and treating the contaminated groundwater. The federal government has already spent more than $7 million to remove the most hazardous wastes and the groundwater decontamination alone is expected to take at least 10 years and cost $12 million. Another example of cleanup costs comes from the State of California Commission for Economic Development which predicts a bright economic future for the state except for the potential outlay of $40 billion for hazardous waste cleanup mandated by federal and state laws.

  14. A functional on-chip pressure generator using solid chemical propellant for disposable lab-on-a-chip.

    Science.gov (United States)

    Hong, Chien-Chong; Murugesan, Suresh; Kim, Sanghyo; Beaucage, Gregory; Choi, Jin-Woo; Ahn, Chong H

    2003-11-01

    This paper presents a functional on-chip pressure generator that utilizes chemical energy from a solid chemical propellant to perform fluidic delivery in applications of plastic-based disposable biochips or lab-on-a-chip systems. In this functional on-chip pressure generator, azobis-isobutyronitrile (AIBN) as the solid chemical propellant is deposited on a microheater using a screen-printing technique, which can heat the AIBN at 70 degrees C to produce nitrogen gas. The output pressure of nitrogen gas, generated from the solid chemical propellant, is adjustable to a desired pressure by controlling the input power of the heater. Using this chemical energy source, the generated pressure depends on the deposited amount of the solid chemical propellant and the temperature of the microheater. Experimental measurements show that this functional on-chip pressure generator can achieve around 3 000 Pa pressure when 189 mJ of energy is applied to heat the 100 microg of AIBN. This pressure can drive 50 nl of water through a microfluidic channel of 70 mm and cross-sectional area of 100 microm x 50 microm. Due to its compact size, ease of fabrication and integration, high reliability (no moving parts), biologically inert gas output along with functionality of gas generation, this pressure generator will be an excellent pressure source for handling the fluids of disposable lab-on-a-chip, biochemical analysis systems or drug delivery systems.

  15. Research on the transformation of nitrate due to its chemical interaction with metals in TRU waste disposal environment

    International Nuclear Information System (INIS)

    Some TRU wastes contain nitrate ions as salt. The nitrate ions might transform into NO2- and NH3, etc. in the disposal site environment because of reducing agent such as metals, possibly changing disposal site environment or affecting nuclide migration parameters. Therefore, we investigated of chemical interaction between NO3- and metals in a low oxygen environment that corresponds to the disposal site environment. (1) The reaction rate constant between carbon steel and NO3- in an environment with low oxygen and high pH underground water was obtained through electrochemical tests. (2) The long-term data on the products (NH3,H2, etc.) of reaction between metals (carbon steel, stainless steel, zircaloy) and NO3- was obtained through immersion tests in an environment with low oxygen and high pH underground water. According to the long-term data of [NO3-], [NO2-] and [NH3], it was considered that reducing reaction of nitrate was consecutive reaction (NO3- → NO2- → NH3). (3) The decomposition and transition behavior of No3- around disposal facilities evaluated, using the geochemical code (PHREEQM-2D), which have considered geochemical reaction based on experimental results. (author)

  16. Chemical and biological warfare: Protection, decontamination, and disposal. (Latest citations from the NTIS bibliographic database). Published Search

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-11-01

    The bibliography contains citations concerning the means to defend against chemical and biological agents used in military operations, and to eliminate the effects of such agents on personnel, equipment, and grounds. Protection is accomplished through protective clothing and masks, and in buildings and shelters through filtration. Elimination of effects includes decontamination and removal of the agents from clothing, equipment, buildings, grounds, and water, using chemical deactivation, incineration, and controlled disposal of material in injection wells and ocean dumping. Other Published Searches in this series cover chemical warfare detection; defoliants; general studies; biochemistry and therapy; and biology, chemistry, and toxicology associated with chemical warfare agents.(Contains 50-250 citations and includes a subject term index and title list.) (Copyright NERAC, Inc. 1995)

  17. Chemical and biological warfare: Protection, decontamination, and disposal. (Latest citations from the NTIS bibliographic database). Published Search

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-10-01

    The bibliography contains citations concerning the means to defend against chemical and biological agents used in military operations, and to eliminate the effects of such agents on personnel, equipment, and grounds. Protection is accomplished through protective clothing and masks, and in buildings and shelters through filtration. Elimination of effects includes decontamination and removal of the agents from clothing, equipment, buildings, grounds, and water, using chemical deactivation, incineration, and controlled disposal of material in injection wells and ocean dumping. Other Published Searches in this series cover chemical warfare detection; defoliants; general studies; biochemistry and therapy; and biology, chemistry, and toxicology associated with chemical warfare agents. (Contains 50-250 citations and includes a subject term index and title list.) (Copyright NERAC, Inc. 1995)

  18. Evaluation of improved chemical waste disposal and recovery methods for N reactor fuel fabrication operations: 1984 annual report

    International Nuclear Information System (INIS)

    Pacific Northwest Laboratory personnel identified and evaluated alternative methods for recovery, recycle, and disposal of waste acids produced during N Reactor fuel operations. This work was conducted under a program sponsored by UNC Nuclear Industries, Inc.; the program goals were to reduce the volume of liquid waste by rejuvenating and recycling acid solutions and to generate a residual waste low in nitrates, fluorides, and metals. Disposal methods under consideration included nitric acid reclamation, grout encapsulation of final residual waste, nitrogen fertilizer production, biodenitrifaction, chemical or thermal destruction of NO3, and short-term impoundment of liquid NO3/SO4 wastes. Preliminary testing indicated that the most feasible and practicable of these alternatives were (1) nitric acid reclamation followed by grouting of residual waste and (2) nitrogen fertilizer production. This report summarizes the investigations, findings, and recommendations for the 1984 fiscal year

  19. Field application of the Numobag as a portable disposable isolation unit and for treating chemical, radiological or biologically induced wounds.

    Energy Technology Data Exchange (ETDEWEB)

    Miller, Keith A.; Felton, Robert; Vaughan, Courtenay Thomas

    2005-04-01

    Numotech Inc. has developed the Numobag{trademark}, a disposable, lightweight, wound healing device which produces Topical Hyperbaric Oxygen Therapy (THOT). The Numobag{trademark} is cost effective and has been clinically validated to heal large skin lesions rapidly and has proven to arrest wound advancement from several insidious forms of biological attack including dermal anthrax, small pox, necrotizing fasciitis etc. The Numobag{trademark} can treat mass casualties wounded by chemical/radiological burns or damaging biological exposures. The Numobag{trademark} can be a frontline tool as an isolation unit, reducing cross-contamination and infection of medical personnel. The heightened oxygen content kills organisms on the skin and in the wound, avoids expensive hospital trash disposal procedures, and helps the flesh heal. The Numobag{trademark} requires high purity oxygen. Numotech Inc. is teaming with Sandia National Laboratories and Spektr Conversion in Russia to develop a cost effective, portable, low power oxygen generator.

  20. Research requirements for a unified approach to modelling chemical effects associated with radioactive waste disposal

    International Nuclear Information System (INIS)

    This report contains the results of a review of the current modelling, laboratory experiments and field experiments being conducted in the United Kingdom to aid understanding and improve prediction of the effects of chemistry on the disposal of radioactive wastes. The aim has been to summarise present work and derive a structure for future research effort that would support the use of probabilistic risk assessment (pra) methods for the disposal of radioactive wastes. The review was conducted by a combination of letter and personal visits, and preliminary results were reported to a plenary meeting of participants held in April, 1986. Following this meeting, copies of the report were circulated to participants at draft stage, so that the finalised report should be taken to provide as far as possible a consensus of opinion of research requirements. (author)

  1. Solid waste disposal in the soil: effects on the physical, chemical, and organic properties of soil

    OpenAIRE

    Vanessa Regina Lasaro Mangieri; João Tavares Filho

    2015-01-01

    Currently, there is growing concern over the final destination of the solid waste generated by society. Landfills should not be considered the endpoint for substances contained or generated in solid waste. The sustainable use of natural resources, especially soil and water, has become relevant, given the increase in anthropogenic activities. Agricultural use is an alternative to solid waste (leachate, biosolid) disposal, considering the hypothesis that the agricultural use of waste is promisi...

  2. Superfund and Toxic Release Inventory Sites - SUPERFUND_IDEM_IN: Superfund Program Facilities in Indiana (Indiana Department of Environmental Management, Point Shapefile)

    Data.gov (United States)

    NSGIC GIS Inventory (aka Ramona) — SUPERFUND_IDEM_IN is a point shapefile that contains GPS-located Superfund Program facility locations in Indiana, provided by personnel of Indiana Department of...

  3. Chemical Stockpile Disposal Program: Review and comment on the Phase 1 environmental report for the Pueblo Depot Activity, Pueblo, Colorado

    Energy Technology Data Exchange (ETDEWEB)

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

    1994-03-01

    As part of the Chemical Stockpile Disposal Program, an independent review is presented of the US Army Phase I environmental report for the disposal of chemical agents and munitions stored at the Pueblo Depot Activity (PUDA) in Pueblo, Colorado. The Phase I report addresses new and additional concerns not incorporated in the final programmatic environmental impact statement (FPEIS). These concerns are addressed by examining site-specific data for the PUDA. On the basis of our review of the Phase I report, we concluded that on-site meteorological data from December 1988 to June 1992 appear to be of insufficient quality to have been used instead of the off-site Pueblo airport data. No additional meteorological data have been collected since June 1992. The Phase I report briefly mentions problems with the air pollution control system. These problems will likely require the systems to be upgraded at the Johnston Atoll site and at each of the other depots in the continental United States. Without such improvements, the probability of accidents during start-up and shutdown would likely increase. The Army has a lessons-learned program to incorporate improvements into the design of future facilities. The Phase I report does not make any design change commitments. These issues need to be fully evaluated and resolved before any final conclusion concerning the adequacy of the decision in the FPEIS can be made with respect to the PUDA. With the exception of this issue, the inclusion of other more detailed site-specific data in the Phase I report does not change the decision reached in the FPEIS (which favored on-site disposal at the PUDA). We recommend that site-specific data on water, ecological, socioeconomic, and cultural resources and emergency planning and preparedness be considered explicitly in the site-specific EIS decision-making process.

  4. Chemical Stockpile Disposal Program: Review and comment on the Phase 1 environmental report for the Pueblo Depot Activity, Pueblo, Colorado

    International Nuclear Information System (INIS)

    As part of the Chemical Stockpile Disposal Program, an independent review is presented of the US Army Phase I environmental report for the disposal of chemical agents and munitions stored at the Pueblo Depot Activity (PUDA) in Pueblo, Colorado. The Phase I report addresses new and additional concerns not incorporated in the final programmatic environmental impact statement (FPEIS). These concerns are addressed by examining site-specific data for the PUDA. On the basis of our review of the Phase I report, we concluded that on-site meteorological data from December 1988 to June 1992 appear to be of insufficient quality to have been used instead of the off-site Pueblo airport data. No additional meteorological data have been collected since June 1992. The Phase I report briefly mentions problems with the air pollution control system. These problems will likely require the systems to be upgraded at the Johnston Atoll site and at each of the other depots in the continental United States. Without such improvements, the probability of accidents during start-up and shutdown would likely increase. The Army has a lessons-learned program to incorporate improvements into the design of future facilities. The Phase I report does not make any design change commitments. These issues need to be fully evaluated and resolved before any final conclusion concerning the adequacy of the decision in the FPEIS can be made with respect to the PUDA. With the exception of this issue, the inclusion of other more detailed site-specific data in the Phase I report does not change the decision reached in the FPEIS (which favored on-site disposal at the PUDA). We recommend that site-specific data on water, ecological, socioeconomic, and cultural resources and emergency planning and preparedness be considered explicitly in the site-specific EIS decision-making process

  5. Superfund National Priority List (NPL) Site Boundaries

    Data.gov (United States)

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

  6. Construction of a technique plan repository and evaluation system based on AHP group decision-making for emergency treatment and disposal in chemical pollution accidents.

    Science.gov (United States)

    Shi, Shenggang; Cao, Jingcan; Feng, Li; Liang, Wenyan; Zhang, Liqiu

    2014-07-15

    The environmental pollution resulting from chemical accidents has caused increasingly serious concerns. Therefore, it is very important to be able to determine in advance the appropriate emergency treatment and disposal technology for different types of chemical accidents. However, the formulation of an emergency plan for chemical pollution accidents is considerably difficult due to the substantial uncertainty and complexity of such accidents. This paper explains how the event tree method was used to create 54 different scenarios for chemical pollution accidents, based on the polluted medium, dangerous characteristics and properties of chemicals involved. For each type of chemical accident, feasible emergency treatment and disposal technology schemes were established, considering the areas of pollution source control, pollutant non-proliferation, contaminant elimination and waste disposal. Meanwhile, in order to obtain the optimum emergency disposal technology schemes as soon as the chemical pollution accident occurs from the plan repository, the technique evaluation index system was developed based on group decision-improved analytical hierarchy process (AHP), and has been tested by using a sudden aniline pollution accident that occurred in a river in December 2012. PMID:24887122

  7. Occurrence and possible sources of arsenic in seafloor sediments surrounding sea-disposed munitions and chemical agents near O´ahu, Hawai´i

    Science.gov (United States)

    Tomlinson, Michael S.; De Carlo, Eric Heinen

    2016-06-01

    The Department of Defense disposed of conventional and chemical munitions as well as bulk containers of chemical agents in US coastal waters including those surrounding the State of Hawai´i. The Hawai´i Undersea Military Munitions Assessment has been collecting biota, water, and sediment samples from two disposal areas south of the island of O´ahu in waters 500 to 600 m deep known to have received both conventional munitions and chemical agents (specifically sulfur mustard). Unlike a number of other sea-disposed munitions investigations which used grabs or corers lowered from surface vessels, we used manned submersibles to collect the samples. Using this approach, we were able to visually identify the munitions and precisely locate our samples in relation to the munitions on the seafloor. This paper focuses on the occurrence and possible sources of arsenic found in the sediments surrounding the disposed military munitions and chemical agents. Using nonparametric multivariate statistical techniques, we looked for patterns in the chemical data obtained from these sediment samples in order to determine the possible sources of the arsenic found in these sediments. The results of the ordination technique nonmetric multidimensional scaling indicate that the arsenic is associated with terrestrial sources and not munitions. This was not altogether surprising given that: (1) the chemical agents disposed of in this area supposedly did not contain arsenic, and (2) the disposal areas studied were under terrestrial influence or served as dredge spoil disposal sites. The sediment arsenic concentrations during this investigation ranged from <1.3 to 40 mg/kg-dry weight with the lower concentrations typically found around control sites and munitions (not located in dredge disposal areas) and the higher values found at dredge disposal sites (with or without munitions). During the course of our investigation we did, however, discover that mercury appears to be loosely associated

  8. Natural weathering in dry disposed ash dump: Insight from chemical, mineralogical and geochemical analysis of fresh and unsaturated drilled cores.

    Science.gov (United States)

    Akinyemi, S A; Akinlua, A; Gitari, W M; Khuse, N; Eze, P; Akinyeye, R O; Petrik, L F

    2012-07-15

    Some existing alternative applications of coal fly ash such as cement manufacturing; road construction; landfill; and concrete and waste stabilisation use fresh ash directly collected from coal-fired power generating stations. Thus, if the rate of usage continues, the demand for fresh ash for various applications will exceed supply and use of weathered dry disposed ash will become necessary alternative. As a result it's imperative to understand the chemistry and pH behaviour of some metals inherent in dry disposed fly ash. The bulk chemical composition as determined by XRF analysis showed that SiO2, Al2O3 and Fe2O3 were the major oxides in fresh ash and unsaturated weathered ashes. The unsaturated weathered ashes are relatively depleted in CaO, Fe2O3, TiO2, SiO2, Na2O and P2O5 due to dissolution and hydrolysis caused by chemical interaction with ingressing CO2 from the atmosphere and infiltrating rain water. Observed accumulations of Fe2O3, TiO2, CaO, K2O, Na2O and SO3 and Zn, Zr, Sr, Pb, Ni, Cr and Co in the lower layers indicate progressive downward movement through the ash dump though at a slow rate. The bulk mineralogy of unsaturated weathered dry disposed ash, as determined by XRD analysis, revealed quartz and mullite as the major crystalline phases; while anorthite, hematite, enstatite, lime, calcite, and mica were present as minor mineral phases. Pore water chemistry revealed a low concentration of readily soluble metals in unsaturated weathered ashes in comparison with fresh ash, which shows high leachability. This suggests that over time the precipitation of transient minor secondary mineral phases; such as calcite and mica might retard residual metal release from unsaturated weathered ash. Chloride and sulphate species of the water soluble extracts of weathered ash are at equilibrium with Na+ and K+; these demonstrate progressive leaching over time and become supersaturated at the base of unsaturated weathered ash. This suggests that the ash dump does not

  9. Chemical stability and adsorption of succinylcholine chloride injections in disposable plastic syringes.

    Science.gov (United States)

    Pramar, Y V; Moniz, D; Hobbs, D

    1994-06-01

    The purpose of these investigations was to determine the stability and adsorption behaviour of succinylcholine chloride (SCC) when stored in plastic syringes. Drug degradation was monitored using the USP high-pressure liquid chromatography method. Solutions containing 20 mg/ml of SCC in 5% dextrose, and in normal saline, were studied at 5, 25 and 40 degrees C. The hydrolysis of SCC in i.v. fluids followed apparent zero-order kinetics. The manufacturer's recommended expiry period was found to be too conservative. If protected from light, storage at room temperature for up to 3 months can be safely recommended, without significant loss of chemical stability. However, microbiological quality assurance will need to be implemented and an appropriate shelf-life assigned on the basis of both microbiological and chemical stability data. PMID:7962223

  10. Treatment and disposal of steam generator and heat exchanger chemical cleaning wastes

    International Nuclear Information System (INIS)

    Wet air oxidation was effective in reducing the organic loading of Ontario Hydro's EDTA-based steam generator cleaning wastes and the organic acid formulation used for heat exchanger chemical cleaning. Destruction of the complexing agents resulted in direct precipitation of iron from the waste steam generator magnetite solvent and from the heat exchanger cleaning waste. The oxidized liquors contain lower molecular weight organic acids, ammonia and amines, suitable for secondary biological treatment. The oxidized copper waste requires further treatment to reduce dissolved copper levels prior to biological digestion. A preliminary evaluation of UV and ozone degradation of these wastes showed less promise than wet air oxidation. 24 refs., 1 fig., 4 tabs

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

    Data.gov (United States)

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

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

    Data.gov (United States)

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

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

    Data.gov (United States)

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

  14. Assessing Worker and Environmental Chemical Exposure Risks at an e-Waste Recycling and Disposal Site in Accra, Ghana

    Directory of Open Access Journals (Sweden)

    Jack Caravanos

    2011-01-01

    Conclusions. The Agbogbloshie e-waste recycling/disposal site in Accra, Ghana revealed an area with extensive lead contamination in both ambient air and topsoil. Given the urban nature of this site e as well as the large adjacent food distribution market, the potential for human health impact is substantial both to workers and local residents.

  15. Investigations of Near-Field Thermal-Hydrologic-Mechanical-Chemical Models for Radioactive Waste Disposal in Clay/Shale Rock

    International Nuclear Information System (INIS)

    Clay/shale has been considered as potential host rock for geological disposal of high-level radioactive waste throughout the world, because of its low permeability, low diffusion coefficient, high retention capacity for radionuclides, and capability to self-seal fractures. For example, Callovo-Oxfordian argillites at the Bure site, France (Fouche et al., 2004), Toarcian argillites at the Tournemire site, France (Patriarche et al., 2004), Opalinus Clay at the Mont Terri site, Switzerland (Meier et al., 2000), and Boom clay at the Mol site, Belgium (Barnichon and Volckaert, 2003) have all been under intensive scientific investigation (at both field and laboratory scales) for understanding a variety of rock properties and their relationships to flow and transport processes associated with geological disposal of radioactive waste. Figure 1-1 presents the distribution of clay/shale formations within the USA.

  16. Investigations of Near-Field Thermal-Hydrologic-Mechanical-Chemical Models for Radioactive Waste Disposal in Clay/Shale Rock

    Energy Technology Data Exchange (ETDEWEB)

    Liu, H.H.; Li, L.; Zheng, L.; Houseworth, J.E.; Rutqvist, J.

    2011-06-20

    Clay/shale has been considered as potential host rock for geological disposal of high-level radioactive waste throughout the world, because of its low permeability, low diffusion coefficient, high retention capacity for radionuclides, and capability to self-seal fractures. For example, Callovo-Oxfordian argillites at the Bure site, France (Fouche et al., 2004), Toarcian argillites at the Tournemire site, France (Patriarche et al., 2004), Opalinus Clay at the Mont Terri site, Switzerland (Meier et al., 2000), and Boom clay at the Mol site, Belgium (Barnichon and Volckaert, 2003) have all been under intensive scientific investigation (at both field and laboratory scales) for understanding a variety of rock properties and their relationships to flow and transport processes associated with geological disposal of radioactive waste. Figure 1-1 presents the distribution of clay/shale formations within the USA.

  17. Hazardous chemical tracking system (HAZ-TRAC)

    Energy Technology Data Exchange (ETDEWEB)

    Bramlette, J D; Ewart, S M; Jones, C E

    1990-07-01

    Westinghouse Idaho Nuclear Company, Inc. (WINCO) developed and implemented a computerized hazardous chemical tracking system, referred to as Haz-Trac, for use at the Idaho Chemical Processing Plant (ICPP). Haz-Trac is designed to provide a means to improve the accuracy and reliability of chemical information, which enhances the overall quality and safety of ICPP operations. The system tracks all chemicals and chemical components from the time they enter the ICPP until the chemical changes form, is used, or becomes a waste. The system runs on a Hewlett-Packard (HP) 3000 Series 70 computer. The system is written in COBOL and uses VIEW/3000, TurboIMAGE/DBMS 3000, OMNIDEX, and SPEEDWARE. The HP 3000 may be accessed throughout the ICPP, and from remote locations, using data communication lines. Haz-Trac went into production in October, 1989. Currently, over 1910 chemicals and chemical components are tracked on the system. More than 2500 personnel hours were saved during the first six months of operation. Cost savings have been realized by reducing the time needed to collect and compile reporting information, identifying and disposing of unneeded chemicals, and eliminating duplicate inventories. Haz-Trac maintains information required by the Superfund Amendment Reauthorization Act (SARA), the Comprehensive Environmental Response, Compensation and Liability Act (CERCLA) and the Occupational Safety and Health Administration (OSHA).

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1994-07-01

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

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

    International Nuclear Information System (INIS)

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

  20. Halomonhystera disjuncta - a young-carrying nematode first observed for the Baltic Sea in deep basins within chemical munitions disposal sites

    Science.gov (United States)

    Grzelak, Katarzyna; Kotwicki, Lech

    2016-06-01

    Three deep basins in the Baltic Sea were investigated within the framework of the CHEMSEA project (Chemical Munitions Search & Assessment), which aims to evaluate the ecological impact of chemical warfare agents dumped after World War II. Nematode communities, which comprise the most numerous and diverse organisms in the surveyed areas, were investigated as a key group of benthic fauna. One of the most successful nematode species was morphologically identified as Halomonhystera disjuncta (Bastian, 1865). The presence of this species, which is an active coloniser that is highly resistant to disturbed environments, may indicate that the sediments of these disposal sites are characterised by toxic conditions that are unfavourable for other metazoans. Moreover, ovoviviparous reproductive behaviour in which parents carry their brood internally, which is an important adaptation to harsh environmental conditions, was observed for specimens from Gdansk Deep and Gotland Deep. This reproductive strategy, which is uncommon for marine nematodes, has not previously been reported for nematodes from the Baltic Sea sediment.

  1. Physico-chemical characterization of clays at Kalpakkam nuclear plant site towards assessment of radioactive waste disposal

    International Nuclear Information System (INIS)

    Highlights: → Colloidal clay particles in groundwater have the potential to transport radionuclides in the ground environment. → Transport of radionuclides through groundwater depends on the nature of the clay colloids and its zeta potential. → The low CEC value of the kaolinite clay colloids ensures reduced potential for transport of radionuclides. → The low cation exchange capacity of the clay mineral in the study area emphasizes the requirement of suitable backfill materials around disposal facilities. - Abstract: In order to evaluate the safety of a radioactive waste repository in a geological formation, it is necessary to study the prevailing sub surface geology surrounding the disposal facility. The Kalpakkam subsurface was found to comprise of charnockite/hypersthene granite which is overlain by clay, sandy clay and sand. Clays can act as a barrier for groundwater flow and attenuate radionuclide migration. Accordingly, in the present study, clay samples were collected at chosen depths in the subsurface within the study area at Kalpakkam and colloidal clay fractions were separated. The clay colloids after separation were characterized for their size, shape, morphology, elemental composition and zeta potential. Photon correlation spectroscopy, scanning electron microscopy, energy dispersive X-ray analysis, X-ray diffraction technique and zetasizer were used to characterize the colloidal particles. The detailed characterization and analysis has revealed that the major clay mineral present in the subsurface at Kalpakkam is kaolinite. Minor quantities of smectite and illite were also identified in some clay samples. It was observed that the clays present in the study area are having low cation exchange capacity for radionuclides and emphasizes the requirement of proper backfill materials around disposal facilities for retardation of radionuclide migration. The occurrence of clay minerals at depths within the aquifer thickness warrants analysis of

  2. PERSONNEL PROTECTION THROUGH RECONNAISSANCE ROBOTICS AT SUPERFUND REMEDIAL SITES

    Science.gov (United States)

    Investigation, mitigation, and clean-up of hazardous materials at Superfund sites normally require on-site workers to perform hazardous and sometimes potentially dangerous functions. uch functions include site surveys and the reconnaissance for airborne and buried toxic environme...

  3. Request for interim approval to operate Trench 94 of the 218-E-12B Burial Ground as a chemical waste landfill for disposal of polychlorinated biphenyl waste in submarine reactor compartments. Revision 2

    Energy Technology Data Exchange (ETDEWEB)

    Cummins, G.D.

    1994-06-01

    This request is submitted to seek interim approval to operate a Toxic Substances Control Act (TSCA) of 1976 chemical waste landfill for the disposal of polychlorinated biphenyl (PCB) waste. Operation of a chemical waste landfill for disposal of PCB waste is subject to the TSCA regulations of 40 CFR 761. Interim approval is requested for a period not to exceed 5 years from the date of approval. This request covers only the disposal of small 10 quantities of solid PCB waste contained in decommissioned, defueled submarine reactor compartments (SRC). In addition, the request applies only to disposal 12 of this waste in Trench 94 of the 218-E-12B Burial Ground (Trench 94) in the 13 200 East Area of the US Department of Energy`s (DOE) Hanford Facility. Disposal of this waste will be conducted in accordance with the Compliance 15 Agreement (Appendix H) between the DOE Richland Operations Office (DOE-RL) and 16 the US Environmental Protection Agency (EPA), Region 10. During the 5-year interim approval period, the DOE-RL will submit an application seeking final 18 approval for operation of Trench 94 as a chemical waste landfill, including 19 any necessary waivers, and also will seek a final dangerous waste permit from 20 the Washington State Department of Ecology (Ecology) for disposal of lead 21 shielding contained in the SRCS.

  4. Request for interim approval to operate Trench 94 of the 218-E-12B Burial Ground as a chemical waste landfill for disposal of polychlorinated biphenyl waste in submarine reactor compartments

    International Nuclear Information System (INIS)

    This request is submitted to seek interim approval to operate a Toxic Substances Control Act (TSCA) of 1976 chemical waste landfill for the disposal of polychlorinated biphenyl (PCB) waste. Operation of a chemical waste landfill for disposal of PCB waste is subject to the TSCA regulations of 40 CFR 761. Interim approval is requested for a period not to exceed 5 years from the date of approval. This request covers only the disposal of small 10 quantities of solid PCB waste contained in decommissioned, defueled submarine reactor compartments (SRC). In addition, the request applies only to disposal 12 of this waste in Trench 94 of the 218-E-12B Burial Ground (Trench 94) in the 13 200 East Area of the US Department of Energy's (DOE) Hanford Facility. Disposal of this waste will be conducted in accordance with the Compliance 15 Agreement (Appendix H) between the DOE Richland Operations Office (DOE-RL) and 16 the US Environmental Protection Agency (EPA), Region 10. During the 5-year interim approval period, the DOE-RL will submit an application seeking final 18 approval for operation of Trench 94 as a chemical waste landfill, including 19 any necessary waivers, and also will seek a final dangerous waste permit from 20 the Washington State Department of Ecology (Ecology) for disposal of lead 21 shielding contained in the SRCS

  5. Geological Disposal of Nuclear Waste: Investigating the Thermo-Hygro-Mechanical-Chemical (THMC) Coupled Processes at the Waste Canister- Bentonite Barrier Interface

    Science.gov (United States)

    Davies, C. W.; Davie, D. C.; Charles, D. A.

    2015-12-01

    Geological disposal of nuclear waste is being increasingly considered to deal with the growing volume of waste resulting from the nuclear legacy of numerous nations. Within the UK there is 650,000 cubic meters of waste safely stored and managed in near-surface interim facilities but with no conclusive permanent disposal route. A Geological Disposal Facility with incorporated Engineered Barrier Systems are currently being considered as a permanent waste management solution (Fig.1). This research focuses on the EBS bentonite buffer/waste canister interface, and experimentally replicates key environmental phases that would occur after canister emplacement. This progresses understanding of the temporal evolution of the EBS and the associated impact on its engineering, mineralogical and physicochemical state and considers any consequences for the EBS safety functions of containment and isolation. Correlation of engineering properties to the physicochemical state is the focus of this research. Changes to geotechnical properties such as Atterberg limits, swelling pressure and swelling kinetics are measured after laboratory exposure to THMC variables from interface and batch experiments. Factors affecting the barrier, post closure, include corrosion product interaction, precipitation of silica, near-field chemical environment, groundwater salinity and temperature. Results show that increasing groundwater salinity has a direct impact on the buffer, reducing swelling capacity and plasticity index by up to 80%. Similarly, thermal loading reduces swelling capacity by 23% and plasticity index by 5%. Bentonite/steel interaction studies show corrosion precipitates diffusing into compacted bentonite up to 3mm from the interface over a 4 month exposure (increasing with temperature), with reduction in swelling capacity in the affected zone, probably due to the development of poorly crystalline iron oxides. These results indicate that groundwater conditions, temperature and corrosion

  6. "Cut holes and sink 'em": chemical weapons disposal and cold war history as a history of risk

    OpenAIRE

    Müller, Simone

    2016-01-01

    Using the incident of the scuttling of the USS Le Baron Russell Briggs, loaded with roughly 22,000 tons of outdated chemical weapons in 1970, this contribution extrapolates how, why, and when in the United States chemical weapons that had been produced as the ultimate answer to the risk of nuclear war became reframed as a risk themselves. The analysis settles on how questions of knowing and not-knowing about potentialities of future events influenced these re-negotiation processes between the...

  7. Remedial design services for Montclair/West Orange and Glen Ridge Superfund sites

    International Nuclear Information System (INIS)

    The Montclair/West Orange and Glen Ridge Superfund Sites are located 12 miles west of New York City in Essex County, New Jersey. The sites are contaminated with waste materials from radium-processing facilities which operated in the area during the early 1900's. The waste materials, containing radium and other radioactive isotopes were placed in three separate landfill sites. Major public health risks are indoor radon gas build-up and indoor/ outdoor gamma radiation. In 1989, the EPA issued a Record of Decision (ROD) which chose excavation and off-site disposal of material as the preferred alternative. The purpose of this presentation is to highlight key elements of the design process for the remedial action at Montclair. Those key elements are as follows: meeting community relations challenges; measuring radioactive contamination; developing plans and specifications; packaging of remedial action contacts; and continually improving both the process and the designs

  8. Contaminant accumulation and biomarker responses in caged mussels, Mytilus galloprovincialis, to evaluate bioavailability and toxicological effects of remobilized chemicals during dredging and disposal operations in harbour areas

    Energy Technology Data Exchange (ETDEWEB)

    Bocchetti, Raffaella; Fattorini, Daniele; Pisanelli, Barbara [Istituto di Biologia e Genetica, Universita Politecnica delle Marche, Via Ranieri Monte d' Ago, 60100 Ancona (Italy); Macchia, Simona; Oliviero, Lisa; Pilato, Fabiano; Pellegrini, David [Istituto Centrale per la Ricerca Scientifica e Tecnologica Applicata al Mare (ICRAM), Viale Nazario Sauro 4, 57128 Livorno (Italy); Regoli, Francesco [Istituto di Biologia e Genetica, Universita Politecnica delle Marche, Via Ranieri Monte d' Ago, 60100 Ancona (Italy)], E-mail: f.regoli@univpm.it

    2008-09-29

    Remobilization of chemicals from contaminated sediments is a major risk associated with dredging and disposal operations in harbour areas. In this work caged mussels, Mytilus galloprovincialis, were chosen as bioindicator organisms to reveal the impact and recovery of organisms from these activities in the harbour of Piombino (Tuscany, Italy) where approximately 100,000 m{sup 3} of sediments were removed and disposed in a local confined disposal facility (CDF). Organisms were deployed before, during and after the end of operations, selecting sites differently impacted by these activities. Temporal changes in environmental bioavailability and biological effects of pollutants were assessed by integrating analyses of trace metals and polycyclic aromatic hydrocarbons (PAHs) accumulated in tissues of caged mussels with a wide array of biomarkers reflecting exposure to specific classes of pollutants and different levels of cellular unbalance or toxicity. Such biological responses included levels of metallothioneins, activity of acyl CoA oxidase (AOX) as a marker of peroxisome proliferation, oxidative stress biomarkers (content of glutathione, enzymatic activities of catalase, glutathione S-transferases, glutathione reductase, glutathione peroxidases), total oxyradical scavenging capacity (TOSC) toward peroxyl and hydroxyl radicals, lysosomal membrane stability and genotoxic effects measured as DNA strand breaks and frequency of micronuclei. Obtained results indicated that a general disturbance was already present in the whole harbour area and especially in the inner site before the beginning of operations, when caged mussels exhibited a significant accumulation of PAHs and Pb, lower TOSC values and higher levels of both lysosomal and genotoxic damages. Bioavailability of trace metals and PAHs markedly increased during dredging activities with values up to 40 {mu}g/g for Pb and up to 2200 ng/g for PAHs in tissues of caged mussels, a significant inhibition of antioxidant

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

    Data.gov (United States)

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

  10. Chemical decomposition of high-level nuclear waste storage/disposal glasses under irradiation. 1998 annual progress report

    International Nuclear Information System (INIS)

    'The objective of this project is to employ the technique of electron spin resonance (ESR), in conjunction with other experimental methods, to study radiation-induced decomposition of vitreous compositions proposed for immobilization/disposal of high-level nuclear wastes (HLW) or excess weapons plutonium. ESR is capable of identifying, even at the parts-per-million level, displaced atoms, ruptured bonds, and free radicals created by radiation in such glassy forms. For example, one of the scientific goals is to determine whether ESR-detectable superoxide (O2-) and ozonide (O3-) ions are precursors of radiation-induced oxygen gas bubbles reported by other investigators. The fundamental understandings obtained in this study will enable reliable predictions of the long-term effects of and decays of the immobilized radionuclides on HLW glasses. This report represents the results of an 18-month effort performed under a 3-year research award. Four categories of materials were studied: (1) several actual and proposed HLW glass compositions fabricated at Savannah River Technology Center (SRTC), samples of which had been irradiated to a dose of 30 MGy (1 Gy = 100 rad) to simulate decay effects, (2) several high-iron phosphate glasses fabricated at the University of Missouri-Rolla (UMR), (3) one other model HLW glass and several simulated natural glasses which had been implanted with 160-keV He+ ions to simulate-decay damage, and (4) an actual geological glass damaged by decays of trace amounts of contained 238U and 232Th over a period of 65 Myears. Among the category-1 materials were two samples of Defense Waste Processing Facility (DWPF) borosilicate glasses modeling compositions currently being used to vitrify HLW at SRTC. The ESR spectra recorded for the unirradiated DWPF-glass simulants were attributable to Fe 3+ ions. The 30-MGy irradiation was found to change the Fe3+ concentration of these glasses by a statistically insignificant factor (0.987 261 0.050) and not to

  11. Chemical decomposition of high-level nuclear waste storage/disposal glasses under irradiation. 1998 annual progress report

    Energy Technology Data Exchange (ETDEWEB)

    Griscom, D.L.; Merzbacher, C.I.

    1998-06-01

    'The objective of this project is to employ the technique of electron spin resonance (ESR), in conjunction with other experimental methods, to study radiation-induced decomposition of vitreous compositions proposed for immobilization/disposal of high-level nuclear wastes (HLW) or excess weapons plutonium. ESR is capable of identifying, even at the parts-per-million level, displaced atoms, ruptured bonds, and free radicals created by radiation in such glassy forms. For example, one of the scientific goals is to determine whether ESR-detectable superoxide (O{sub 2}{sup -}) and ozonide (O{sub 3}{sup -}) ions are precursors of radiation-induced oxygen gas bubbles reported by other investigators. The fundamental understandings obtained in this study will enable reliable predictions of the long-term effects of and decays of the immobilized radionuclides on HLW glasses. This report represents the results of an 18-month effort performed under a 3-year research award. Four categories of materials were studied: (1) several actual and proposed HLW glass compositions fabricated at Savannah River Technology Center (SRTC), samples of which had been irradiated to a dose of 30 MGy (1 Gy = 100 rad) to simulate decay effects, (2) several high-iron phosphate glasses fabricated at the University of Missouri-Rolla (UMR), (3) one other model HLW glass and several simulated natural glasses which had been implanted with 160-keV He{sup +} ions to simulate-decay damage, and (4) an actual geological glass damaged by decays of trace amounts of contained {sup 238}U and {sup 232}Th over a period of 65 Myears. Among the category-1 materials were two samples of Defense Waste Processing Facility (DWPF) borosilicate glasses modeling compositions currently being used to vitrify HLW at SRTC. The ESR spectra recorded for the unirradiated DWPF-glass simulants were attributable to Fe 3{sup +} ions. The 30-MGy irradiation was found to change the Fe{sup 3+} concentration of these glasses by a

  12. 75 FR 53694 - Florida Petroleum Reprocessors Superfund Site; Davie, Broward County, FL; Notice of Settlement

    Science.gov (United States)

    2010-09-01

    ... AGENCY Florida Petroleum Reprocessors Superfund Site; Davie, Broward County, FL; Notice of Settlement... costs concerning the Florida Petroleum Reprocessors Superfund Site located in Davie, Broward County... Petroleum Reprocessors Superfund Site by one of the following methods: http://www.regulations.gov :...

  13. 77 FR 9652 - Proposed CERCLA Administrative Cost Recovery Settlement; Lake Linden Superfund Site in Lake...

    Science.gov (United States)

    2012-02-17

    ... AGENCY Proposed CERCLA Administrative Cost Recovery Settlement; Lake Linden Superfund Site in Lake Linden... administrative settlement for recovery of past response costs concerning the Lake Linden Superfund Site in Lake..., Chicago, Illinois, C-14J, 60604, (312) 886-6609. Comments should reference the Lake Linden Superfund...

  14. 78 FR 729 - Ellman Battery Superfund Site; Orlando, Orange County, FL; Notice of Settlement

    Science.gov (United States)

    2013-01-04

    ... AGENCY Ellman Battery Superfund Site; Orlando, Orange County, FL; Notice of Settlement AGENCY... concerning a previous Removal Action at the Ellman Battery Superfund Site located in Orlando, Orange County.... Submit your comments by Site name Ellman Battery Superfund Site by one of the following methods:...

  15. 77 FR 8255 - Constitution Road Drum Superfund Site, Atlanta, Dekalb County, GA; Notice of Settlement

    Science.gov (United States)

    2012-02-14

    ... AGENCY Constitution Road Drum Superfund Site, Atlanta, Dekalb County, GA; Notice of Settlement AGENCY... entered into a settlement for past response costs concerning the Constitution Road Drum Superfund Site... available from Ms. Paula V. Painter. Submit your comments by Site name Constitution Road Drum Superfund...

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

    International Nuclear Information System (INIS)

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

  17. The Role of the Two-Component System BaeSR in Disposing Chemicals through Regulating Transporter Systems in Acinetobacter baumannii.

    Directory of Open Access Journals (Sweden)

    Ming-Feng Lin

    Full Text Available Bacterial two-component regulatory systems (TCSs facilitate changes in gene expression in response to environmental stimuli. TCS BaeR regulons influence tigecycline susceptibility in Acinetobacter baumannii through positively regulating the pump genes adeA and adeB. In this study, we demonstrate that an additional two transport systems, AdeIJK and MacAB-TolC, are also regulated by BaeSR. In the wild type and clinical tigecycline-resistant A. baumannii strains, gene expression of AdeIJK and MacAB-TolC increased after tigecycline induction, implicating their importance to tigecycline resistance in addition to AdeABC. Phenotypic microarray results showed that A. baumannii is vulnerable to certain chemicals, especially tannic acid, after deleting baeR, which was confirmed using the spot assay. The wild-type strain of A. baumannii also exhibited 1.6-fold and 4.4-fold increase in gene expression of adeJ and macB in the medium with 100 μg/mL tannic acid, but the increase was fully inhibited by baeR deletion. An electrophoretic motility shift assay based on an interaction between His-BaeR and the adeA, adeI and macA promoter regions did not demonstrate direct binding. In conclusion, A. baumannii can use the TCS BaeSR in disposing chemicals, such as tannic acid and tigecycline, through regulating the efflux pumps.

  18. Treatment and Disposal of Status and Analysis for Chemical Waste%废弃化学品处理处置现状与分析

    Institute of Scientific and Technical Information of China (English)

    弓创周; 丁灵; 李洁; 夏俊玲; 安晓英; 赵美敬

    2015-01-01

    我国工业经济的迅速发展,带来了工业三废量的急剧增长,不加处理随意排放,将对周边大气、水体、土壤及生态系统带来了严重破坏,造成有回收利用价值的废弃化学品资源的浪费。加强废弃化学品处理处置标准化工作,进行资源化科技创新,深入实施节能减排、资源综合再利用,促进循环经济、绿色产业、低碳技术发展,符合我国的产业政策发展规划的总体要求。%Along with the rapid development of industry in our country, three industrial wastes are increasing quickly. If these untreated substances are discharged arbitrarily it will cause serious environmental pollution and waste of resources for chemical waste. It was conformed that the overall requirement of the industrial policy of development was planed in our country, such as strengthening the standardization work of treatment and disposaling for chemical waste, proceeding technological innovation, implementation energy - saving and utilization of resources, promoting the development of the circular economy, green industries and low-carbon technologies.

  19. 1992 update of US EPA's Superfund Innovative Technology Evaluation (SITE) Emerging Technology Program

    International Nuclear Information System (INIS)

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

  20. Discussion on Disposing Acid Waste Water by Physico-chemical Treatment Technology%利用物化技术处理含酸废水的技术探讨

    Institute of Scientific and Technical Information of China (English)

    张绍坤

    2013-01-01

    Based on analyzing al kinds of the disposal technology characters and application on acid waste water, the article approves that the physico-chemical treatment technology could effectively dispose al kinds of acid waste water. The physico-chemical treatment technology had some advantages such as wide adaptability on waste water, high heavy metal removal efficiency, and so on. So it can be used widely in the waste water disposal projects. According to the application of waste water disposal projects, the article points out several shortcomings need to be solved, such as the high disposal cost, the hard process control.%  通过分析各种含酸废水处理技术的特点和工程应用,指出利用物化技术能够有效处理各种含酸废水,具有废水适应性广、重金属去除效率高等优点,适合工程应用;物化技术在实际工程应用中,还存在处理成本高、工艺控制点不易控制等不足,需进一步研究加以克服。

  1. Chemical decomposition of high-level nuclear waste storage/disposal glasses under irradiation. 1997 annual progress report

    International Nuclear Information System (INIS)

    'The objective of this research is to use the sensitive technique of electron spin resonance (ESR) to look for evidence of radiation-induced chemical decomposition of vitreous forms contemplated for immobilization of plutonium and/or high-level nuclear wastes, to interpret this evidence in terms of existing knowledge of glass structure, and to recommend certain materials for further study by other techniques, particularly electron microscopy and measurements of gas evolution by high-vacuum mass spectroscopy. Previous ESR studies had demonstrated that an effect of y rays on a simple binary potassium silicate glass was to induce superoxide (O2-) and ozonide (O3-) as relatively stable product of long-term irradiation Accordingly, some of the first experiments performed as a part of the present effort involved repeating this work. A glass of composition 44 K2O: 56 SiO2 was prepared from reagent grade K2CO3 and SiO2 powders melted in a Pt crucible in air at 1,200 C for 1.5 hr. A sample irradiated to a dose of 1 MGy (1 MGy = 108 rad) indeed yielded the same ESR results as before. To test the notion that the complex oxygen ions detected may be harbingers of radiation-induced phase separation or bubble formation, a small-angle neutron scattering (SANS) experiment was performed. SANS is theoretically capable of detecting voids or bubbles as small as 10 305 in diameter. A preliminary experiment was carried out with the collaboration of Dr. John Barker (NIST). The SANS spectra for the irradiated and unirradiated samples were indistiguishable. A relatively high incoherent background (probably due to the presence of protons) may obscure scattering from small gas bubbles and therefore decrease the effective resolution of this technique. No further SANS experiments are planned at this time.'

  2. Chemical decomposition of high-level nuclear waste storage/disposal glasses under irradiation. 1997 annual progress report

    Energy Technology Data Exchange (ETDEWEB)

    Griscom, D.L.; Merzbacher, C.I.

    1997-01-01

    'The objective of this research is to use the sensitive technique of electron spin resonance (ESR) to look for evidence of radiation-induced chemical decomposition of vitreous forms contemplated for immobilization of plutonium and/or high-level nuclear wastes, to interpret this evidence in terms of existing knowledge of glass structure, and to recommend certain materials for further study by other techniques, particularly electron microscopy and measurements of gas evolution by high-vacuum mass spectroscopy. Previous ESR studies had demonstrated that an effect of y rays on a simple binary potassium silicate glass was to induce superoxide (O{sub 2}{sup -}) and ozonide (O{sub 3}{sup -}) as relatively stable product of long-term irradiation Accordingly, some of the first experiments performed as a part of the present effort involved repeating this work. A glass of composition 44 K{sub 2}O: 56 SiO{sub 2} was prepared from reagent grade K{sub 2}CO3 and SiO{sub 2} powders melted in a Pt crucible in air at 1,200 C for 1.5 hr. A sample irradiated to a dose of 1 MGy (1 MGy = 10{sup 8} rad) indeed yielded the same ESR results as before. To test the notion that the complex oxygen ions detected may be harbingers of radiation-induced phase separation or bubble formation, a small-angle neutron scattering (SANS) experiment was performed. SANS is theoretically capable of detecting voids or bubbles as small as 10 \\305 in diameter. A preliminary experiment was carried out with the collaboration of Dr. John Barker (NIST). The SANS spectra for the irradiated and unirradiated samples were indistiguishable. A relatively high incoherent background (probably due to the presence of protons) may obscure scattering from small gas bubbles and therefore decrease the effective resolution of this technique. No further SANS experiments are planned at this time.'

  3. Disposable rabbit

    Science.gov (United States)

    Lewis, Leroy C.; Trammell, David R.

    1986-01-01

    A disposable rabbit for transferring radioactive samples in a pneumatic transfer system comprises aerated plastic shaped in such a manner as to hold a radioactive sample and aerated such that dissolution of the rabbit in a solvent followed by evaporation of the solid yields solid waste material having a volume significantly smaller than the original volume of the rabbit.

  4. SUPERFUND GROUND WATER ISSUE - ACCURACY OF DEPTH TO WATER MEASUREMENTS

    Science.gov (United States)

    Accuracy of depth to water measurements is an issue identified by the Forum as a concern of Superfund decision-makers as they attempt to determine directions of ground-water flow, areas of recharge of discharge, the hydraulic characteristics of aquifers, or the effects of manmade...

  5. Waste disposal

    CERN Multimedia

    2006-01-01

    We should like to remind you that you can have all commonplace, conventional waste (combustible, inert, wood, etc.) disposed of by the TS-FM Group. Requests for the removal of such waste should be made by contacting FM Support on tel. 77777 or by e-mail (Fm.Support@cern.ch). For requests to be acted upon, the following information must be communicated to FM Support: budget code to be debited for the provision and removal of the skip / container; type of skip required (1m3, 4 m3, 7 m3, 15 m3, 20 m3, 30 m3); nature of the waste to be disposed of (bulky objects, cardboard boxes, etc.); building concerned; details of requestor (name, phone number, department, group, etc.). We should also like to inform you that the TS-FM Group can arrange for waste to be removed from work-sites for firms under contract to CERN, provided that the prior authorisation of the CERN Staff Member in charge of the contract is obtained and the relevant disposal/handling charges are paid. You are reminded that the selective sorting...

  6. Waste disposal

    CERN Multimedia

    2006-01-01

    We should like to remind you that you can have all commonplace, conventional waste (combustible, inert, wood, etc.) disposed of by the TS-FM Group. Requests for the removal of such waste should be made by contacting FM Support on tel. 77777 or by e-mail (Fm.Support@cern.ch). For requests to be acted upon, the following information must be communicated to FM Support: budget code to be debited for the provision and removal of the skip / container. type of skip required (1m3, 4 m3, 7 m3, 15 m3, 20 m3, 30 m3). nature of the waste to be disposed of (bulky objects, cardboard boxes, etc.). building concerned. details of requestor (name, phone number, department, group, etc.). We should also like to inform you that the TS-FM Group can arrange for waste to be removed from work-sites for firms under contract to CERN, provided that the prior authorisation of the CERN Staff Member in charge of the contract is obtained and the relevant disposal/handling charges are paid. You are reminded that the selective sorting o...

  7. 40 CFR 35.6345 - Equipment disposal options.

    Science.gov (United States)

    2010-07-01

    ... ASSISTANCE STATE AND LOCAL ASSISTANCE Cooperative Agreements and Superfund State Contracts for Superfund Response Actions Personal Property Requirements Under A Cooperative Agreement § 35.6345 Equipment...

  8. The Political Production of Superfund: Some Financial Market Results

    OpenAIRE

    Brett Dalton; David Riggs; Bruce Yandle

    1996-01-01

    In this article, we assess the prospective effects of different legislative packages by examining how financial markets reacted to alternate proposals and the final law. The use of financial markets analysis provides at least one avenue for identifying interest groups that won and lost as the major features of proposed legislation were modified. The analysis indirectly determines who pays for Superfund. Significant shareholder losses indicate shareholders pay. By contrast, the absence of weal...

  9. Modelling soil and soil to plant transfer processes of radionuclides and toxic chemicals at long time scales for performance assessment of Radwaste disposal

    Science.gov (United States)

    Albrecht, Achim; Miquel, Stephan

    2015-04-01

    Performance assessments for surface nuclear waste disposal facilities require simulation of transfer processes from the waste canisters to a reference group living near-by. Such simulations need to be extended over several hundred to hundred thousand years, depending on waste type, restraining possibilities to represent short term system complexity and variability. Related modelling can be simplified as long as processes are represented conservatively with assessment endpoints estimated larger compared to more realistic modelling approaches. The indicators are doses for radionuclides (RN) and risk factors for toxic chemicals (TC, i.e. heavy metals, nitrate). We discuss a new simulation tool (SCM-Andra-multilayer-model, SAMM) that, among others, allows to model situations where RN/TC move through a soil profile characterised by temporal undersaturation and root growth (soil-plant subsystem of the biosphere model compared to the adjacent saturated geosphere). SAMM describes all relevant transfer and reaction processes (advection, diffusion, root transport, radioactive decay, chemical reactions incl. sorption - desorption) using well known differential equations solved numerically within MATLAB with scenario description and parameterisation defined in Excel sheets. With this conservative approach in mind, we apply global parameters for which the solid-solution (Kd) or soil-to-plant (TF) distribution coefficients are the most relevant. Empirical data are available for homogeneous situations, such as one compartment pot experiments, but rare for entire soil profiles. Similarly soil hydrology, in particular upward and downward advective fluxes are modelled using an empirical approach solely based on key soil hydrological parameters (precipitation, evapotranspiration, irrigation, water table level) and the soil porosity. Variability of soil hydrology in space and time, likely to change drastically even on hourly bases (i.e. intense precipitation event) or within a single

  10. A summary of chemical and biological testing of proposed disposal of sediment from Richmond Harbor relative to the Deep Off-Shelf Reference Area, the Bay Farm Borrow Area, and the Alcatraz Environs Reference Area

    Energy Technology Data Exchange (ETDEWEB)

    Mayhew, H.L.; Karle, L.M.; Gruendell, B.D.; Pinza, M.R. [Battelle/Marine Sciences Lab., Sequim, WA (United States)

    1993-12-01

    The US Army Corps of Engineers was authorized to dredge Richmond Harbor to accomodate large, deep-draft vessels. An ecological evaluation of the Harbor sediments was performed describing the physical characteristics, toxic substances, effects on aquatic organisms,and potential for bioaccumulation of chemical contaminants. The objective of this report is to compare the sediment chemistry, acute toxicity, and bioaccumulation results of the Richmond Harbor sediments to each of the reference areas; i.e., the Deep Off-Shelf Reference Area, the Bay Farm Borrow Area, and the Alcatraz Environs Reference Area. This report will enable the US Army Corps of Engineers to determine whether disposal at a reference area is appropriate for all or part of the dredged material from Richmond Harbor. Chemical analyses were performed on 30 sediment samples; 28 of those samples were then combined to form 7 composites. The seven composites plus sediment from two additional stations received both chemical and biological evaluations.

  11. 75 FR 81269 - Ward Transformer Superfund Site Raleigh, Wake County, NC; Notice of Settlements

    Science.gov (United States)

    2010-12-27

    ... AGENCY Ward Transformer Superfund Site Raleigh, Wake County, NC; Notice of Settlements AGENCY... Ward Transformer Superfund Site located in Raleigh, Wake County, North Carolina for publication. DATES... your comments, identified by Docket ID No. EPA-RO4- SFUND-2010-1053 or Site name Ward...

  12. 78 FR 14543 - Ward Transformer Superfund Site; Raleigh, Wake County, NC; Notice of Settlement

    Science.gov (United States)

    2013-03-06

    ... AGENCY Ward Transformer Superfund Site; Raleigh, Wake County, NC; Notice of Settlement AGENCY... Agency has entered into a settlement at the Ward Transformer Superfund Site located in Raleigh, Wake... EPA Region 4 contact Ms. Paula V. Painter. Submit your comments by Site name Ward...

  13. Waste disposal: preliminary studies

    International Nuclear Information System (INIS)

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

  14. Are typical plains state towns potential superfund sites?

    International Nuclear Information System (INIS)

    A typical plains town (Hastings, population 23,000) in south-central Nebraska was the subject of a remedial investigation/feasibility study (RI/FS). This town was classified as a Superfund site in 1985. The RI/FS consisted of installing 40 monitoring wells, drilling 111 exploratory boreholes, and analyzing numerous soil, soil gas, and ground-water samples. As the picture unfolded, it became evident that this Superfund site is probably typical of any agricultural community in the plains states. The site is approximately 3.25 miles long, 0.5 mile wide, and is centered on the intersection of two major rail lines. The site was segmented into seven subsites based on identified sources of ground-water contamination. Each source could represent an operation typical of small towns located on the plains. Two of the subsites were designated because of fumigant releases at former and current grain storage facilities; one of these subsites also experienced a solvent release from a manufacturing facility. A third subsite was designated because of a solvent release. This subsite was adjacent to a fourth subsite containing the residuals of a former coal gasification operation. Another two subsites were former landfills. The seventh subsite, a former Navy Ammunition Depot located outside of town, is not typical of most towns in the plains states. This subsite is currently an industrial complex. Contaminant releases have been identified on this subsite that are the result of former ammunition operations and some current operations. Ground-water contaminant configuration is very complicated in that the site ground-water contaminant plume is the commingling of six major contaminants forming five separate plumes. Given the overall similarity in the physiographic conditions, geologic formations, hydrogeology, and farming related industries/operations, we believe that HaStings may not be unique and other typical plains state towns have the potential to become Superfund sites

  15. Analysis and Disposal of Organic Pollutants in Waste Soil Chemical Pollution Accident Risk%化工污染事故危险废土中有机污染物的分析与处置

    Institute of Scientific and Technical Information of China (English)

    张慧敏; 王晓毅; 时治富

    2012-01-01

    以(某)化工公司污染事故为例,针对危险固废中主要污染物进行了测试分析和危险特性鉴别,通过对污染土壤焚烧实验研究,着重分析讨论了各种处置方法的优缺点,结果表明,利用民生砖厂隧道窑配制烧砖处置方案较好,通过实际应用,取得了良好效果。%Take a chemical company's pollution accident for example, after the accident of pollution, the test analysis and identification of hazardous properties is made for the major pollutants in the contaminated waste soil. The selection of incineration parameters of contaminated soil is studied and analyzed. Further exploration and study of environmental emergency disposal solution of pollution soil is made, so to provide a soild waste disposal methods for dealing with hazardous waste soil in chemical company pollution acci- dent.

  16. Depleted uranium disposal options evaluation

    International Nuclear Information System (INIS)

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

  17. Strategic planning for waste management: Characterization of chemically and radioactively hazardous waste and treatment, storage, and disposal capabilities for diverse and varied multisite operations

    International Nuclear Information System (INIS)

    Information about current and projected waste generation as well as available treatment, storage, and disposal (TSD) capabilities and needs is crucial for effective, efficient, and safe waste management. This is especially true for large corporations that are responsible for multisite operations involving diverse and complex industrial processes. Such information is necessary not only for day-to-day operations, but also for strategic planning to ensure safe future performance. This paper reports on some methods developed and successfully applied to obtain requisite information and to assist waste management planning at the corporate level in a nationwide system of laboratories and industries. Waste generation and TSD capabilities at selected US Department of Energy (DOE) sites were studied. 1 ref., 2 tabs

  18. Growth, Structural and Optical Characterization of ZnO Nanotubes on Disposable-Flexible Paper Substrates by Low-Temperature Chemical Method

    Directory of Open Access Journals (Sweden)

    M. Y. Soomro

    2012-01-01

    Full Text Available We report the synthesis of vertically aligned ZnO nanotubes (NTs on paper substrates by low-temperature hydrothermal method. The growth of ZnO NTs on the paper substrate is discussed; further, the structural and optical properties are investigated by scanning electron microscope (SEM, transmission electron microscopy (TEM, X-ray diffraction (XRD, energy-dispersive X-ray spectroscopy (EDS, and cathodoluminescence (CL, and it was found that the ZnO NTs on paper substrate fulfill the structural and optical properties of ZnO NTs grown on other conventional substrates. This will be more beneficial in future usage of ZnO NTs in different fields and applications. Particularly, this approach opens the ways in research and development for high volume manufacturing of low-cost, flexible optoelectronics devices on disposable paper substrates and can be used in the future miniaturization trends.

  19. Cleanups In My Community (CIMC) - Federal facilities that are also Superfund sites, National Layer

    Data.gov (United States)

    U.S. Environmental Protection Agency — Federal facilities are properties owned by the federal government. This data layer provides access to Federal facilities that are Superfund sites as part of the...

  20. Cleanups In My Community (CIMC) - Base Realignment and Closure (BRAC) Superfund Sites, National Layer

    Data.gov (United States)

    U.S. Environmental Protection Agency — This data layer provides access to Base Realignment and Closure (BRAC) Superfund Sites as part of the CIMC web service. EPA works with DoD to facilitate the reuse...

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

    Science.gov (United States)

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

    2011-01-01

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

  2. 77 FR 69827 - Comprehensive Environmental Response, Compensation and Liability Act (CERCLA) or Superfund...

    Science.gov (United States)

    2012-11-21

    ... outreach to local communities to increase their awareness and knowledge regarding the importance of... From the Federal Register Online via the Government Publishing Office ENVIRONMENTAL PROTECTION AGENCY Comprehensive Environmental Response, Compensation and Liability Act (CERCLA) or Superfund;...

  3. Proposed plan for the United Nuclear Corporation Disposal Site at the Oak Ridge Y-12 Plant, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    The US Department of Energy (DOE) in compliance with Section 117(a) of the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) of 1980, as amended by the Superfund Amendments and Reauthorization Act (SARA) of 1986, is releasing the proposed plan for remedial action at the United Nuclear Corporation (UNC) Disposal Site located at the DOE Oak Ridge Operations (ORO) Y-12 Plant, Oak Ridge, Tennessee. The purpose of this document is to present and solicit for comment to the public and all interested parties the ''preferred plan'' to remediate the UNC Disposal Site. However, comments on all alternatives are invited

  4. Maxey Flats low-level waste disposal site closure activities

    International Nuclear Information System (INIS)

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

  5. Radioactive Water Treatment at a United States Environmental Protection Agency Superfund Site - 12322

    International Nuclear Information System (INIS)

    A water treatment system at a United States Environmental Protection Agency (USEPA) Superfund site impacted by radiological contaminants is used to treat water entering the site. The United States Army Corps of Engineers (USACE) is actively managing the remedial action for the USEPA using contracts to support the multiple activities on site. The site is where former gas mantle production facilities operated around the turn of the century. The manufacturing facilities used thorium ores to develop the mantles and disposed of off-specification mantles and ore residuals in the surrounding areas. During Site remedial actions, both groundwater and surface water comes into contact with contaminated soils and must be collected and treated at an on-site treatment facility. The radionuclides thorium and radium with associated progeny are the main concern for treatment. Suspended solids, volatile organic compounds, and select metals are also monitored during water treatment. The water treatment process begins were water is pumped to a collection tank where debris and grit settle out. Stored water is pumped to a coagulant tank containing poly-aluminum chloride to collect dissolved solids. The water passes into a reaction tube where aspirated air is added or reagent added to remove Volatile Organic Compounds (VOC'S) by mass transfer and convert dissolved iron to a solid. The water enters the flocculent polymer tank to drop solids out. The flocculated water overflows to a fluidized bed contact chamber to increase precipitation. Flocculation is where colloids of material drop out of suspension and settle. The settled solids are periodically removed and disposed of as radioactive waste. The water is passed through filters and an ion exchange process to extract the radionuclides. Several million liters of water are processed each year from two water treatment plants servicing different areas of the remediation site. Ion exchange resin and filter material are periodically replaced

  6. Waste package degradation from thermal and chemical processes in performance assessments for the Yucca Mountain disposal system for spent nuclear fuel and high-level radioactive waste

    International Nuclear Information System (INIS)

    This paper summarizes modeling of waste container degradation in performance assessments conducted between 1984 and 2008 to evaluate feasibility, viability, and assess compliance of a repository for spent nuclear fuel and high-level radioactive waste at Yucca Mountain, Nevada. As understanding of the Yucca Mountain disposal system increased, modeling of container degradation evolved from a component of the source term in 1984 to a separate module describing both container and drip shield degradation in 2008. A thermal module for evaluating the influence of higher heat loads from more closely packed, large waste packages was also introduced. In addition, a module for evaluating drift chemistry was added in later PAs to evaluate the potential for localized corrosion of the outer barrier of the waste container composed of Alloy 22, a highly corrosion-resistant nickel–chromium–tungsten–molybdenum alloy. The uncertainty of parameters related to container degradation contributed significantly to the estimated uncertainty of performance measures (cumulative release in assessments prior to 1995 and individual dose, thereafter). - Highlights: • Progression of container modeling from an assumption of complete failure before 1993 to a stochastic description after 1995 is described. • Introduction of thermal-hydrologic model to examine interaction between the engineered and natural barrier, and container degradation is described. • The introduction of a water chemistry module to evaluate the possibility of localized corrosion of the container is described. • The addition of seismic damage models to evaluate container damage from drift degradation and container movement is described

  7. CHEMICALS

    CERN Multimedia

    Medical Service

    2002-01-01

    It is reminded that all persons who use chemicals must inform CERN's Chemistry Service (TIS-GS-GC) and the CERN Medical Service (TIS-ME). Information concerning their toxicity or other hazards as well as the necessary individual and collective protection measures will be provided by these two services. Users must be in possession of a material safety data sheet (MSDS) for each chemical used. These can be obtained by one of several means : the manufacturer of the chemical (legally obliged to supply an MSDS for each chemical delivered) ; CERN's Chemistry Service of the General Safety Group of TIS ; for chemicals and gases available in the CERN Stores the MSDS has been made available via EDH either in pdf format or else via a link to the supplier's web site. Training courses in chemical safety are available for registration via HR-TD. CERN Medical Service : TIS-ME :73186 or service.medical@cern.ch Chemistry Service : TIS-GS-GC : 78546

  8. Safe disposal of surplus plutonium

    Science.gov (United States)

    Gong, W. L.; Naz, S.; Lutze, W.; Busch, R.; Prinja, A.; Stoll, W.

    2001-06-01

    About 150 tons of weapons grade and weapons usable plutonium (metal, oxide, and in residues) have been declared surplus in the USA and Russia. Both countries plan to convert the metal and oxide into mixed oxide fuel for nuclear power reactors. Russia has not yet decided what to do with the residues. The US will convert residues into a ceramic, which will then be over-poured with highly radioactive borosilicate glass. The radioactive glass is meant to provide a deterrent to recovery of plutonium, as required by a US standard. Here we show a waste form for plutonium residues, zirconia/boron carbide (ZrO 2/B 4C), with an unprecedented combination of properties: a single, radiation-resistant, and chemically durable phase contains the residues; billion-year-old natural analogs are available; and criticality safety is given under all conceivable disposal conditions. ZrO 2/B 4C can be disposed of directly, without further processing, making it attractive to all countries facing the task of plutonium disposal. The US standard for protection against recovery can be met by disposal of the waste form together with used reactor fuel.

  9. Problems of radioactive waste disposal in cryolithozone

    International Nuclear Information System (INIS)

    The paper considers the problems of utilizing perennially frozen rocks as host medium for underground disposal of radwaste. Peculiarities of mechanical, thermal and chemical interaction of radwaste with frozen ground are shown. Significant differences in the impact of low-, intermediate- and high-active waste on the geological environment of cryolithozone are established; the differences require a mathematical modeling of thermal interaction of heat emitting radwaste with frozen soils. The investigations show that a long-term reliable disposal of radwaste in the frozen rock formations is feasible and, according to many indicators, is more preferable as compared to the disposal in nonfrozen rock formations. 15 refs., 10 figs

  10. 钚在某处置工程屏障水环境中化学形态及影响因素%Chemical Forms and Influence Factors of Plutonium in Environmental Water of a Disposal Engineering Barrier

    Institute of Scientific and Technical Information of China (English)

    马应明; 何艺峰; 李哲; 刘莉; 刘艳; 石建芳

    2013-01-01

    Aimed at backfill structure in the engineering barrier of a certain disposal project,the geochemical modeling software,EQ3/6,was applied to simulate chemical forms of plutonium based on results of barrier samples leaching by the fracture water and chemical analysis of leaching samples.Results showed that the form of plutonium was Pu(OH)5-in Pu(Ⅳ)valence state.Changes of pH and Eh values in environmental water will affect the forms and valence state of plutonium.%针对某放射性废物包装容器回填处置工程屏障结构特征,采用岩体裂隙水浸泡工程屏障样品的方式,在对各平衡水样化学成分分析的基础上,利用地球化学模拟软件EQ3/6对钚在回填工程屏障水环境中的存在化学形态进行了模拟计算,得出钚在回填工程屏障水环境中主要以Pu(Ⅳ)价态Pu(OH)5形式存在,同时水环境中pH值和Eh值的变化皆会影响钚的存在化学形态和价态.

  11. Radioactive waste disposal policy

    International Nuclear Information System (INIS)

    The responsibilities of the Minister of Agriculture, Fisheries and Food and Ministry policy on radioactive waste disposal are described. The disposal of solid radioactive waste at sea is subject to detailed safeguards developed within two international agreements to which the United Kingdom is a contracting party. The agreements are discussed together with a research and monitoring programme to provide scientific data for informed decisions on waste disposal authorisations and dumping licences. (U.K.)

  12. 76 FR 24479 - In the Matter of the Taylor Lumber and Treating Superfund Site, Sheridan, Oregon, Amendment to...

    Science.gov (United States)

    2011-05-02

    ... AGENCY In the Matter of the Taylor Lumber and Treating Superfund Site, Sheridan, Oregon, Amendment to... with PWPO provided a covenant not to sue for response costs at the Taylor Lumber and Treating Site... should reference the Taylor Lumber and Treating Superfund Site in Sheridan, Oregon, EPA Docket No....

  13. EPA Superfund Records of Decision (RODs) for Region 9: Arizona, California, Hawaii, Nevada, American Samoa, and Guam

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-03-01

    The purpose of an EPA Record of Decision is to evaluate a Superfund Site with the goal of protecting human health and the environment while ensuring consistency of evaluations in contamination and clean-up of all Superfund sites. The ROD is a public document signed by the appropriate Regional Administrator which details cleanup, cost estimates, and EPA`s responsiveness to the public comment summary. The ROD may be litigated, thus it is important to have all current updates to the signed EPA decision. The ROD may be amended with an Amendment or supplemented by an Explanation of Significant Difference (ESD). A Superfund Site may have multiple RODs, as each Superfund Site may be further redefined as Operable Units and Events. This allows EPA`s decisions to evolve as new technology presents itself. Average clean-up time for a Superfund Site can range from 12 to 100 years.

  14. EPA superfund Records of Decision (RODs) for region 9: Arizona, California, Hawaii, Nevada, American Samoa, and Guam. Irregular report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-03-01

    The purpose of an EPA Record of Decision is to evaluate a Superfund Site with the goal of protecting human health and the environment while ensuring consistency of evaluations in contamination and clean-up of all Superfund sites. The ROD is a public document signed by the appropriate Regional Administrator which details cleanup, cost estimates, and EPA`s responsiveness to the public comment summary. The ROD may be litigated, thus it is important to have all current updates to the signed EPA decision. The ROD may be amended with an Amendment or supplemented by an Explanation of Significant Difference (ESD). A Superfund Site may have multiple RODs, as each Superfund Site may be further redefined as Operable Units and Events. This allows EPA`s decisions to evolve as new technology presents itself. Average clean-up time for a Superfund Site can range from 12 to 100 years.

  15. EPA superfund Records of Decision (RODs) for region 9: Arizona, California, Hawaii, Nevada, American Samoa, and Guam. Irregular report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-01-01

    The purpose of an EPA Record of Decision is to evaluate a Superfund Site with the goal of protecting human health and the environment while ensuring consistency of evaluations in contamination and clean-up of all Superfund sites. The ROD is a public document signed by the appropriate Regional Administrator which details cleanup, cost estimates, and EPA`s responsiveness to the public comment summary. The ROD may be litigated, thus it is important to have all current updates to the signed EPA decision. The ROD may be amended with an Amendment or supplemented by an Explanation of Significant Difference (ESD). A Superfund Site may have multiple RODs, as each Superfund Site may be further redefined as Operable Units and Events. This allows EPA`s decisions to evolve as new technology presents itself. Average clean-up time for a Superfund Site can range from 12 to 100 years.

  16. 粉煤灰场复垦地肥力状况及对土壤理化性质的影响%Reclaimed Soil Fertility and Its Response to the Physical-Chemical Properties in Fly Ash Disposal Sites

    Institute of Scientific and Technical Information of China (English)

    王长垒; 严家平; 陈孝杨

    2013-01-01

    选择安徽省淮南市上窑镇粉煤灰处置场覆土复垦地为研究区域,测定覆土厚度和土壤剖面各层的容重、pH、含水量、有机质等理化性质,土壤总氮、有效磷、速效钾等养分含量,以及冬小麦抽穗期的生物量,研究粉煤灰处置场复垦土壤理化性质及其与土壤养分的相关性,不同覆土厚度复垦地冬小麦生长的差异性.结果表明,粉煤灰场复垦地土壤总氮含量约0.90 g/kg,有效磷和速效钾含量分别为12~76 mg/kg、114~135 mg/kg,土壤肥力与作物生长状况和自然农业土壤相比差异不显著;除复垦土壤厚度、容重、含水量对有效磷含量影响显著外,其余土壤养分与土壤理化性质和表土厚度的相关性不强.%The reclaimed field of fly ash disposal sites was selected as the research area in Shaoyao,Huainan.The cover soil thickness,some soil physico-chemical properties (bulk density,water content,pH and organic matter),soil nutrients (total nitrogen,available phosphorus and available potassium) and winter wheat biomass in heading stage were determined,and the correlation of the reclaimed soil physico-chemical properties and its nutrient was analyzed in fly ash disposal sites.The winter wheat growth differences were also studied under different coversoil thickness conditions.The results showed that the total nitrogen content was about 900 mg/kg in reclaimed soil of fly ash disposal sites,the content of available phosphorus and available potassium was 12~76mg/kg and 114~135 mg/kg respectively.The soil fertility and crop growth conditions were not significant difference with natural agricultural soils.The available phosphorus content and reclaimed soil bulk density,water content had a significant correlation.In addition,the response relationship between the reclaimed soil fertility and its properties,topsoil thickness was not obvious.

  17. TECHNO – ECONOMIC ACCEPTABILITY ANALISYS OF WASTE DISPOSAL BY INJECTION INTO APPROPRIATE FORMATION

    OpenAIRE

    Vladislav Brkić; Daria Karasalihović Sedlar

    2013-01-01

    During exploration and production of oil and natural gas, various types of waste must be disposed in a permanent and safe way. There is a range of methods for processing and disposal of waste, such as disposal into landfills, solidification, namely chemical stabilization, thermal processing, appropriate formation injections uncovered by a deep well, disposal into salt domes and bioremediation. The method of waste disposal into appropriate formations is a method where strict geological and tec...

  18. 高放废物处置库雅满苏和天湖地段地下水化学特征%Groundwater Chemical Characteristics in Yamansu and Tianhu Section for High Level Radioactive Waste Disposal Repository

    Institute of Scientific and Technical Information of China (English)

    郭永海; 李娜娜; 周志超; 董建楠; 季瑞利; 刘淑芬

    2014-01-01

    Yamansu and Tianhu area in Xinjiang is the main preselected section of disposal repository for high level radioactive waste(HLW)in our country.In the siting and site char-acterization study for high level radioactive waste repository,the groundwater chemical char-acteristics are the one of the most important evaluation factors.From 2009 to 2013,the field hydrogeochemical investigation was carried out and more than 30 groundwater samples were collected.According to the measurement data,the paper discussed the groundwater chemical features in Yamansu and Tianhu preselected section for China’s high level radioactive waste repository.The main conclusion is that:the groundwater in the study area is mainly saline water with high dissolved solids,7.69-9.64 pH value,11.8-24.0℃,542.7-413 375.5 mg/L total dissolved solids and Cl · SO4—Na,SO4 · Cl—Na and Cl—Na chemical types.The hydrogeochemical features show that lixiviation and evaporation are the basic pattern forming the groundwater chemistry in the section.%新疆雅满苏和天湖地区是我国高放废物处置库场址的主要预选地段之一。在高放废物处置库选址和评价中,水文地球化学特征是最重要的评价因素之一。在2009—2013年间,开展了雅满苏和天湖地段区域水文地球化学调查,采集地下水样品30余组,根据样品测试结果,讨论了该地区水文地球化学特征,其主要结论是:研究区地下水主要为高矿化的咸水。地下水的 pH=7.69~9.64;水温11.8~24.0℃;地下水矿化度(TDS)在542.7~413375.5 mg/L之间变化,地下水的主要化学类型为Cl·SO4—Na、SO4·Cl—Na和Cl—Na型。控制地下水化学形成的主要作用是溶滤作用和蒸发浓缩作用。

  19. Waste Water Disposal Design And Management IV

    International Nuclear Information System (INIS)

    This book introduces biological waste water treatment with basic theory and activated sludge process, which includes chemical reaction engineering with reaction velocity and mass balance, an effector, characteristic of water treatment effector and biological waste water disposal such as flow pattern and tracer test. This is biological theory of steady on waste water treatment, design and management.

  20. Special waste disposal in Austria - cost benefit analysis

    International Nuclear Information System (INIS)

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

  1. Health Effects Associated with Wastewater Treatment, Reuse, and Disposal.

    Science.gov (United States)

    Qu, Xiaoyan; Zhao, Yuanyuan; Yu, Ruoren; Li, Yuan; Falzone, Charles; Smith, Gregory; Ikehata, Keisuke

    2016-10-01

    A review of the literature published in 2015 on topics relating to public and environmental health risks associated with wastewater treatment, reuse, and disposal is presented. This review is divided into the following sections: wastewater management, microbial hazards, chemical hazards, wastewater treatment, wastewater reuse, agricultural reuse in different regions, greywater reuse, wastewater disposal, hospital wastewater, industrial wastewater, and sludge and biosolids. PMID:27620110

  2. 77 FR 16548 - Florida Petroleum Reprocessors Superfund Site; Davie, Broward County, FL; Notice of Settlements

    Science.gov (United States)

    2012-03-21

    ...] Florida Petroleum Reprocessors Superfund Site; Davie, Broward County, FL; Notice of Settlements AGENCY... entered into four (4) settlements for past response costs concerning the Florida Petroleum Reprocessors... settlement are available from Ms. Paula V. Painter. Submit your comments by Site name Florida...

  3. Superfund record of decision (EPA Region 5): Ormet Corporation, Hannibal, OH, September 1994

    Energy Technology Data Exchange (ETDEWEB)

    1994-09-12

    The Record of Decision presents the selected remedy for the Ormet Corporation Superfund Site. The purpose of this remedy is to eliminate or reduce contamination in soils, sediments and ground water, and to reduce the risks associated with exposure to contaminated materials. This is the first and final remedy planned for the Site.

  4. 77 FR 2981 - Constitution Road Drum Superfund Site; Atlanta, Dekalb County, GA; Notice of Settlement

    Science.gov (United States)

    2012-01-20

    ... AGENCY Constitution Road Drum Superfund Site; Atlanta, Dekalb County, GA; Notice of Settlement AGENCY... Protection Agency has entered into a settlement for past response costs concerning the Constitution Road Drum... settlement are available from Ms. Paula V. Painter. Submit your comments by Site name Constitution Road...

  5. 75 FR 38100 - National Institute of Environmental Health Sciences Superfund Hazardous Substance Research and...

    Science.gov (United States)

    2010-07-01

    ... strategies and technologies to provide solutions to the magnitude and complexity of Superfund assessment and...-based, solution-oriented research. The multi-disciplinary scope of mandates and the Program structure... design problem-based, solution-oriented research proposals. This will create opportunities to...

  6. A General Chemistry Assignment Analyzing Environmental Contamination for the Depue, IL, National Superfund Site

    Science.gov (United States)

    Saslow Gomez, Sarah A.; Faurie-Wisniewski, Danielle; Parsa, Arlen; Spitz, Jeff; Spitz, Jennifer Amdur; Loeb, Nancy C.; Geiger, Franz M.

    2015-01-01

    The classroom exercise outlined here is a self-directed assignment that connects students to the environmental contamination problem surrounding the DePue Superfund site. By connecting chemistry knowledge gained in the classroom with a real-world problem, students are encouraged to personally connect with the problem while simultaneously…

  7. PILOT-SCALE INCINERATION OF CONTAMINATED SLUDGES FROM THE BOFORS-NOBEL SUPERFUND SITE

    Science.gov (United States)

    A detailed test program was performed at the U.S. Environmental Protection Agency’s (EPA’s) Incineration Research Facility (IRF) to help determine the effectiveness of incineration in treating two contaminated lagoon sludges from the Bofors-Nobel Superfund site in Mus...

  8. Shallow land disposal technology

    International Nuclear Information System (INIS)

    This paper covers the radioactive waste management policy and regulatory framework, the characteristics of low and intermediate level radioactive waste, the characteristics of waste package, the waste acceptance criteria, the waste acceptance and related activities, the design of the disposal system, the organization of waste transportation, the operation feature, the safety assessment of the Centre de L'Aube, the post closure measures, the closure of the Centre de la Mache disposal facility, the licensing issues. 3 tabs., 7 figs

  9. Development of the Borehole Disposal Concept

    International Nuclear Information System (INIS)

    The Nuclear Energy Corporation of South Africa (Necsa) initiated the Borehole Disposal Concept (BDC) with a view to improving radioactive waste management practices in Africa. An IAEA Technical Cooperation project was launched to investigate the technical feasibility and economic viability of a borehole for the disposal of disused sealed radioactive sources. Phase III of the project was completed by the end of 2004, and the main objective of this phase was to demonstrate the technical feasibility of the concept by means of a practical demonstration. The disposal concept consists of a 260 mm diameter borehole drilled to a depth of up to 100 m in which stainless steel disposal containers are emplaced and backfilled with cement. Each disposal container contains a source within a stainless steel capsule within a containment barrier. Included in the terms of reference of Phase III were the design and the evaluation of the disposal concept. The evaluation included container materials, backfill materials and a generic post-closure safety assessment. The post-closure safety assessment and the associated derivation of activity limits showed that, through the use of multiple physical and chemical barriers, the BDC provides an appropriate degree of long term safety. Furthermore, the safety of the disposal concept is not reliant on an extended period of institutional control, and owing to its small 'footprint', the likelihood of direct human intrusion into the borehole is small. An international peer review team positively assessed the technical feasibility, economic viability and overall safety of the concept, and thus concluded the development phase of the project. The Member States of the African Regional Cooperative Agreement for Research, Development and Training related to Nuclear Science and Technology (AFRA) have decided to proceed to Phase IV of the project with the main aim to implement the borehole disposal technology. (author)

  10. U.S. EPA Superfund Program's Policy for Risk and Dose Assessment

    International Nuclear Information System (INIS)

    The Environmental Protection Agency (EPA) Office of Superfund Remediation and Technology Innovation (OSRTI) has primary responsibility for implementing the long-term (non-emergency) portion of a key U.S. law regulating cleanup: the Comprehensive Environmental Response, Compensation and Liability Act, CERCLA, nicknamed 'Superfund'. The purpose of the Superfund program is to protect human health and the environment over the long term from releases or potential releases of hazardous substances from abandoned or uncontrolled hazardous waste sites. The focus of this paper is on risk and dose assessment policies and tools for addressing radioactively contaminated sites by the Superfund program. EPA has almost completed two risk assessment tools that are particularly relevant to decommissioning activities conducted under CERCLA authority. These are the: 1. Building Preliminary Remediation Goals for Radionuclides (BPRG) electronic calculator, and 2. Radionuclide Outdoor Surfaces Preliminary Remediation Goals (SPRG) electronic calculator. EPA developed the BPRG calculator to help standardize the evaluation and cleanup of radiologically contaminated buildings at which risk is being assessed for occupancy. BPRGs are radionuclide concentrations in dust, air and building materials that correspond to a specified level of human cancer risk. The intent of SPRG calculator is to address hard outside surfaces such as building slabs, outside building walls, sidewalks and roads. SPRGs are radionuclide concentrations in dust and hard outside surface materials. EPA is also developing the 'Radionuclide Ecological Benchmark' calculator. This calculator provides biota concentration guides (BCGs), also known as ecological screening benchmarks, for use in ecological risk assessments at CERCLA sites. This calculator is intended to develop ecological benchmarks as part of the EPA guidance 'Ecological Risk Assessment Guidance for Superfund: Process for Designing and Conducting Ecological Risk

  11. Co-disposal of mixed waste materials

    International Nuclear Information System (INIS)

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

  12. A Comparison of Distillery Stillage Disposal Methods

    Directory of Open Access Journals (Sweden)

    V. Sajbrt

    2010-01-01

    Full Text Available This paper compares the main stillage disposal methods from the point of view of technology, economics and energetics. Attention is paid to the disposal of both solid and liquid phase. Specifically, the following methods are considered: a livestock feeding, b combustion of granulated stillages, c fertilizer production, d anaerobic digestion with biogas production and e chemical pretreatment and subsequent secondary treatment. Other disposal techniques mentioned in the literature (electrofenton reaction, electrocoagulation and reverse osmosis have not been considered, due to their high costs and technological requirements.Energy and economic calculations were carried out for a planned production of 120 m3 of stillage per day in a given distillery. Only specific treatment operating costs (per 1 m3 of stillage were compared, including operational costs for energy, transport and chemicals. These values were determined for January 31st, 2009. Resulting sequence of cost effectiveness: 1. – chemical pretreatment, 2. – combustion of granulated stillage, 3. – transportation of stillage to a biogas station, 4. – fertilizer production, 5. – livestock feeding. This study found that chemical pretreatment of stillage with secondary treatment (a method developed at the Department of Process Engineering, CTU was more suitable than the other methods. Also, there are some important technical advantages. Using this method, the total operating costs are approximately 1 150 ??/day, i.e. about 9,5 ??/m3 of stillage. The price of chemicals is the most important item in these costs, representing about 85 % of the total operating costs.

  13. HISTORY AND ACCOMPLISHMENTS OF THE US EPA'S SUPERFUND INNOVATIVE TECHNOLOGY EVALUATION (SITE) MONITORING AND MEASUREMENT (MMT) PROGRAM

    Science.gov (United States)

    This manuscript presents the history and evolution of the U.S. Environmental Protection Agency's (EPA) Superfund Innovative Technology Evaluation (SITE) Monitoring and Measurement Technology (MMT) Program. This includes a discussion of how the fundamental concepts of a performanc...

  14. 76 FR 72405 - San Fernando Valley Area 2 Superfund Site; Notice of Proposed Prospective Purchaser Agreement Re...

    Science.gov (United States)

    2011-11-23

    ... From the Federal Register Online via the Government Publishing Office ENVIRONMENTAL PROTECTION AGENCY San Fernando Valley Area 2 Superfund Site; Notice of Proposed Prospective Purchaser Agreement Re: 4057 and 4059 Goodwin Avenue, Los Angeles, CA AGENCY: Environmental Protection Agency (EPA)....

  15. Physical and Chemical Characteristics and Disposal Ways of Sorting Waste in Shanghai%上海市分类垃圾理化特性分析及处置方式探讨

    Institute of Scientific and Technical Information of China (English)

    贾悦; 董晓丹; 夏苏湘; 李晓勇

    2013-01-01

    通过现场采样和室内试验,对上海市生活垃圾分类后干垃圾、湿垃圾的物理组成、含水率、容重、发热量、元素以及生化指标等理化特性进行了分析研究,并在此基础上探讨了分类垃圾的处置方式。结果表明:分类干垃圾有机物减少30%,而潜在可回收废物、易燃物均提高约75%,含水率、容重显著降低,而热值(湿基低位发热量)6881~7279 kJ/kg。适合作焚烧处置,利于处置效果的实现;分类湿垃圾有机物比重80%,含水率为72%,容重达304 kg/m3,热值(湿基低位发热量)低于2500 kJ/kg ,有机质、蛋白质、粗脂肪的含量占其干物质比例,分别为75%、14%、7%,是生化堆肥的良好材料。%This article studies the physical and chemical characteristics of the sorting waste (dry and wet waste)in Shanghai based on field sampling and laboratory testing ,and monitors the indexes including physical composition , moisture ,unit weight , calorific value , elements and biochemical indexes . And then it proposes some relevant treatment measures .The results show that ,for dry sorting waste ,the organic matter decreases by 30% ,while potentially recyclable waste and combustible materials increase about 75% , moisture and unit weight decrease significantly ,and the calorific value (wet low calorific value) is between 6881~7279 kJ/kg ,which is suitable for incineration disposal ;for wet sorting waste ,organic matter is 80% ,moisture is 72% ,unit weight is 304 kg/m3 , calorific value is lower than 2500 kJ/kg ,organic matter ,protein and fat content are respectively 75% ,14% and 7%of dry material proportion ,which is proved to be a good material for biochemical compost .

  16. Volatile Organic Compounds (VOCs) and Elevated Concentrations of Carbon Dioxide (CO2) in Unsaturated-Zone Vapors Near a Chemical and Low-Level Radioactivity Waste-Disposal Facility, Amargosa Desert Research Site, Nye County, Nevada

    Science.gov (United States)

    Baker, R. J.; Andraski, B. J.; Walvoord, M. A.; Stonestrom, D. A.; Prudic, D. E.; Luo, W.

    2003-12-01

    As part of its Toxic Substances Hydrology Program, the U.S. Geological Survey is studying contaminant-transport processes in an arid environment at the Amargosa Desert Research Site (http://nevada.usgs.gov/adrs/). The site is near waste-disposal facilities 20 kilometers east of Death Valley National Park. Low-level radioactive waste was buried in unlined trenches of varying depth during 1962-92. Hazardous chemical waste was buried in unlined trenches at an adjacent facility during 1970-88. Mean annual precipitation at the site from 1981 to 2000 was 108 millimeters. The unsaturated zone is aerobic down to the water table, which is about 110 m (meters) deep. Sampling infrastructure south and west of the facility includes a grid of vapor probes 1.5 m deep, a 23.8-m-deep background borehole (JFDB), and two approximately 100-m-deep boreholes (UZB-2 and UZB-3), which are 160 m and 100 m from the nearest trench, respectively, and are instrumented for multi-level sampling. Analytes detected in unsaturated-zone-vapor samples include elevated concentrations of tritium and carbon-14; three chlorofluorocarbon (CFC) compounds, eight chlorinated solvent compounds, and toluene, all at concentrations exceeding 1,000 parts per billion (ppb) in UZB-3, and at lower concentrations in UZB-2 and in the shallow-vapor-probe grid; and CO2 in concentrations up to 2% in UZB-3, whereas maximum CO2 concentrations in JFDB are less than 0.2%. With the notable exception of toluene, VOCs that are known to be highly biodegradable are generally absent or occur at low concentrations (1,000 ppb) in UZB-3 are relatively recalcitrant to biodegradation in this environment. 4. The similarity among their vertical and radial concentration profiles indicates that the same vapor-transport phenomena are responsible for the observed elevated levels of CO2, hydrocarbons, and radionuclides. The CO2- and VOC-concentration data will be used to enhance ongoing efforts to develop process-based models of contaminant

  17. The electro-thermal dynamic stripping process for the remediation of a creosote-contaminated superfund site

    Energy Technology Data Exchange (ETDEWEB)

    Northington, C.D. [WRS Infrastructure and Environment, Tampa, FL (United States); McGee, B.C.W. [McMillan-McGee Corp., Calgary, AB (Canada)

    2005-07-01

    Pump-and-treat is a conventional soil and groundwater contaminant removal method that depends on factors such as the chemical nature of the contaminant, subsurface heterogeneity, sorption of contaminants to subsurface materials, difficulties in characterizing the subsurface, and system design. The cleanup of dense non-aqueous phase liquids (DNAPLs) is further complicated by the uncertain contaminant fate due to the tendency of DNAPLs to migrate downward, where they become difficult to locate and where they become immobile residual globules and a long-term source of ground water contamination. This paper presents the results of a pilot scale study in which an in-situ thermal decontamination technology was tested. The technology known as the Electro-Thermal Dynamic Stripping Process{sup TM} (ET-DS), was developed for a creosote-contaminated Superfund site to show the effectiveness of full-scale implementation of this method over the currently used pump-and- treat system to address contamination in the source zone. The pilot study follows similar methods used by reservoir engineers in the evaluation of thermal recovery methods for the recovery of bitumen and heavy oil. ET-DS was field test in the oil sands in order to use some operating data from the pilot to design oil sand specific ET-DS.

  18. Geological disposal concept hearings

    International Nuclear Information System (INIS)

    The article outlines the progress to date on AECL spent-nuclear fuel geological disposal concept. Hearings for discussion, organised by the federal Environmental Assessment Review Panel, of issues related to this type of disposal method occur in three phases, phase I focuses on broad societal issues related to long term management of nuclear fuel waste; phase II will focus on the technical aspects of this method of disposal; and phase III will consist of community visits in New Brunswick, Quebec, Ontario, Manitoba and Saskatchewan. This article provides the events surrounding the first two weeks of phase I hearings (extracted from UNECAN NEWS). In the first week of hearings, where submissions on general societal issues was the focus, there were 50 presentations including those by Natural Resources Canada, Energy Probe, Ontario Hydro, AECL, Canadian Nuclear Society, Aboriginal groups, environmental activist organizations (Northwatch, Saskatchewan Environmental Society, the Inter-Church Uranium Committee, and the Canadian Coalition for Nuclear responsibility). In the second week of hearings there was 33 presentations in which issues related to siting and implementation of a disposal facility was the focus. Phase II hearings dates are June 10-14, 17-21 and 27-28 in Toronto

  19. Waste disposal package

    Science.gov (United States)

    Smith, M.J.

    1985-06-19

    This is a claim for a waste disposal package including an inner or primary canister for containing hazardous and/or radioactive wastes. The primary canister is encapsulated by an outer or secondary barrier formed of a porous ceramic material to control ingress of water to the canister and the release rate of wastes upon breach on the canister. 4 figs.

  20. Biomonitoring for metal contamination near two Superfund sites in Woburn, Massachusetts, using phytochelatins

    Energy Technology Data Exchange (ETDEWEB)

    Gawel, James E.; Hemond, Harold F

    2004-09-01

    Characterizing the spatial extent of groundwater metal contamination traditionally requires installing sampling wells, an expensive and time-consuming process in urban areas. Moreover, extrapolating biotic effects from metal concentrations alone is problematic, making ecological risk assessment difficult. Our study is the first to examine the use of phytochelatin measurements in tree leaves for delimiting biological metal stress in shallow, metal-contaminated groundwater systems. Three tree species (Rhamnus frangula, Acer platanoides, and Betula populifolia) growing above the shallow groundwater aquifer of the Aberjona River watershed in Woburn, Massachusetts, display a pattern of phytochelatin production consistent with known sources of metal contamination and groundwater flow direction near the Industri-Plex Superfund site. Results also suggest the existence of a second area of contaminated groundwater and elevated metal stress near the Wells G and H Superfund site downstream, in agreement with a recent EPA ecological risk assessment. Possible contamination pathways at this site are discussed.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1996-12-31

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

  2. Radioactivity in the industrial effluent disposed soil

    OpenAIRE

    Meenashisundaram V.; Narayanaswamy R.; Senthilkumar R. D.

    2012-01-01

    Studies on radiation and radioactivity distribution in the soils of effluent disposed from the sugar industry in India have been conducted. The external gamma dose rates in air and natural radionuclides activities in the soils were measured using an Environmental Radiation Dosimeter and a Gamma-ray Spectrometer respectively. The soil samples were also subject to various physico-chemical analyses. This study revealed some remarkable results that are discussed in the article.

  3. Radioactivity in the industrial effluent disposed soil

    Directory of Open Access Journals (Sweden)

    Meenashisundaram V.

    2012-04-01

    Full Text Available Studies on radiation and radioactivity distribution in the soils of effluent disposed from the sugar industry in India have been conducted. The external gamma dose rates in air and natural radionuclides activities in the soils were measured using an Environmental Radiation Dosimeter and a Gamma-ray Spectrometer respectively. The soil samples were also subject to various physico-chemical analyses. This study revealed some remarkable results that are discussed in the article.

  4. Radioactivity in the industrial effluent disposed soil

    Science.gov (United States)

    Senthilkumar, R. D.; Narayanaswamy, R.; Meenashisundaram, V.

    2012-04-01

    Studies on radiation and radioactivity distribution in the soils of effluent disposed from the sugar industry in India have been conducted. The external gamma dose rates in air and natural radionuclides activities in the soils were measured using an Environmental Radiation Dosimeter and a Gamma-ray Spectrometer respectively. The soil samples were also subject to various physico-chemical analyses. This study revealed some remarkable results that are discussed in the article.

  5. Hazardous materials waste disposal. 1977-June, 1980 (citations from the NTIS data base). Report for 1977-Jun 80

    Energy Technology Data Exchange (ETDEWEB)

    Cavagnaro, D.M.

    1980-06-01

    Topics relate to disposal of pesticides, explosives, chemical warfare agents, dangerous industrial chemicals, and other types of hazardous materials. The citations include research on management planning, spills, toxicity, water pollution abatement, and National Disposal Sites. Pollution studies related to disposal in landfills and by incineration are also covered as is deep mine disposal. Radioactive wastes are excluded. (This updated bibliography contains 217 abstracts, 38 of which are new entries to the previous edition.)

  6. Household Chemical Emergencies

    Science.gov (United States)

    ... and disposing of the material according to the manufacturer’s directions. It is critical to store household chemicals in places where children cannot access them. Remember that products such as aerosol cans of hair spray and deodorant, nail polish ...

  7. TRU waste disposal

    International Nuclear Information System (INIS)

    This paper reports on the U.S. Department of Energy's (DOE's) Waste Isolation Pilot Plant (WIPP) which is located on an arid 10,240 acre site in the remote Los Medanos (the dunes) region of the northern Chihuahuan desert in southeast New Mexico near Carlsbad. The mission of the WIPP is to demonstrate the safe, environmentally sound disposal of transuranic (TRU) waste resulting from the nation's defense program activities. Authorized by Congress in 1979 via Public Law 96-164, the WIPP represents a necessary, environmentally responsible, deep geologic disposal option. Initially thought to be subject to regulation under the Atomic Energy Act, further definition of the 1980 Resource Conservation and Recovery Act (RCRA) in 1986 and 1988 has made it clear that this demonstration must also show compliance with RCRA. The majority of retrievable TRU waste proposed and available for eventual disposal at the WIPP also contains hazardous constituents defined by RCRA, with the resultant mixed waste subject to its provisions

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

    International Nuclear Information System (INIS)

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

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

    Energy Technology Data Exchange (ETDEWEB)

    Cook, J.R.

    1997-09-01

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

  10. Electrochemical Disposal of Hydrazines in Water

    Science.gov (United States)

    Kim, Jinseong; Gonzalez-Mar, Anuncia; Salinas, Carlos; Rutherford, Larris; Jeng, King-Tsai; Andrews, Craig; Yalamanchili, Ratlaya

    2007-01-01

    An electrochemical method of disposal of hydrazines dissolved in water has been devised. The method is applicable to hydrazine (N2H4), to monomethyl hydrazine [also denoted by MMH or by its chemical formula, (CH3)HNNH2], and to unsymmetrical dimethyl hydrazine [also denoted UDMH or by its chemical formula, (CH3)2NNH2]. The method involves a room-temperature process that converts the hydrazine to the harmless products N2, H2O, and, in some cases, CO2

  11. XPERT DESIGN AND DIAGNOSTICS' (XDD) IN-SITU CHEMICAL OXIDATION PROCESS USING POTASSIUM PERMANGANATE (KMNO4)

    Science.gov (United States)

    Xpert Design and Diagnostic's (XDD)potassium permanganate in situ chemical oxidation (ISCO) process was evaluated under the EPA Superfund Innovative Technology Evaluation (SITE) Program at the former MEC Building site located in Hudson, New Hampshire. At this site, both soil and ...

  12. High level radioactive waste (HLW) disposal a global challenge

    CERN Document Server

    PUSCH, R; NAKANO, M

    2011-01-01

    High Level Radioactive Waste (HLW) Disposal, A Global Challenge presents the most recent information on proposed methods of disposal for the most dangerous radioactive waste and for assessing their function from short- and long-term perspectives. It discusses new aspects of the disposal of such waste, especially HLW.The book is unique in the literature in making it clear that, due to tectonics and long-term changes in rock structure, rock can serve only as a ""mechanical support to the chemical apparatus"" and that effective containment of hazardous elements can only be managed by properly des

  13. Records of wells and chemical analyses of water from wells for the period June 13, 1984 to December 4, 1986 at the Maxey Flats Radioactive Waste Disposal Site, Kentucky

    Science.gov (United States)

    Lyverse, M.A.

    1987-01-01

    Lithologic data are presented for 113 wells drilled at the Maxey Flats Radioactive Waste Disposal Site for the period June 13, 1984 to December 4, 1986. Water levels, tritium concentrations, and specific conductance are also presented for wells yielding sufficient water for measuring and sampling. At least one sample was collected from most wells for the determination of gross alpha and beta activity. These activities and the results for gamma emitting radionuclides (Cobalt 60 and Cesium 137) are also presented. (USGS)

  14. Radioactive waste disposal

    International Nuclear Information System (INIS)

    A deep gap, reflecting a persisting fear, separates the viewpoints of the experts and that of the public on the issue of the disposal of nuclear WASTES. The history of this field is that of the proliferation with time of spokesmen who pretend to speak in the name of the both humans and non humans involved. Three periods can be distinguished: 1940-1970, an era of contestation and confusion when the experts alone represents the interest of all; 1970-1990, an era of contestation and confusion when spokespersons multiply themselves, generating the controversy and the slowing down of most technological projects; 1990-, an era of negotiation, when viewpoints, both technical and non technical, tend to get closer and, let us be optimistic, leading to the overcome of the crisis. We show that, despite major differences, the options and concepts developed by the different actors are base on two categories of resources, namely Nature and Society, and that the consensus is built up through their 'hydridation'. we show in this part that the perception of nuclear power and, in particular of the underground disposal of nuclear wastes, involves a very deep psychological substrate. Trying to change mentalities in the domain by purely scientific and technical arguments is thus in vain. The practically instinctive fear of radioactivity, far from being due only to lack of information (and education), as often postulated by scientists and engineers, is rooted in archetypical structures. These were, without doubt, reactivated in the 40 s by the traumatizing experience of the atomic bomb. In addition, anthropological-linked considerations allow us to conclude that he underground disposal of wastes is seen as a 'rape' and soiling of Mother Earth. This contributes to explaining, beyond any rationality, the refusal of this technical option by some persons. However, it would naturally be simplistic and counter-productive to limit all controversy in this domain to these psychological aspects

  15. HLW Disposal System Development

    Energy Technology Data Exchange (ETDEWEB)

    Choi, J. W.; Choi, H. J.; Lee, J. Y. (and others)

    2007-06-15

    A KRS is suggested through design requirement analysis of the buffer and the canister which are the constituent of disposal system engineered barrier and HLW management plans are proposed. In the aspect of radionuclide retention capacity, the thickness of the buffer is determined 0.5m, the shape to be disc and ring and the dry density to be 1.6 g/cm{sup 3}. The maximum temperature of the buffer is below 100 .deg. which meets the design requirement. And bentonite blocks with 5 wt% of graphite showed more than 1.0 W/mK of thermal conductivity without the addition of sand. The result of the thermal analysis for proposed double-layered buffer shows that decrease of 7 .deg. C in maximum temperature of the buffer. For the disposal canister, the copper for the outer shell material and cast iron for the inner structure material is recommended considering the results analyzed in terms of performance of the canisters and manufacturability and the geochemical properties of deep groundwater sampled from the research area with granite, salt water intrusion, and the heavy weight of the canister. The results of safety analysis for the canister shows that the criticality for the normal case including uncertainty is the value of 0.816 which meets subcritical condition. Considering nation's 'Basic Plan for Electric Power Demand and Supply' and based on the scenario of disposing CANDU spent fuels in the first phase, the disposal system that the repository will be excavated in eight phases with the construction of the Underground Research Laboratory (URL) beginning in 2020 and commissioning in 2040 until the closure of the repository is proposed. Since there is close correlation between domestic HLW management plans and front-end/back-end fuel cycle plans causing such a great sensitivity of international environment factor, items related to assuring the non-proliferation and observing the international standard are showed to be the influential factor and acceptability

  16. Disposal - practical problems

    International Nuclear Information System (INIS)

    Most Polish power plants have stockyards for storage of fly ash and slag. This paper describes the: methods of fly ash and slag storage used, methods of conveying the waste to the stockpiles (by railway cars, trucks, belt conveyors or hydraulically); construction of wet stockyards and dry stockyards and comparison of the ash dumped, development of methods of ash disposal in mine workings; composition and properties of fly ash and slag from hard coal; and the effects of ash storage yards on the environment (by leaching of trace elements, dust, effect on soils, and noise of machinery). 16 refs., 3 figs., 6 tabs

  17. HLW Disposal System Development

    International Nuclear Information System (INIS)

    A KRS is suggested through design requirement analysis of the buffer and the canister which are the constituent of disposal system engineered barrier and HLW management plans are proposed. In the aspect of radionuclide retention capacity, the thickness of the buffer is determined 0.5m, the shape to be disc and ring and the dry density to be 1.6 g/cm3. The maximum temperature of the buffer is below 100 .deg. which meets the design requirement. And bentonite blocks with 5 wt% of graphite showed more than 1.0 W/mK of thermal conductivity without the addition of sand. The result of the thermal analysis for proposed double-layered buffer shows that decrease of 7 .deg. C in maximum temperature of the buffer. For the disposal canister, the copper for the outer shell material and cast iron for the inner structure material is recommended considering the results analyzed in terms of performance of the canisters and manufacturability and the geochemical properties of deep groundwater sampled from the research area with granite, salt water intrusion, and the heavy weight of the canister. The results of safety analysis for the canister shows that the criticality for the normal case including uncertainty is the value of 0.816 which meets subcritical condition. Considering nation's 'Basic Plan for Electric Power Demand and Supply' and based on the scenario of disposing CANDU spent fuels in the first phase, the disposal system that the repository will be excavated in eight phases with the construction of the Underground Research Laboratory (URL) beginning in 2020 and commissioning in 2040 until the closure of the repository is proposed. Since there is close correlation between domestic HLW management plans and front-end/back-end fuel cycle plans causing such a great sensitivity of international environment factor, items related to assuring the non-proliferation and observing the international standard are showed to be the influential factor and acceptability of HLW management

  18. Radioactive waste disposal

    International Nuclear Information System (INIS)

    The current disposal concept for radioactive waste in the FRG was discussed in the framework of this seminar. In addition to this concept for the treatment of radioactive waste also the volume of this waste is indicated. The present state of the two repositories 'Konrad' and 'Gorleben' is explained, as well as the requirements on waste packages for transportation, intermediate and ultimate storage. The final part discusses the conditioning of this radioactive waste and the control of the barrels as regards the observance of the requirements. (orig.)

  19. 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

  20. Geoenvironment and waste disposal

    International Nuclear Information System (INIS)

    Within the activities planned by UNESCO in its Water and Earth Science programme, an interdisciplinary meeting on geology and environment was scheduled by this organization to be held by the beginning of 1983. At this meeting it was intended to consider geological processes in the light of their interaction and influence on the environment with special emphasis on the impact of various means of waste disposal on geological environment and on man-induced changes in the geological environment by mining, human settlements, etc. Considering the increasing interest shown by the IAEA in the field, through environmental studies, site studies, and impact studies for nuclear facilities and particularly nuclear waste disposal, UNESCO expressed the wish to organize the meeting jointly so as to take into account the experience gained by the Agency, and in order to avoid any duplication in the activities of the two organizations. This request was agreed to by the IAEA Secretariat and as a result, the meeting was organized by both organizations and held at IAEA Headquarters in Vienna from 21-23 March 1983. The report of this meeting is herewith presented

  1. Canada's disposal concept

    International Nuclear Information System (INIS)

    A concept for the safe and permanent disposal of nuclear fuel wastes from Canada's CANDU reactors has been developed by Atomic Energy of Canada Ltd. (AECL). The waste would be placed in an engineered disposal vault 500 to 1000 m below the surface in plutonic rock of the Canadian Shield. The multiple barriers to retain the waste and retard the release of radioactivity would be the waste form, the containers, buffer and backfill, and the rock overlying the vault. Numerous research programmes have been carried out to develop the technology for the concept. These include work on materials corrosion and failure mechanisms to assess the performance of the used fuel containers. Predictive modelling has shown that more than 97% of ASTM Grade 2 titanium containers will retain their integrity, even under pessimistic assumptions, for 1200-6000 years after emplacement, and even longer times may be achieved with other grades of titanium or copper. Other research has been aimed at vault sealing, at site characterization for an underground research laboratory and at the development of a methodology for assessing radiological and environmental effects after closure of the facility. A review of the safety and environmental impacts of the concept is now being carried out by an independent panel appointed by the government. (2 figures, 3 references) (UK)

  2. EFFECTS OF SLASH DISPOSAL METHODS ON THE PHYSICAL AND CHEMICAL PROPERTIES OF SOIL ON THE HARVESTED SITES IN NORTHEAST CHINA%森林采伐迹地清理方式对迹地土壤理化性质的影响

    Institute of Scientific and Technical Information of China (English)

    王立海

    2002-01-01

    采伐剩余物迹地清理是森林作业的重要组成部分之一.本文通过在黑龙江省带岭林业局野外迹地取样和实验室分析,对森林采伐剩余物迹地清理方式对迹地土壤的影响进行了初步研究.结果表明,迹地清理方式对作业迹地土壤理化特性产生一定程度的影响,进而影响森林采伐后的迹地天然更新与苗木生长质量.研究结果还表明,火烧和堆积方法对迹地土壤物理特性影响不十分显著,但对土壤的化学特性影响十分显著,尤其是火烧迹地土壤养分流失程度差异比较显著.%Forest harvesting slash disposal is one of the important parts of forest operations. A field survey for investigating slash disposal was carried out in a forest sector in Heilongjiang Province, northeast China. Through the research, it is explicit that slash disposal has also affected on the physical and chemical properties of soil on the harvested sites. The presented results of this study show that both of piling method and burning method do not affect the physical properties of soil very much, but impact the chemical properties of soil quite significantly, and the burning method may cause soil erosion if handling poorly.

  3. Application of Generic Disposal System Models

    Energy Technology Data Exchange (ETDEWEB)

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

    2015-11-01

    This report describes specific GDSA activities in fiscal year 2015 (FY2015) toward the development of the enhanced disposal system modeling and analysis capability for geologic disposal of nuclear waste. The GDSA framework employs the PFLOTRAN thermal-hydrologic-chemical multi-physics code (Hammond et al., 2011) and the Dakota uncertainty sampling and propagation code (Adams et al., 2013). Each code is designed for massively-parallel processing in a high-performance computing (HPC) environment. Multi-physics representations in PFLOTRAN are used to simulate various coupled processes including heat flow, fluid flow, waste dissolution, radionuclide release, radionuclide decay and ingrowth, precipitation and dissolution of secondary phases, and radionuclide transport through the engineered barriers and natural geologic barriers to a well location in an overlying or underlying aquifer. Dakota is used to generate sets of representative realizations and to analyze parameter sensitivity.

  4. Bioactive contaminants leach from disposable laboratory plasticware.

    Science.gov (United States)

    McDonald, G Reid; Hudson, Alan L; Dunn, Susan M J; You, Haitao; Baker, Glen B; Whittal, Randy M; Martin, Jonathan W; Jha, Amitabh; Edmondson, Dale E; Holt, Andrew

    2008-11-01

    Disposable plasticware such as test tubes, pipette tips, and multiwell assay or culture plates are used routinely in most biological research laboratories. Manufacturing of plastics requires the inclusion of numerous chemicals to enhance stability, durability, and performance. Some lubricating (slip) agents, exemplified by oleamide, also occur endogenously in humans and are biologically active, and cationic biocides are included to prevent bacterial colonization of the plastic surface. We demonstrate that these manufacturing agents leach from laboratory plasticware into a standard aqueous buffer, dimethyl sulfoxide, and methanol and can have profound effects on proteins and thus on results from bioassays of protein function. These findings have far-reaching implications for the use of disposable plasticware in biological research. PMID:18988846

  5. Disposal in continental geologic formations

    International Nuclear Information System (INIS)

    Waste retrievability is the factor used to distinguish between waste storage and waste disposal alternatives. Disposal options assume no assured ability to retrieve wastes, while storage alternatives are predicted on a design allowing waste recovery for a specified period of time. The waste form, the emplacement method, and the time elapsed since emplacement are three factors that influence the degree of retrievability from a storage or disposal alternative. An overview of these and other factors and how they apply to various waste management storage and disposal alternatives is presented. The advantages, disadvantages and technical uncertainties associated with geologic waste disposal in very deep holes (greater than 10 km) are summarized. Deep well injection and hydrofracture disposal of selected liquid wastes are briefly reviewed. The geologic requirements for deep well injection and its applicability to tritiated water disposal are discussed. Hydrofracture has been used to dispose of intermediate level liquid wastes at ORNL, and the results to date of this disposal operation are presented. Three emplacement methods for radioactive waste storage and disposal on, in, or under ice sheets are described. Recent international comments on ice sheet disposal, reflecting concern about the lack of knowledge and predictability of long-term ice sheet stability, are presented. Four melting disposal alternatives are described. These techniques all use the thermal power density of high-level waste to bring the surrounding medium to its melting temperature range. The techniques primarily differ in emplacement geometry and the time to first melt and to final resolidification. The similarities and differences of these techniques are discussed

  6. Does Hazardous Waste Matter? Evidence from the Housing Market and the Superfund Program

    OpenAIRE

    Greenstone, Michael; Gallagher, Justin

    2005-01-01

    This paper uses the housing market to develop estimates of the local welfare impacts of Superfund sponsored clean-ups of hazardous waste sites.We show that if consumers value the clean-ups, then the hedonic model predicts that they will lead to increases in local housing prices and new home construction, as well as the migration of individuals that place a high value on environmental quality to the areas near the improved sites. We compare housing market outcomes in the areas surrounding the ...

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

    Science.gov (United States)

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

    2010-01-01

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

  8. Radwaste Disposal Safety Analysis

    International Nuclear Information System (INIS)

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

  9. Physiochemical technologies for HCB remediation and disposal: A review

    Energy Technology Data Exchange (ETDEWEB)

    Tong, Man [State Key Lab of Biogeology and Environmental Geology, China University of Geosciences, Wuhan 430074 (China); Environmental Science Research Institute, Huazhong University of Science and Technology, Wuhan 430074 (China); Yuan, Songhu, E-mail: yuansonghu622@hotmail.com [State Key Lab of Biogeology and Environmental Geology, China University of Geosciences, Wuhan 430074 (China)

    2012-08-30

    Highlights: Black-Right-Pointing-Pointer HCB contamination is still a serious environmental problem. Black-Right-Pointing-Pointer Physiochemical technologies for HCB remediation and disposal are reviewed. Black-Right-Pointing-Pointer Perspectives for most remediation technologies are proposed. Black-Right-Pointing-Pointer Pilot and large scale remediation and disposal are presented. - Abstract: Hexachlorobenzene (HCB) is one of the 12 persistent organic pollutants (POPs) listed in 'Stockholm Convention'. It is hydrophobic, toxic and persistent in the environment. Due to extensive use in the past, HCB contamination is still a serious environmental problem. Strong adsorption on solid particles makes the remediation difficult. This paper presents an overview of the physiochemical technologies for HCB remediation and disposal. The adsorption/desorption behavior of HCB is firstly described because it comprises the fundamental for most remediation technologies. Physiochemical technologies concerned mostly for HCB remediation and disposal, i.e., chemical enhanced washing, electrokinetic remediation, reductive dechlorination and thermal decomposition, are reviewed in terms of fundamentals, state of the art and perspectives. The other physiochemical technologies including chemical oxidation, radiation induced catalytic dechlorination, ultrasonic assisted treatment and mechanochemical dechlorination are also reviewed. The pilot and large scale tests on HCB remediation or disposal are summarized in the end. This review aims to provide useful information to researchers and practitioners regarding HCB remediation and disposal.

  10. Developments in management and technology of waste reduction and disposal.

    Science.gov (United States)

    Rushbrook, Philip

    2006-09-01

    Scandals and public dangers from the mismanagement and poor disposal of hazardous wastes during the 1960s and 1970s awakened the modern-day environmental movement. Influential publications such as "Silent Spring" and high-profile disposal failures, for example, Love Canal and Lekkerkerk, focused attention on the use of chemicals in everyday life and the potential dangers from inappropriate disposal. This attention has not abated and developments, invariably increasing expectations and tightening requirements, continue to be implemented. Waste, as a surrogate for environmental improvement, is a topic where elected representatives and administrations continually want to do more. This article will chart the recent changes in hazardous waste management emanating from the European Union legislation, now being implemented in Member States across the continent. These developments widen the range of discarded materials regarded as "hazardous," prohibit the use of specific chemicals, prohibit the use of waste management options, shift the emphasis from risk-based treatment and disposal to inclusive lists, and incorporate waste producers into more stringent regulatory regimes. The impact of the changes is also intended to provide renewed impetus for waste reduction. Under an environmental control system where only certainty is tolerated, the opportunities for innovation within the industry and the waste treatment and disposal sector will be explored. A challenging analysis will be offered on the impact of this regulation-led approach to the nature and sustainability of hazardous waste treatment and disposal in the future.

  11. Engineering analysis for disposal of depleted uranium tetrafluoride (UF4)

    International Nuclear Information System (INIS)

    This report presents and evaluates options for disposing of depleted uranium in the chemical form of uranium tetrafluoride (UF4). Two depleted uranium inventories are considered. One results from the original U.S. Department of Energy (DOE) inventory of 560,000 metric tons (te) of depleted uranium hexafluoride (UF6); the other inventory is the original DOE inventory augmented by 145,000 te of depleted UF6 from the United States Enrichment Corporation. Preconceptual designs are included for three disposal options: disposal in a vault, disposal in an engineered trench, and disposal in a deep mine cavity. The disposal container is taken to be either a 30-gallon drum or a 55-gallon drum. Descriptions of the facilities associated with the three disposal options are provided. Staffing estimates for the construction and operation of the facilities are also provided. Wastes and emissions from the facilities during construction, operation, and maintenance have been estimated. Parametric studies have also been performed on the basis of 25% and 50% of the original inventory

  12. Grouting as a waste immobilization/disposal method

    International Nuclear Information System (INIS)

    Many options are available today for the immobilization and disposal of wastes that contain environmentally harmful materials. The option chosen depends upon the type of waste, regulatory requirements, and economics of process. Some options are specific to a given waste type; others are more versatile. This presentation discusses a very versatile option for waste immobilization/disposal, i.e. grouting. Many types of grout are available, such as chemical, clays or other particulates, fly ash, cements, or a combination of these. Within the limited allowable time, this presentation discusses the application of a variety of cement-based grouting techniques available for disposal of environmentally harmful materials. Areas discussed are in situ grouting of pits, ponds and lagoons, grouting as remedial action, and fixation for disposal in burial trenches or vaults

  13. Underground disposal of radioactive wastes

    International Nuclear Information System (INIS)

    This report is an overview document for the series of IAEA reports dealing with underground waste disposal to be prepared in the next few years. It provides an introduction to the general considerations involved in implementing underground disposal of radioactive wastes. It suggests factors to be taken into account for developing and assessing waste disposal concepts, including the conditioned waste form, the geological containment and possible additional engineered barriers. These guidelines are general so as to cover a broad range of conditions. They are generally applicable to all types of underground disposal, but the emphasis is on disposal in deep geological formations. Some information presented here may require slight modifications when applied to shallow ground disposal or other types of underground disposal. Modifications may also be needed to reflect local conditions. In some specific cases it may be that not all the considerations dealt with in this book are necessary; on the other hand, while most major considerations are believed to be included, they are not meant to be all-inclusive. The book primarily concerns only underground disposal of the wastes from nuclear fuel cycle operations and those which arise from the use of isotopes for medical and research activities

  14. Integrated Disposal Facility Risk Assessment

    International Nuclear Information System (INIS)

    An environmental risk assessment associated with the disposal of projected Immobilized Low-Activity Waste, solid wastes and failed or decommissioned melters in an Integrated Disposal Facility was performed. Based on the analyses all performance objectives associated with the groundwater, air, and intruder pathways were met

  15. Integrated Disposal Facility Risk Assessment

    Energy Technology Data Exchange (ETDEWEB)

    MANN, F. M.

    2003-06-03

    An environmental risk assessment associated with the disposal of projected Immobilized Low-Activity Waste, solid wastes and failed or decommissioned melters in an Integrated Disposal Facility was performed. Based on the analyses all performance objectives associated with the groundwater, air, and intruder pathways were met.

  16. Melter Disposal Strategic Planning Document

    Energy Technology Data Exchange (ETDEWEB)

    BURBANK, D.A.

    2000-09-25

    This document describes the proposed strategy for disposal of spent and failed melters from the tank waste treatment plant to be built by the Office of River Protection at the Hanford site in Washington. It describes program management activities, disposal and transportation systems, leachate management, permitting, and safety authorization basis approvals needed to execute the strategy.

  17. EPA RREL's mobile volume reduction unit advances soil washing at four Superfund sites

    International Nuclear Information System (INIS)

    Research testing of the US. Environmental Protection Agency (EPA) Risk Reduction Engineering Laboratory's (RREL) Volume Reduction Unit (VRU), produced data helping advance soil washing as a remedial technology for contaminated soils. Based on research at four Superfund sites, each with a different matrix of organic contaminants, EPA evaluated the soil technology and provided information to forecast realistic, full-scale remediation costs. Primarily a research tool, the VRU is RREL's mobile test unit for investigating the breadth of this technology. During a Superfund Innovative Technology Evaluation (SITE) Demonstration at Escambia Wood Treating Company Site, Pensacola, FL, the VRU treated soil contaminated with pentachlorophenol (PCP) and polynuclear aromatic hydrocarbon-laden creosote (PAH). At Montana Pole and Treatment Plant Site, Butte, MT, the VRU treated soil containing PCP mixed with diesel oil (measured as total petroleum hydrocarbons) and a trace of dioxin. At Dover Air Force Base Site, Dover, DE, the VRU treated soil containing JP-4 jet fuel, measured as TPHC. At Sand Creek Site, Commerce City, CO, the feed soil at this site was contaminated with two pesticides: heptachlor and dieldrin. Less than 10 percent of these pesticides remained in the treated coarse soil fractions

  18. Basic research needs for management and disposal of DOE wastes

    International Nuclear Information System (INIS)

    This document was chartered by the Department of Energy (DOE), Office of Energy Research. It identifies and describes 87 basic research needs in support of advanced technology for management and disposal of Department of Energy radioactive, hazardous chemical, and mixed wastes. A team of scientists and engineers from several DOE laboratories and sites, from academia, and from industry identified and described the basic research needs called out in this report. Special efforts were made to ensure that basic research needs related to management and disposal of any hazardous chemical wastes generated at nonnuclear DOE sites and facilities were properly identified. It is hoped that scientists in both DOE and nongovernment laboratories and institutions will find this document useful when formulating research efforts relevant to waste management and disposal. For management and disposal of DOE radioactive and mixed wastes, basic research needs are identified in nine separate action areas. Basic research needs for management and disposal of DOE hazardous chemical wastes are identified in five action areas. Sufficient description and background information are provided in the report for each particular research need to enable qualified and imaginative scientists to conceive research efforts and programs that will meet the need. 28 refs., 7 tabs

  19. Salt disposal of heat-generating nuclear waste.

    Energy Technology Data Exchange (ETDEWEB)

    Leigh, Christi D. (Sandia National Laboratories, Carlsbad, NM); Hansen, Francis D.

    2011-01-01

    This report summarizes the state of salt repository science, reviews many of the technical issues pertaining to disposal of heat-generating nuclear waste in salt, and proposes several avenues for future science-based activities to further the technical basis for disposal in salt. There are extensive salt formations in the forty-eight contiguous states, and many of them may be worthy of consideration for nuclear waste disposal. The United States has extensive experience in salt repository sciences, including an operating facility for disposal of transuranic wastes. The scientific background for salt disposal including laboratory and field tests at ambient and elevated temperature, principles of salt behavior, potential for fracture damage and its mitigation, seal systems, chemical conditions, advanced modeling capabilities and near-future developments, performance assessment processes, and international collaboration are all discussed. The discussion of salt disposal issues is brought current, including a summary of recent international workshops dedicated to high-level waste disposal in salt. Lessons learned from Sandia National Laboratories' experience on the Waste Isolation Pilot Plant and the Yucca Mountain Project as well as related salt experience with the Strategic Petroleum Reserve are applied in this assessment. Disposal of heat-generating nuclear waste in a suitable salt formation is attractive because the material is essentially impermeable, self-sealing, and thermally conductive. Conditions are chemically beneficial, and a significant experience base exists in understanding this environment. Within the period of institutional control, overburden pressure will seal fractures and provide a repository setting that limits radionuclide movement. A salt repository could potentially achieve total containment, with no releases to the environment in undisturbed scenarios for as long as the region is geologically stable. Much of the experience gained from

  20. Disposal of Savannah River Plant waste salt

    International Nuclear Information System (INIS)

    Proposed NRC guidelines for the disposal of waste with the radionuclide content of SRP salt would permit shallow land burial. Federal and state rules require that potentially hazardous chemical wastes (mainly nitrate-nitrite salts in the saltcrete) be contained to the degree necessary to meet drinking water standards in the ground water beneath the landfill boundary. This paper describes the proposed saltcrete landfill and tests under way to ensure that the landfill meet these criteria. The work includes laboratory and field tests of the saltcrete itself, a field test of a one-tenth linear scale model of the entire landfill system, and a numerical model of the system

  1. Preparations for Mixed Waste Disposal at the Nevada Test Site

    International Nuclear Information System (INIS)

    The Radioactive Waste Management Complex (RWMC) at the Nevada Test Site (NTS) is preparing for the receipt and disposal of low-level mixed waste (MV) generated within the U.S. Department of Energy (DOE) complex. The NTS maintains and develops disposal locations to accommodate various waste forms, and is engaged in developing verification and handling processes to ensure proper acceptance and disposal. Operations at the RWMC are focused on ensuring future disposal needs can be accommodated with a maximum benefit to risk ratio. This paper addresses the programmatic developments implemented at the NTS to accommodate the receipt, verification, and disposal of MW. The Radioactive Waste Acceptance Program (RWAP) has incorporated aspects of the Waste Analysis Plan (WAP) into the Nevada Test Site Waste Acceptance Criteria (NTSWAC). The verification program includes statistical sampling components that take into account waste form, program reliability, and other factors. The WAP allows for a conglomerate of verification techniques including visual examination, non-destructive examination, and chemical screening ensuring compliance with the NTSWAC. The WAP also provides for the acceptance of MW with most U.S. Environmental Protection Agency waste codes. The MW sent to the NTS for disposal must meet Land-Disposal Restriction standards. To support the verification processes outlined in the WAP, a Real-Time-Radiography (RTR) facility was constructed. Using a 450 keV, 5-mA tube-head system with a bridge and manipulator assembly, MW packages can undergo non-destructive examination (x-ray) at the RWMC. Prior to the NTS accepting the waste shipment, standard waste boxes, drums, and nominally sized bulk items can be manipulated on a cart and examined directly or skewed in real-time to ensure compliance with NTSWAC requirement s An existing MW disposal cell at the RWMC has been tailored to meet the requirements of a Category 2 non-reactor Nuclear Facility. In retrofitting an existing

  2. Chemical, zooplankton, phytoplankton, and other data from moored current meter casts and other instruments in the Gulf of Mexico during the Brine Disposal project, 07 September 1982 - 30 November 1982 (NODC Accession 8300075)

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — Chemical, phytoplankton, zooplankton, and other data were collected using moored current meter casts and other instruments in the Gulf of Mexico from September 7,...

  3. Current direction, chemical, zooplankton, and other data from moored current meter casts and other instruments in the Gulf of Mexico during the Brine Disposal project, 22 September 1978 - 22 January 1979 (NODC Accession 7900212)

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — Current direction, chemical, zooplankton, and other data were collected using moored current meter casts and other instruments in the Gulf of Mexico from September...

  4. Chemical, zooplankton, phytoplankton, and other data from moored current meter casts and other instruments in the Gulf of Mexico during the Brine Disposal project, 17 February 1981 - 27 May 1982 (NODC Accession 8200183)

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — Chemical, phytoplankton, zooplankton, and other data were collected using moored current meter casts and other instruments in the Gulf of Mexico from February 17,...

  5. Current direction, chemical, zooplankton, phytoplankton, and other data from moored current meter casts and other instruments in the Gulf of Mexico during the Brine Disposal project, 24 January 1980 - 22 June 1981 (NODC Accession 8100704)

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — Current direction, chemical, phytoplankton, zooplankton, and other data were collected using moored current meter casts and other instruments in the Gulf of Mexico...

  6. Current direction, chemical, phytoplankton, and other data from moored current meter casts and other instruments in the Gulf of Mexico during the Brine Disposal project, 21 November 1977 to 09 September 1981 (NODC Accession 8200008)

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — Current direction, chemical, phytoplankton, zooplankton, and other data were collected using moored current meter casts and other instruments in the Gulf of Mexico...

  7. Chemical, phytoplankton, zooplankton, and other data from moored current meter casts and other instruments in the Gulf of Mexico during the Brine Disposal project, 17 April 1980 - 17 July 1981 (NODC Accession 8100731)

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — Current direction, chemical, phytoplankton, zooplankton, and other data were collected using moored current meter casts and other instruments in the Gulf of Mexico...

  8. Current direction, benthic organisms, zooplankton, chemical, toxis substances, and other data from moored current meter casts and other instruments in the Gulf of Mexico during the Brine Disposal project, 24 March 1981 - 19 February 1982 (NODC Accession 8200129)

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — Current direction, benthic organisms, zooplankton, chemical, toxic substances, and other data were collected using moored current meter casts and other instruments...

  9. Chemical, zooplankton, and marine toxic substances data from moored current meter casts and other instruments in the Gulf of Mexico during the Brine Disposal project, 02 June 1978 - 02 June 1979 (NODC Accession 8000002)

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — Chemical, zooplankton, and marine toxic substances data were collected using moored current meter casts and other instruments in the Gulf of Mexico from June 2,...

  10. Chemical, benthic organisms, zooplankton, marine toxic substances, and other data from moored current meter casts and other instruments in the Gulf of Mexico during the Brine Disposal project, 30 August 1979 - 21 September 1981 (NODC Accession 8200012)

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — Chemical, marine toxic substances, benthic organisms, zooplankton, and other data were collected using moored current meter casts and other instruments in the Gulf...

  11. Current direction, chemical, and other data from moored current meter casts and other instruments in the Gulf of Mexico during the Brine Disposal project, 13 December 1980 - 01 March 1982 (NODC Accession 8200097)

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — Current direction, chemical, and other data were collected using moored current meter casts and other instruments in the Gulf of Mexico from December 13, 1980 to...

  12. Current direction, chemical, phytoplankton, zooplankton, and other data from moored current meter casts and other instruments in the Gulf of Mexico during the Brine Disposal project, 15 September 1977 - 27 May 1981 (NODC Accession 8100657)

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — Current direction, chemical, phytoplankton, zooplankton, and other data were collected using moored current meter casts and other instruments in the Gulf of Mexico...

  13. Current direction, chemical, benthic organisms, and wind wave spectra data from moored current meter casts and other instruments in the Gulf of Mexico as part of the Brine Disposal project, 14 October 1977 - 24 August 1979 (NODC Accession 7900335)

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — Current direction, chemical, benthic organisms, and wind direction data were collected using moored current meter casts and other instruments in the Gulf of Mexico...

  14. Chemical, phytoplankton, zooplankton, benthic organisms, and other data from moored current meter casts and other instruments in the Gulf of Mexico during the Brine Disposal project, 12 February 1981 - 05 January 1982 (NODC Accession 8200064)

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — Chemical, phytoplankton, benthic organisms, zooplankton, and other data were collected using moored current meter casts and other instruments in the Gulf of Mexico...

  15. Current direction, chemical, benthic organisms, and other data from moored current meter casts and other instruments in the Gulf of Mexico during the Brine Disposal project, 21 January 1981 - 27 July 1982 (NODC Accession 8200207)

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — Current direction, chemical, benthic organisms, and other data were collected using moored current meter casts and other instruments in the Gulf of Mexico from...

  16. Current direction, chemical, zooplankton, phytoplankton, and other data from moored current meter casts and other instruments in the Gulf of Mexico during the Brine Disposal project, 19 February 1982 - 23 March 1983 (NODC Accession 8300099)

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — Current direction, chemical, phytoplankton, zooplankton, and other data were collected using moored current meter casts and other instruments in the Gulf of Mexico...

  17. Current direction, chemical, benthic organisms, and other data from moored current meter casts and other instruments in the Gulf of Mexico during the Brine Disposal project, 10 March 1980 - 29 July 1981 (NODC Accession 8100727)

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — Current direction, chemical, benthic organisms, and other data were collected using moored current meter casts and other instruments in the Gulf of Mexico from...

  18. Chemical data from moored current meter, bottle casts, and other instruments in the Gulf of Mexico during the Brine Disposal project, 23 June 1978 - 30 June 1978 (NODC Accession 7900006)

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — Chemical data were collected using moored current meter, bottle casts, and other instruments in the Gulf of Mexico from June 18, 1978 to June 24, 1981. Data were...

  19. Current direction, chemical, and marine toxic substances data from moored current meter casts and other instruments in the Gulf of Mexico during the Brine Disposal project, 09 September 1978 - 19 November 1979 (NODC Accession 8000043)

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — Current direction, marine toxic substances, and chemical data were collected using moored current meter casts and other instruments in the Gulf of Mexico from...

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2013-07-29

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

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

    International Nuclear Information System (INIS)

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

  2. Waste and Disposal: Research and Development

    Energy Technology Data Exchange (ETDEWEB)

    Neerdael, B.; Marivoet, J.; Put, M.; Van Iseghem, P

    2002-04-01

    This contribution to the annual report describes the main activities of the Waste and Disposal Department of the Belgian Nuclear Research Center SCK-CEN. Achievements in 2001 in three topical areas are reported on: performance assessments (PA), waste forms/packages and near- and far field studies. Performance assessment calculations were made for the geological disposal of high-level and long-lived waste in a clay formation. SCK-CEN partcipated in several PA projects supported by the European Commission. In the BENIPA project, the role of bentonite barriers in performance assessments of HLW disposal systems is evaluated. The applicability of various output variables (concentrations, fluxes) as performance and safety indicators is investigated in the SPIN project. The BORIS project investigates the chemical behaviour and the migration of radionuclides at the Borehole injection site at Krasnoyarsk-26 and Tomsk-7. SCK-CEN contributed to an impact assessment of a radium storage facility at Olen (Belgium) and conducted PA for site-specific concepts regarding surface or deep disposal of low-level waste at the nuclear zones in the Mol-Dessel region. As regards R and D on waste forms and packages, SCK continued research on the compatbility of various waste forms (bituminised waste, vitrified waste, spent fuel) with geological disposal in clay. Main emphasis in 2001 was on corrosion studies on vitrified high-level waste, the investigation of localised corrosion of candidate container and overpack materials and the study of the effect of the degradation of cellulose containing waste as well as of bituminized waste on the solubility and the sorption of Pu and Am in geological disposal conditions in clay. With regard to near- and far-field studies, percolation and diffusion experiments to determine migration parameters of key radionuclides were continued. The electromigration technique was used to study the migration of redox sensitive species like uranium. In addition to

  3. Geological disposal system development

    International Nuclear Information System (INIS)

    Spent fuel inventories to be disposed of finally and design base spent fuel were determined. Technical and safety criteria for a geological repository system in Korea were established. Based on the properties of spent PWR and CANDU fuels, seven repository alternatives were developed and the most promising repository option was selected by the pair-wise comparison method from the technology point of view. With this option preliminary conceptual design studies were carried out. Several module, e.g., gap module, congruent release module were developed for the overall assessment code MASCOT-K. The prominent overseas databases such as OECD/NEA FEP list were are fully reviewed and then screened to identify the feasible ones to reflect the Korean geo-hydrological conditions. In addition to this the well known scenario development methods such as PID, RES were reviewed. To confirm the radiological safety of the proposed KAERI repository concept the preliminary PA was pursued. Thermo-hydro-mechanical analysis for the near field of repository were performed to verify thermal and mechanical stability for KAERI repository system. The requirements of buffer material were analyzed, and based on the results, the quantitative functional criteria for buffer material were established. The hydraulic and swelling property, mechanical properties, and thermal conductivity, the organic carbon content, and the evolution of pore water chemistry were investigated. Based on the results, the candidate buffer material was selected

  4. Geological disposal system development

    Energy Technology Data Exchange (ETDEWEB)

    Kang, Chul Hyung; Kuh, J. E.; Kim, S. K. and others

    2000-04-01

    Spent fuel inventories to be disposed of finally and design base spent fuel were determined. Technical and safety criteria for a geological repository system in Korea were established. Based on the properties of spent PWR and CANDU fuels, seven repository alternatives were developed and the most promising repository option was selected by the pair-wise comparison method from the technology point of view. With this option preliminary conceptual design studies were carried out. Several module, e.g., gap module, congruent release module were developed for the overall assessment code MASCOT-K. The prominent overseas databases such as OECD/NEA FEP list were are fully reviewed and then screened to identify the feasible ones to reflect the Korean geo-hydrological conditions. In addition to this the well known scenario development methods such as PID, RES were reviewed. To confirm the radiological safety of the proposed KAERI repository concept the preliminary PA was pursued. Thermo-hydro-mechanical analysis for the near field of repository were performed to verify thermal and mechanical stability for KAERI repository system. The requirements of buffer material were analyzed, and based on the results, the quantitative functional criteria for buffer material were established. The hydraulic and swelling property, mechanical properties, and thermal conductivity, the organic carbon content, and the evolution of pore water chemistry were investigated. Based on the results, the candidate buffer material was selected.

  5. Status report on the disposal of radioactive wastes

    Energy Technology Data Exchange (ETDEWEB)

    Culler, F.L. Jr.; McLain, S. (comps.)

    1957-06-25

    A comprehensive survey of waste disposal techniques, requirements, costs, hazards, and long-range considerations is presented. The nature of high level wastes from reactors and chemical processes, in the form of fission product gases, waste solutions, solid wastes, and particulate solids in gas phase, is described. Growth predictions for nuclear reactor capacity and the associated fission product and transplutonic waste problem are made and discussed on the basis of present knowledge. Biological hazards from accumulated wastes and potential hazards from reactor accidents, ore and feed material processing, chemical reprocessing plants, and handling of fissionable and fertile material after irradiation and decontamination are surveyed. The waste transportation problem is considered from the standpoints of magnitude of the problem, present regulations, costs, and cooling periods. The possibilities for ultimate waste management and/or disposal are reviewed and discussed. The costs of disposal, evaporation, storage tanks, and drum-drying are considered.

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

    Science.gov (United States)

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

    2016-01-01

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

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

    Science.gov (United States)

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

    2016-10-01

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

  8. 10 CFR 61.50 - Disposal site suitability requirements for land disposal.

    Science.gov (United States)

    2010-01-01

    ... could erode or inundate waste disposal units. (7) The disposal site must provide sufficient depth to the... fluctuation of the water table. (8) The hydrogeologic unit used for disposal shall not discharge ground water... DISPOSAL OF RADIOACTIVE WASTE Technical Requirements for Land Disposal Facilities § 61.50 Disposal......

  9. Disposable diapers: a hygienic alternative.

    Science.gov (United States)

    Kamat, Maithili; Malkani, Ram

    2003-11-01

    The use of disposable diapers has offered improved health care benefits. Urine and fecal matter leakage from the cloth nappies and the hand-to-mouth behavior in infants leads to many illnesses with a feco-oral mode of transmission. Also, the tender skin of the infant is more prone to nappy rash. The modern age disposable diapers, when compared to cloth nappy, have displayed a superior ability in containment of urine and feces, thereby reducing contamination and transmission of infection. Also disposable diapers contain Super Absorbent Material (SAM) that successfully reduces the incidence of nappy rash. PMID:14703226

  10. Avaliação das técnicas de precipitação química e encapsulamento no tratamento e destinação conjunta de resíduos líquidos contendo cromo e vidrarias de laboratório Evaluation of chemical precipitation and encapsulation techniques in the treatment and joint disposal of liquid wastes containing chromium and laboratory glassware

    Directory of Open Access Journals (Sweden)

    Juliana Graciela Giovannini

    2008-01-01

    Full Text Available In this paper, we present procedures for the treatment and final disposal of residual solutions containing chromium, in order to evaluate the effectiveness of chemical precipitation of the metal and the potential of the glass encapsulation technique, using broken laboratory glassware. The results demonstrated that pH-values convenient for chemical precipitation are between 10 - 11. With regard to Cr(OH3 encapsulation, the leaching and solubilization tests allowed to classify the waste as non-dangerous and non-inert. Finally, it is pointed out that the adoption of waste management practices in universities should be encouraged, helping to train professionals skilled in good laboratory practices.

  11. Coffee Stirrers and Drinking Straws as Disposable Spatulas

    Science.gov (United States)

    Turano, Morgan A.; Lobuono, Cinzia; Kirschenbaum, Louis J.

    2015-01-01

    Although metal spatulas are damaged through everyday use and become discolored and corroded by chemical exposure, plastic drinking straws are inexpensive, sterile, and disposable, reducing the risk of cross-contamination during laboratory procedures. Drinking straws are also useful because they come in a variety of sizes; narrow sample containers…

  12. 78 FR 8194 - Exemption of Material for Proposed Disposal Procedures for the Westinghouse Electric Company, LLC...

    Science.gov (United States)

    2013-02-05

    ... Unit 1 at the HDP is Alternative 4: Removal, Treatment of Volatile Organic ] Compound Waste, and Off-site Disposal of Low-Level Radioactive Waste (LLRW) and Non-Hazardous Treatment Residues. The no-action... chemically hazardous waste. This is the same facility that was evaluated as an alternative disposal site...

  13. Hydrogeologic characterization and assessment of bioremediation of chlorinated benzenes and benzene in wetland areas, Standard Chlorine of Delaware, Inc. Superfund Site, New Castle County, Delaware, 2009-12

    Science.gov (United States)

    Lorah, Michelle M.; Walker, Charles W.; Baker, Anna C.; Teunis, Jessica A.; Majcher, Emily H.; Brayton, Michael J.; Raffensperger, Jeff P.; Cozzarelli, Isabelle M.

    2014-01-01

    Wetlands at the Standard Chlorine of Delaware, Inc. Superfund Site (SCD) in New Castle County, Delaware, are affected by contamination with chlorobenzenes and benzene from past waste storage and disposal, spills, leaks, and contaminated groundwater discharge. In cooperation with the U.S. Environmental Protection Agency, the U.S. Geological Survey began an investigation in June 2009 to characterize the hydrogeology and geochemistry in the wetlands and assess the feasibility of monitored natural attenuation and enhanced bioremediation as remedial strategies. Groundwater flow in the wetland study area is predominantly vertically upward in the wetland sediments and the underlying aquifer, and groundwater discharge accounts for a minimum of 47 percent of the total discharge for the subwatershed of tidal Red Lion Creek. Thus, groundwater transport of contaminants to surface water could be significant. The major contaminants detected in groundwater in the wetland study area included benzene, monochlorobenzene, and tri- and di-chlorobenzenes. Shallow wetland groundwater in the northwest part of the wetland study area was characterized by high concentrations of total chlorinated benzenes and benzene (maximum about 75,000 micrograms per liter [μg/L]), low pH, and high chloride. In the northeast part of the wetland study area, wetland groundwater had low to moderate concentrations of total chlorinated benzenes and benzene (generally not greater than 10,000 μg/L), moderate pH, and high sulfate concentrations. Concentrations in the groundwater in excess of 1 percent of the solubility of the individual chlorinated benzenes indicate that a contaminant source is present in the wetland sediments as dense nonaqueous phase liquids (DNAPLs). Consistently higher contaminant concentrations in the shallow wetland groundwater than deeper in the wetland sediments or the aquifer also indicate a continued source in the wetland sediments, which could include dissolution of DNAPLs and

  14. Radioactive waste processing and disposal

    International Nuclear Information System (INIS)

    This compilation contains 4144 citations of foreign and domestic reports, journal articles, patents, conference proceedings, and books pertaining to radioactive waste processing and disposal. Five indexes are provided: Corporate Author, Personal Author, Subject, Contract Number, and Report Number

  15. Monitoring methods for nuclear fuel waste disposal

    Energy Technology Data Exchange (ETDEWEB)

    Cooper, R.B.; Barnard, J.W.; Bird, G.A. [and others

    1997-11-01

    This report examines a variety of monitoring activities that would likely be involved in a nuclear fuel waste disposal project, during the various stages of its implementation. These activities would include geosphere, environmental, vault performance, radiological, safeguards, security and community socioeconomic and health monitoring. Geosphere monitoring would begin in the siting stage and would continue at least until the closure stage. It would include monitoring of regional and local seismic activity, and monitoring of physical, chemical and microbiological properties of groundwater in rock and overburden around and in the vault. Environmental monitoring would also begin in the siting stage, focusing initially on baseline studies of plants, animals, soil and meteorology, and later concentrating on monitoring for changes from these benchmarks in subsequent stages. Sampling designs would be developed to detect changes in levels of contaminants in biota, water and air, soil and sediments at and around the disposal facility. Vault performance monitoring would include monitoring of stress and deformation in the rock hosting the disposal vault, with particular emphasis on fracture propagation and dilation in the zone of damaged rock surrounding excavations. A vault component test area would allow long-term observation of containers in an environment similar to the working vault, providing information on container corrosion mechanisms and rates, and the physical, chemical and thermal performance of the surrounding sealing materials and rock. During the operation stage, radiological monitoring would focus on protecting workers from radiation fields and loose contamination, which could be inhaled or ingested. Operational zones would be established to delineate specific hazards to workers, and movement of personnel and materials between zones would be monitored with radiation detectors. External exposures to radiation fields would be monitored with dosimeters worn by

  16. Monitoring methods for nuclear fuel waste disposal

    International Nuclear Information System (INIS)

    This report examines a variety of monitoring activities that would likely be involved in a nuclear fuel waste disposal project, during the various stages of its implementation. These activities would include geosphere, environmental, vault performance, radiological, safeguards, security and community socioeconomic and health monitoring. Geosphere monitoring would begin in the siting stage and would continue at least until the closure stage. It would include monitoring of regional and local seismic activity, and monitoring of physical, chemical and microbiological properties of groundwater in rock and overburden around and in the vault. Environmental monitoring would also begin in the siting stage, focusing initially on baseline studies of plants, animals, soil and meteorology, and later concentrating on monitoring for changes from these benchmarks in subsequent stages. Sampling designs would be developed to detect changes in levels of contaminants in biota, water and air, soil and sediments at and around the disposal facility. Vault performance monitoring would include monitoring of stress and deformation in the rock hosting the disposal vault, with particular emphasis on fracture propagation and dilation in the zone of damaged rock surrounding excavations. A vault component test area would allow long-term observation of containers in an environment similar to the working vault, providing information on container corrosion mechanisms and rates, and the physical, chemical and thermal performance of the surrounding sealing materials and rock. During the operation stage, radiological monitoring would focus on protecting workers from radiation fields and loose contamination, which could be inhaled or ingested. Operational zones would be established to delineate specific hazards to workers, and movement of personnel and materials between zones would be monitored with radiation detectors. External exposures to radiation fields would be monitored with dosimeters worn by

  17. Americium product solidification and disposal

    International Nuclear Information System (INIS)

    The americium product from the TRUEX processing plant needs to be converted into a form suitable for ultimate disposal. An evaluation of the disposal based on safety, number of process steps, demonstrated operability of the processes, production of low-level alpha waste streams, and simplicity of maintenance with low radiation exposures to personnel during maintenance, has been made. The best process is to load the americium on a cation exchange resin followed by calcination or oxidation of the resin after loading

  18. Final disposal of radioactive waste

    OpenAIRE

    Freiesleben H.

    2013-01-01

    In this paper the origin and properties of radioactive waste as well as its classification scheme (low-level waste – LLW, intermediate-level waste – ILW, high-level waste – HLW) are presented. The various options for conditioning of waste of different levels of radioactivity are reviewed. The composition, radiotoxicity and reprocessing of spent fuel and their effect on storage and options for final disposal are discussed. The current situation of final waste disposal in a selected number of c...

  19. Near-surface land disposal

    International Nuclear Information System (INIS)

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

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

    Science.gov (United States)

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

    2015-07-16

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

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

    Science.gov (United States)

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

    2015-01-01

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

  2. Raman spectroscopy of efflorescent sulfate salts from Iron Mountain Mine Superfund Site, California

    Science.gov (United States)

    Sobron, Pablo; Alpers, Charles N.

    2013-01-01

    The Iron Mountain Mine Superfund Site near Redding, California, is a massive sulfide ore deposit that was mined for iron, silver, gold, copper, zinc, and pyrite intermittently for nearly 100 years. As a result, both water and air reached the sulfide deposits deep within the mountain, producing acid mine drainage consisting of sulfuric acid and heavy metals from the ore. Particularly, the drainage water from the Richmond Mine at Iron Mountain is among the most acidic waters naturally found on Earth. The mineralogy at Iron Mountain can serve as a proxy for understanding sulfate formation on Mars. Selected sulfate efflorescent salts from Iron Mountain, formed from extremely acidic waters via drainage from sulfide mining, have been characterized by means of Raman spectroscopy. Gypsum, ferricopiapite, copiapite, melanterite, coquimbite, and voltaite are found within the samples. This work has implications for Mars mineralogical and geochemical investigations as well as for terrestrial environmental investigations related to acid mine drainage contamination.

  3. Contingency analysis modeling for superfund sites and other sources. Final report

    International Nuclear Information System (INIS)

    The report provides information on contingency modeling for a wide range of different accidental release scenarios of hazardous air pollutants that might take place at Superfund and other sites. The scenarios are used to illustrate how atmospheric dispersion models, including dense gas models, should be applied. Particular emphasis is made on the input data that is needed for proper applications of models. Flow charts direct the user to specific sections where various scenarios are discussed. A check list of items that should be discussed before running the model is provided. Several examples are provided to specifically show how to apply the models so as to produce a credible analysis for a particular release scenario

  4. Proceedings of the workshop on transite decontamination dismantlement and recycle/disposal

    International Nuclear Information System (INIS)

    On February 3--4, 1993, a workshop was conducted to examine issues associated with the decontamination, dismantlement, and recycle/disposal of transite located at the US Department of Energy Fernald site near Cincinnati, OH. The Fernald Environmental Management Project (FEMP) is a Superfund Site currently undergoing remediation. A major objective of the workshop was to assess the state-of-the-art of transite remediation, and generate concepts that could be useful to the Fernald Environmental Restoration Management Co. (FERMCO) for remediation of transite. Transite is a building material consisting of asbestos fiber and cement and may be radioactively contaminated as a result of past uranium processing operations at the FEMP. Many of the 100 buildings within the former uranium production area were constructed of transite siding and roofing and consequently, over 180,000 m2 of transite must be disposed or recycled. Thirty-six participants representing industry, academia, and government institutions such as the EPA and DOE assembled at the workshop to present their experience with transite, describe work in progress, and address the issues involved in remediating transite

  5. Development of a model for geomorphological assessment at U.S. DOE chemical/radioactive waste disposal facilities in the central and eastern United States; Weldon spring site remedial action project, Weldon Spring, Missouri

    International Nuclear Information System (INIS)

    Landform development and long-term geomorphic stability is the result of a complex interaction of a number of geomorphic processes. These processes may be highly variable in intensity and duration under different physiographic settings. This limitation has influenced the applicability of previous geomorphological stability assessments conducted in the arid or semi-arid western United States to site evaluations in more temperate and humid climates. The purpose of this study was to develop a model suitable for evaluating both long-term and short-term geomorphic processes which may impact landform stability and hence the stability of disposal facilities located in the central and eastern United States. The model developed for the geomorphological stability assessment at the Weldon Spring Site Remedial Action Project (WSSRAP) near St. Louis, Missouri, included an evaluation of existing landforms and consideration of the impact of both long-term and short-term geomorphic processes. These parameters were evaluated with respect to their impact and contribution to three assessment criteria considered most important with respect to the stability analysis; evaluation of landform age, evaluation of present geomorphic process activity and; determination of the impact of the completed facility on existing geomorphic processes. The geomorphological assessment at the Weldon Spring site indicated that the facility is located in an area of excellent geomorphic stability. The only geomorphic process determined to have a potential detrimental effect on long-term facility performance is an extension of the drainage network. A program of mitigating measures has been proposed to minimize the impact that future gully extension could have on the integrity of the facility

  6. Integrating Monitoring and Genetic Methods To Infer Historical Risks of PCBs and DDE to Common and Roseate Terns Nesting Near the New Bedford Harbor Superfund Site (Massachusetts, USA).

    Science.gov (United States)

    Nacci, Diane E; Hahn, Mark E; Karchner, Sibel I; Jayaraman, Saro; Mostello, Carolyn; Miller, Kenneth M; Blackwell, Carma Gilchrist; Nisbet, Ian C T

    2016-09-20

    Common and roseate terns are migratory piscivorous seabirds with major breeding colonies within feeding range of the polychlorinated biphenyl (PCB)-contaminated New Bedford Harbor (NBH, MA, USA) Superfund site. Our longitudinal study shows that before PCB discharges into NBH ceased (late 1970s), tern eggs had very high but variable PCB concentrations. However, egg concentrations of PCBs as well as DDE (1,1-bis(p-chlorophenyl)-2,2-dichloroethene), the degradation product of the ubiquitous global contaminant DDT (1,1,1-trichloro-2,2-bis(p-chlorophenyl) ethane), have since declined. Rate constants for temporal decline of PCB congeners in tern eggs varied inversely with log10KOW (n-octanol-water partition coefficient), shifting egg congener patterns away from those characterizing NBH sediment. To estimate the toxic effects on tern eggs of PCB dioxin-like congener (DLC) exposures, we extrapolated published laboratory data on common terns to roseate terns by characterizing genetic and functional similarities in species aryl hydrocarbon receptors (AHRs), which mediate DLC sensitivity. Our assessment of contaminant risks suggests that terns breeding near NBH were exposed historically to toxic levels of PCBs and DDE; however, acute effects on tern egg development have become less likely since the 1970s. Our approach demonstrates how comparative genetics at target loci can effectively increase the range of inference for chemical risk assessments from tested to untested and untestable species. PMID:27564328

  7. Development of grouting technologies for geological disposal of high level waste in Japan (7). Hydrological and chemical change of the groundwater in a pre-grouted crystalline rock after earthquakes

    International Nuclear Information System (INIS)

    The Japan Atomic Energy Agency has conducted 'The project for Grouting Technology Development' under a contract study with the Ministry of Economy, Trade and Industry (METI). As a part of the study, the groundwater chemistry has been monitored for four years after pre-grouting the crystalline rock in the Mizunami underground research laboratory (URL). Measured groundwater pressures were temporarily changed by earthquakes of seismic intensity ≥ 3 and recovered within about one year. Changes to the chemical composition of the groundwater by the earthquakes were not detected and the injected grout material was not significantly damaged. (author)

  8. Superfund TIO videos: Set B. Community relations, communicating with the media and presenting technical information. Part 9. Audio-Visual

    International Nuclear Information System (INIS)

    The videotape is divided into three sections. Section 1 discusses the Superfund Community Relations (CR) Program and its history and objectives. Community Relations requirements as defined by CERCLA for Superfund actions are outlined. Community Relations requirements, the nature of community involvement in CR plans, effective CR techniques, and the roles of the OSC, RPM, and EPA Community Relations Coordinator (CRC) are discussed. Section 2 (1) describes the media's perspective on seeking information; (2) identifies five settings and mechanisms for interacting with the media; (3) offers good media-relations techniques; and (4) lists tips for conducting media interviews. Section 3 outlines techniques for presenting technical information, describes how to be prepared to address typical issues of community concern, and identifies the four key elements in handling tough questions

  9. Arsenic species in weathering mine tailings and biogenic solids at the Lava Cap Mine Superfund Site, Nevada City, CA

    OpenAIRE

    Ashley Roger P; Foster Andrea L; Rytuba James J

    2011-01-01

    Abstract Background A realistic estimation of the health risk of human exposure to solid-phase arsenic (As) derived from historic mining operations is a major challenge to redevelopment of California's famed "Mother Lode" region. Arsenic, a known carcinogen, occurs in multiple solid forms that vary in bioaccessibility. X-ray absorption fine-structure spectroscopy (XAFS) was used to identify and quantify the forms of As in mine wastes and biogenic solids at the Lava Cap Mine Superfund (LCMS) s...

  10. Used Fuel Disposal in Crystalline Rocks. FY15 Progress Report

    Energy Technology Data Exchange (ETDEWEB)

    Wang, Yifeng [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2015-08-20

    The objective of the Crystalline Disposal R&D Work Package is to advance our understanding of long-term disposal of used fuel in crystalline rocks and to develop necessary experimental and computational capabilities to evaluate various disposal concepts in such media. Chapter headings are as follows: Fuel matrix degradation model and its integration with performance assessments, Investigation of thermal effects on the chemical behavior of clays, Investigation of uranium diffusion and retardation in bentonite, Long-term diffusion of U(VI) in bentonite: dependence on density, Sorption and desorption of plutonium by bentonite, Dissolution of plutonium intrinsic colloids in the presence of clay and as a function of temperature, Laboratory investigation of colloid-facilitated transport of cesium by bentonite colloids in a crystalline rock system, Development and demonstration of discrete fracture network model, Fracture continuum model and its comparison with discrete fracture network model.

  11. Superfund reform: US Environmental Protection Agency`s 30-day study and its implication for the US Department of Energy

    Energy Technology Data Exchange (ETDEWEB)

    Siegel, M.R.; Friedman, J.R.; Neff, R.W.

    1993-03-01

    As part of an ongoing effort to reform and restructure the US Environmental Protection Agency`s (EPAS) Superfund program, the EPA Administrator on October 21, 1991, announced several key programmatic reforms. These reforms are a result of the Superfund 30-Day Task Force Report (30-Day Study, EPA 1991a), an effort carried out by EPAs office of Solid Waste and Emergency Response (OSWER). The EPA OSWER oversees environmental cleanup activities under a number of statutory authorities, including the Comprehensive Environmental response, Compensation, and Liability Act (CERCLA, also known as Superfund). CERCLA and its implementing regulation, the National Contingency Plan (NCP), establish a regulatory framework to govern the cleanup of existing, and often abandoned, hazardous waste sites. The purposes of this report are to (1) review the background and recommendations of EPNs 30-Day Study, (2) identify and discuss the initiatives from the 30-Day Study that may impact DOE`s environmental restoration mission, (3) report on EPAs progress in implementing the selected priority initiatives, and (4) describe potentially related DOE activities.

  12. Radioactive waste disposal and constitution

    International Nuclear Information System (INIS)

    The radioactive waste disposal has many dimensions with regard to the constitutional law. The central problem is the corret delimitation between adequate governmental precautions against risks and or the permitted risk which the state can impose on the citizen, and the illegal danger which nobody has to accept. The solution requires to consider all aspects which are relevant to the constitutional law. Therefore, the following analysis deals not only with the constitutional risks and the risks of the nuclear energy, but also with the liberal, overall-economic, social, legal, and democratic aspects of radioactive waste disposal. (HSCH)

  13. Final disposal of radioactive waste

    Science.gov (United States)

    Freiesleben, H.

    2013-06-01

    In this paper the origin and properties of radioactive waste as well as its classification scheme (low-level waste - LLW, intermediate-level waste - ILW, high-level waste - HLW) are presented. The various options for conditioning of waste of different levels of radioactivity are reviewed. The composition, radiotoxicity and reprocessing of spent fuel and their effect on storage and options for final disposal are discussed. The current situation of final waste disposal in a selected number of countries is mentioned. Also, the role of the International Atomic Energy Agency with regard to the development and monitoring of international safety standards for both spent nuclear fuel and radioactive waste management is described.

  14. Sewage sludge disposal in Austria

    International Nuclear Information System (INIS)

    Sewage systems serve about 70% of the Austrian population, producing 6 million m3 of sewage sludge per year with a dry matter content of 4-5%. At present about 52% of this sludge is disposed of in land fills, 33% is incinerated, and only about 15 % is used in agriculture. Although agricultural utilization is becoming increasingly important, several problems, especially those related to public opinion, need to be resolved before increased use will be possible. In this paper, wastewater treatment and sewage-sludge production in Austria, and problems associated with sludge disposal are discussed. (author)

  15. Challenges in Disposing of Anthrax Waste

    Energy Technology Data Exchange (ETDEWEB)

    Lesperance, Ann M.; Stein, Steven L.; Upton, Jaki F.; Toomey, Christopher

    2011-09-01

    Disasters often create large amounts of waste that must be managed as part of both immediate response and long-term recovery. While many federal, state, and local agencies have debris management plans, these plans often do not address chemical, biological, and radiological contamination. The Interagency Biological Restoration Demonstration’s (IBRD) purpose was to holistically assess all aspects of an anthrax incident and assist the development of a plan for long-term recovery. In the case of wide-area anthrax contamination and the follow-on response and recovery activities, a significant amount of material will require decontamination and disposal. Accordingly, IBRD facilitated the development of debris management plans to address contaminated waste through a series of interviews and workshops with local, state, and federal representatives. The outcome of these discussion was the identification of three primary topical areas that must be addressed: 1) Planning; 2) Unresolved research questions, and resolving regulatory issues.

  16. Superfund and Toxic Release Inventory Sites, StateCERCLIS-This data set contains potential EPA Superfund sites. These locations represent sites, not contaminated areas., Published in 2008, 1:100000 (1in=8333ft) scale, State of Utah Automated Geographic Reference Center.

    Data.gov (United States)

    NSGIC GIS Inventory (aka Ramona) — This Superfund and Toxic Release Inventory Sites dataset, published at 1:100000 (1in=8333ft) scale, was produced all or in part from Field Survey/GPS information as...

  17. Superfund and Toxic Release Inventory Sites, Point or polygon geo-location of federally designated superfund sites in Wisconsin. Usually geolocated via on screen digitizing against DOPs (could be geo-located via GPS). Source year of DOPs vary, Published in unknown, 1:4800 (1in=400ft) scale, Wisconsin DNR - Bureau of Remediation and Redevelopment.

    Data.gov (United States)

    NSGIC GIS Inventory (aka Ramona) — This Superfund and Toxic Release Inventory Sites dataset, published at 1:4800 (1in=400ft) scale, was produced all or in part from Orthoimagery information as of...

  18. Contributions of Geology to the Problem of Radioactive Waste Disposal

    International Nuclear Information System (INIS)

    The earth is the sphere of interest of the geologist, and it is the only place on or in which wastes can he dispersed or stored. In that sense, problems of radioactive waste disposal are primarily geological. Accumulated geologic knowledge and established principles have been applied widely in the United States to problems of disposal, and the unique nature of these problems has led to research and significant advances of knowledge in specialized aspects of geology. A common activity has been appraisal of sites for nuclear energy facilities. This includes analysis and evaluation of geologic, topographic, hydrologic, geochemical and seismic factors. Also, regional analyses are made of the gross characteristics of. major physical subdivisions of the United States and the relation of these characteristics to waste storage and disposal. Special problems include the actual and potential behaviour of ordinary wastes in specific geologic environments. Other studies concern possible use of structural basins, stratigraphic traps, and salt beds and salt domes for storage and containment of high-level waste. Much general and some detailed study has been made of background radiometry. Water is the critical factor in waste disposal; accordingly certain natural processes by which water may be purified or chemically altered have been investigated. Significant results have been achieved in studies of dispersion and diffusion processes in ground water and surface water ; the rate of travel of contaminants in streams; the mechanics of ground-water flow in granular materials ; ground-water flow in cavernous rocks ; and the behaviour of water and chemical solutions in the zone of aeration. Thermal and chemical-stability problems that would develop if high-level waste were injected in geologic formations also have been investigated. Geologic, petrologic and geophysical studies have been made of specific areas, and research in clay mineralogy, ion exchange and geochemistry has been

  19. West Hackberry Strategic Petroleum Reserve site brine disposal monitoring, Year I report. Volume V. Supporting data for estuarine hydrology, discharge plume analysis, chemical oceanography, biological oceanography, and data management. Final report

    Energy Technology Data Exchange (ETDEWEB)

    DeRouen, L.R.; Hann, R.W.; Casserly, D.M.; Giammona, C.; Lascara, V.J. (eds.)

    1983-02-01

    This project centers around the Strategic Petroleum Site (SPR) known as the West Hackberry salt dome which located in southwestern Louisiana, and which is designed to store 241 million barrels of crude oil. Oil storage caverns are formed by injecting water into salt deposits, and pumping out the resulting brine. Studies described in this report were designed as follow-on studies to three months of pre-discharge characterization work, and include data collected during the first year of brine leaching operations. The objectives were to: (1) characterize the environment in terms of physical, chemical and biological attributes; (2) determine if significant adverse changes in ecosystem productivity and stability of the biological community are occurring as a result of brine discharge; and (3) determine the magnitude of any change observed. Volume V contains appendices for the following: supporting data for estuarine hydrology and hydrography; supporting data analysis of discharge plume; supporting data for water and sediment chemistry; CTD/DO and pH profiles during biological monitoring; supporting data for nekton; and supporting data for data management.

  20. Final disposal of nuclear waste

    International Nuclear Information System (INIS)

    The nuclear industry argues that high level radioactive waste can be safely disposed of in deep underground repositories. As yet, however, no such repositories are in use and the amount of spent nuclear fuel in ponds and dry storage is steadily increasing. Although the nuclear industry further argues that storage is a safe option for up to 50 years and has the merit of allowing the radioactivity of the fuel to decay to a more manageable level, the situation seems to be far from ideal. The real reasons for procrastination over deep disposal seem to have as much to do with politics as safe technology. The progress of different countries in finding a solution to the final disposal of high level waste is examined. In some, notably the countries of the former Soviet Union, cost is a barrier; in others, the problem has not yet been faced. In these countries undertaking serious research into deep disposal there has been a tendency, in the face of opposition from environmental groups, to retreat to sites close to existing nuclear installations and to set up rock laboratories to characterize them. These sites are not necessarily the best geologically, but the laboratories may end up being converted into actual repositories because of the considerable financial investment they represent. (UK)

  1. Final disposal of nuclear waste

    Energy Technology Data Exchange (ETDEWEB)

    Anon.

    1995-10-01

    The nuclear industry argues that high level radioactive waste can be safely disposed of in deep underground repositories. As yet, however, no such repositories are in use and the amount of spent nuclear fuel in ponds and dry storage is steadily increasing. Although the nuclear industry further argues that storage is a safe option for up to 50 years and has the merit of allowing the radioactivity of the fuel to decay to a more manageable level, the situation seems to be far from ideal. The real reasons for procrastination over deep disposal seem to have as much to do with politics as safe technology. The progress of different countries in finding a solution to the final disposal of high level waste is examined. In some, notably the countries of the former Soviet Union, cost is a barrier; in others, the problem has not yet been faced. In these countries undertaking serious research into deep disposal there has been a tendency, in the face of opposition from environmental groups, to retreat to sites close to existing nuclear installations and to set up rock laboratories to characterize them. These sites are not necessarily the best geologically, but the laboratories may end up being converted into actual repositories because of the considerable financial investment they represent. (UK).

  2. General Instructions for Disposable Respirators

    Centers for Disease Control (CDC) Podcasts

    2009-04-09

    This podcast, intended for the general public, demonstrates how to put on and take off disposable respirators that are to be used in areas affected by the influenza outbreak.  Created: 4/9/2009 by CDC, National Institute for Occupational Safety and Health (NIOSH).   Date Released: 4/29/2009.

  3. Physiochemical technologies for HCB remediation and disposal: a review.

    Science.gov (United States)

    Tong, Man; Yuan, Songhu

    2012-08-30

    Hexachlorobenzene (HCB) is one of the 12 persistent organic pollutants (POPs) listed in "Stockholm Convention". It is hydrophobic, toxic and persistent in the environment. Due to extensive use in the past, HCB contamination is still a serious environmental problem. Strong adsorption on solid particles makes the remediation difficult. This paper presents an overview of the physiochemical technologies for HCB remediation and disposal. The adsorption/desorption behavior of HCB is firstly described because it comprises the fundamental for most remediation technologies. Physiochemical technologies concerned mostly for HCB remediation and disposal, i.e., chemical enhanced washing, electrokinetic remediation, reductive dechlorination and thermal decomposition, are reviewed in terms of fundamentals, state of the art and perspectives. The other physiochemical technologies including chemical oxidation, radiation induced catalytic dechlorination, ultrasonic assisted treatment and mechanochemical dechlorination are also reviewed. The pilot and large scale tests on HCB remediation or disposal are summarized in the end. This review aims to provide useful information to researchers and practitioners regarding HCB remediation and disposal. PMID:22709849

  4. 40 CFR 761.75 - Chemical waste landfills.

    Science.gov (United States)

    2010-07-01

    ... above the waste disposal unit liner and above a secondary installed liner. This design is recommended... the sides and under the bottom of the waste disposal unit liner. This type of system works best when... PROHIBITIONS Storage and Disposal § 761.75 Chemical waste landfills. This section applies to facilities used...

  5. Groundwater Fate and Transport Modeling for Texarkana Wood Preserving Company Superfund Site, Texarkana, Texas

    Energy Technology Data Exchange (ETDEWEB)

    Arnett, Ronald Chester

    1999-08-01

    Fate and transport model results are presented for the Texarkana Wood Preserving Company (TWPC)superfund site. The conceptual model assumes two sources of contamination, specifically, the areas around the old and new process areas. Recent data show the presence of non-aqueous phase liquids (NAPL) in the aquifer that are also sources of dissolved contamination in the aquifer. A flow model was constructed and calibrated against measured hydraulic heads at permanent monitoring wells. Good matches were obtained between model simulated heads and most measured heads. An unexplained exception occurs at monitoring well MW-13 down gradient of the site beyond the measured contaminant plume where the model predicts heads that are more than 2 ft. lower than reported field measurements. Adjusting hydraulic parameters in the model could not account for this anomaly and still preserve the head matches at other wells. There is likely a moderate deficiency in the conceptual model or perhaps a data error. Other information such as substantial amounts of infiltrating surface water in the area or a correction in surveyed elevation would improve the flow model. A particle tracking model calculated a travel time from the new process area to the Day’s Creek discharge location on the order of 40 years. Travel times from the old process area to Day’s Creek were calculated to be on the order of 80 years. While these calculations are subject to some uncertainty, travel times of decades are indicated.

  6. 48 CFR 245.603 - Disposal methods.

    Science.gov (United States)

    2010-10-01

    ... 48 Federal Acquisition Regulations System 3 2010-10-01 2010-10-01 false Disposal methods. 245.603 Section 245.603 Federal Acquisition Regulations System DEFENSE ACQUISITION REGULATIONS SYSTEM, DEPARTMENT... Contractor Inventory 245.603 Disposal methods....

  7. Earth Construction and Landfill Disposal Options for Slaker Grits

    OpenAIRE

    Risto Pöykiö; G. Watkins; H. Nurmesniemi and O. Dahl

    2010-01-01

    Slaker grits, an industrial residue originating from the chemical recovery process at sulfate (kraft) pulp mills, are typically disposed of to landfill in Finland. However, due to the relatively low total heavy metal and low leachable heavy metal, chloride, fluoride, sulfate, Dissolved O rganic Carbon (DOC) and Total Dissolved Solids (TDS) concentrations, the residue is a potential earth construction material. This paper gives an overview of the relevant Finnish legislation on the use of indu...

  8. Disposable products in the hospital waste stream.

    OpenAIRE

    Gilden, D. J.; Scissors, K. N.; Reuler, J B

    1992-01-01

    Use of disposable products in hospitals continues to increase despite limited landfill space and dwindling natural resources. We analyzed the use and disposal patterns of disposable hospital products to identify means of reducing noninfectious, nonhazardous hospital waste. In a 385-bed private teaching hospital, the 20 disposable products of which the greatest amounts (by weight) were purchased, were identified, and total hospital waste was tabulated. Samples of trash from three areas were so...

  9. Chemical exchange program analysis.

    Energy Technology Data Exchange (ETDEWEB)

    Waffelaert, Pascale

    2007-09-01

    As part of its EMS, Sandia performs an annual environmental aspects/impacts analysis. The purpose of this analysis is to identify the environmental aspects associated with Sandia's activities, products, and services and the potential environmental impacts associated with those aspects. Division and environmental programs established objectives and targets based on the environmental aspects associated with their operations. In 2007 the most significant aspect identified was Hazardous Materials (Use and Storage). The objective for Hazardous Materials (Use and Storage) was to improve chemical handling, storage, and on-site movement of hazardous materials. One of the targets supporting this objective was to develop an effective chemical exchange program, making a business case for it in FY07, and fully implementing a comprehensive chemical exchange program in FY08. A Chemical Exchange Program (CEP) team was formed to implement this target. The team consists of representatives from the Chemical Information System (CIS), Pollution Prevention (P2), the HWMF, Procurement and the Environmental Management System (EMS). The CEP Team performed benchmarking and conducted a life-cycle analysis of the current management of chemicals at SNL/NM and compared it to Chemical Exchange alternatives. Those alternatives are as follows: (1) Revive the 'Virtual' Chemical Exchange Program; (2) Re-implement a 'Physical' Chemical Exchange Program using a Chemical Information System; and (3) Transition to a Chemical Management Services System. The analysis and benchmarking study shows that the present management of chemicals at SNL/NM is significantly disjointed and a life-cycle or 'Cradle-to-Grave' approach to chemical management is needed. This approach must consider the purchasing and maintenance costs as well as the cost of ultimate disposal of the chemicals and materials. A chemical exchange is needed as a mechanism to re-apply chemicals on site. This

  10. Chemicals from Cradle to Grave

    Science.gov (United States)

    Science Scope, 2005

    2005-01-01

    About two years ago, an urban school district had planned for the disposal of some hazardous chemicals. It contracted with a chemical recycling company that was considered to be reputable. The school district, along with several other companies, was charged and fined by the Environmental Protection Agency for improperly releasing hazardous…

  11. Environmental chemistry of radioactive waste disposal

    Energy Technology Data Exchange (ETDEWEB)

    Duffield, J.R.; Williams, D.R.

    1986-09-01

    In this review the environmental chemistry problems associated with radioactive waste disposal are considered from the point of view of the threat to man of waste disposal, contamination pathways, the chemistry of waste containment, speciation of radio-isotopes, chemisorption, risk assessment and computerized simulation of waste disposal phenomena. A strategy for the future is discussed.

  12. 48 CFR 2845.603 - Disposal methods.

    Science.gov (United States)

    2010-10-01

    ... 48 Federal Acquisition Regulations System 6 2010-10-01 2010-10-01 true Disposal methods. 2845.603 Section 2845.603 Federal Acquisition Regulations System DEPARTMENT OF JUSTICE Contract Management GOVERNMENT PROPERTY Reporting, Redistribution, and Disposal of Contractor Inventory 2845.603 Disposal...

  13. 48 CFR 945.603 - Disposal methods.

    Science.gov (United States)

    2010-10-01

    ... 48 Federal Acquisition Regulations System 5 2010-10-01 2010-10-01 false Disposal methods. 945.603 Section 945.603 Federal Acquisition Regulations System DEPARTMENT OF ENERGY CONTRACT MANAGEMENT GOVERNMENT PROPERTY Reporting, Redistribution, and Disposal of Contractor Inventory 945.603 Disposal methods....

  14. Nuclear waste management: storage and disposal aspects

    International Nuclear Information System (INIS)

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

  15. The disposal of mine tailings

    International Nuclear Information System (INIS)

    The paper examines the consequences of dam building with slime of high water content, and therefore low relative density, such as the tailings usually associated with the extraction of uranium. It shows how a low relative density reduces the practica maximum rate of rise, and hence the establishment cost, of slimes dams built by conventional means. Further hidden costs of such tailings dams are examined. It is concluded that dewatering of tailings before their disposal is the most cost-effective means of increasing the rate at which a particular dam can be constructed, or of reducing operating or stability problems on existing dams. In the longer term, underground disposal seems to be a feasible alternative. However, it is pointed out that there are factors that can compound the operating difficulties, and that these should be investigated before remedial steps are taken

  16. Final disposal of radioactive waste

    Directory of Open Access Journals (Sweden)

    Freiesleben H.

    2013-06-01

    Full Text Available In this paper the origin and properties of radioactive waste as well as its classification scheme (low-level waste – LLW, intermediate-level waste – ILW, high-level waste – HLW are presented. The various options for conditioning of waste of different levels of radioactivity are reviewed. The composition, radiotoxicity and reprocessing of spent fuel and their effect on storage and options for final disposal are discussed. The current situation of final waste disposal in a selected number of countries is mentioned. Also, the role of the International Atomic Energy Agency with regard to the development and monitoring of international safety standards for both spent nuclear fuel and radioactive waste management is described.

  17. Shallow disposal of radioactive waste

    International Nuclear Information System (INIS)

    A review and evaluation of computer codes capable of simulating the various processes that are instrumental in determining the dose rate to individuals resulting from the shallow disposal of radioactive waste was conducted. Possible pathways of contamination, as well as the mechanisms controlling radionuclide movement along these pathways have been identified. Potential transport pathways include the unsaturated and saturated ground water systems, surface water bodies, atmospheric transport and movement (and accumulation) in the food chain. Contributions to dose may occur as a result of ingestion of contaminated water and food, inhalation of contaminated air and immersion in contaminated air/water. Specific recommendations were developed regarding the selection and modification of a model to meet the needs associated with the prediction of dose rates to individuals as a consequence of shallow radioactive waste disposal. Specific technical requirements with regards to risk, sensitivity and uncertainty analyses have been addressed

  18. Siting of geological disposal facilities

    International Nuclear Information System (INIS)

    Radioactive waste is generated from the production of nuclear energy and from the use of radioactive materials in industrial applications, research and medicine. The importance of safe management of radioactive waste for the protection of human health and the environment has long been recognized and considerable experience has been gained in this field. The Radioactive Waste Safety Standards (RADWASS) programme is the IAEA's contribution to establishing and promoting the basic safety philosophy for radioactive waste management and the steps necessary to ensure its implementation. This Safety Guide defines the process to be used and guidelines to be considered in selecting sites for deep geological disposal of radioactive wastes. It reflects the collective experience of eleven Member States having programmes to dispose of spent fuel, high level and long lived radioactive waste. In addition to the technical factors important to site performance, the Safety Guide also addresses the social, economic and environmental factors to be considered in site selection. 3 refs

  19. Equity and nuclear waste disposal

    International Nuclear Information System (INIS)

    Following the recommendations of the US National Academy of Sciences and the mandates of the 1987 Nuclear Waste Policy Amendments Act, the US Department of Energy has proposed Yucca Mountain, Nevada as the site of the world's first permanent repository for high-level nuclear waste. The main justification for permanent disposal (as opposed to above-ground storage) is that it guarantees safety by means of waste isolation. This essay argues, however, that considerations of equity (safer for whom?) undercut the safety rationale. The article surveys some prima facie arguments for equity in the distribution of radwaste risks and then evaluates four objections that are based, respectively, on practicality, compensation for risks, scepticism about duties to future generations, and the uranium criterion. The conclusion is that, at least under existing regulations and policies, permanent waste disposal is highly questionable, in part, because it fails to distribute risk equitably or to compensate, in full, for this inequity

  20. Idaho CERCLA Disposal Facility Complex Waste Acceptance Criteria

    Energy Technology Data Exchange (ETDEWEB)

    W. Mahlon Heileson

    2006-10-01

    The Idaho Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) Disposal Facility (ICDF) has been designed to accept CERCLA waste generated within the Idaho National Laboratory. Hazardous, mixed, low-level, and Toxic Substance Control Act waste will be accepted for disposal at the ICDF. The purpose of this document is to provide criteria for the quantities of radioactive and/or hazardous constituents allowable in waste streams designated for disposal at ICDF. This ICDF Complex Waste Acceptance Criteria is divided into four section: (1) ICDF Complex; (2) Landfill; (3) Evaporation Pond: and (4) Staging, Storage, Sizing, and Treatment Facility (SSSTF). The ICDF Complex section contains the compliance details, which are the same for all areas of the ICDF. Corresponding sections contain details specific to the landfill, evaporation pond, and the SSSTF. This document specifies chemical and radiological constituent acceptance criteria for waste that will be disposed of at ICDF. Compliance with the requirements of this document ensures protection of human health and the environment, including the Snake River Plain Aquifer. Waste placed in the ICDF landfill and evaporation pond must not cause groundwater in the Snake River Plain Aquifer to exceed maximum contaminant levels, a hazard index of 1, or 10-4 cumulative risk levels. The defined waste acceptance criteria concentrations are compared to the design inventory concentrations. The purpose of this comparison is to show that there is an acceptable uncertainty margin based on the actual constituent concentrations anticipated for disposal at the ICDF. Implementation of this Waste Acceptance Criteria document will ensure compliance with the Final Report of Decision for the Idaho Nuclear Technology and Engineering Center, Operable Unit 3-13. For waste to be received, it must meet the waste acceptance criteria for the specific disposal/treatment unit (on-Site or off-Site) for which it is destined.

  1. Main orientations in ICRP recommendations on waste disposal

    International Nuclear Information System (INIS)

    The disposal of chemically toxic or radioactive waste is a particularly thorny problem for the public, since waste is usually perceived as something completely negative and entirely independent of the beneficial practices which generated it. Radioactive waste disposal is a radiological protection problem, since the principal objective is the protection of current and future generations. There is no doubt that the Commission on Radiological Protection (ICRP) plays an essential role in this subject, due to its competence and to the fact that ICRP is a non governmental organisation independent from national regulatory authorities. However, until recently it should be recognised that its role regarding radioactive waste disposal has been limited, despite a specific publication on the subject more than a decade ago (ICRP 46 'Radiation Protection Principles for the Disposal of Solid Waste'). The purpose of this paper is to show the evolution of ICRP's position, since it considered as essential to clarify the way in which radiological protection principles and concepts are applied to radioactive waste (effluents or solid waste). It will show the importance of publication 77 ('Radiological Protection Policy for the Disposal of Radioactive Waste', 1997) and the main themes of an ongoing study on long lived solid waste ('Radiation Protection Recommendations as applied to the Disposal of Long Lived Solid Radioactive Waste'). Special attention will be given to the following issues: protection of future generations, definition of hypothetical group, optimisation in the context of potential exposure. A distinction should be made between the application of the criteria to exposure situations resulting from natural processes (gradual or disruptive) and human intrusion, technical and managerial principles, compliance with the radiological protection principles. The objective of the paper is to clarity the usefulness of these recommendations in the decision making process. (author)

  2. Regional gross disposable household income

    OpenAIRE

    Eddie Holmes

    2008-01-01

    Presents estimates published in May 2008, an overview of methodology used and future plans for regional economic dataThis article looks at estimates for regional gross disposable household income (GDHI) at current basic prices, published in May 2008. These data are published using the European Union Nomenclature of Units for Territorial Statistics (NUTS) regions. Data are published for the NUTS1, NUTS2 and NUTS3 levels for the period 1995 to 2006. There is an overview of the methodology used ...

  3. Disposal of spent nuclear fuel

    International Nuclear Information System (INIS)

    This report addresses the topic of the mined geologic disposal of spent nuclear fuel from Pressurized Water Reactors (PWR) and Boiling Water Reactors (BWR). Although some fuel processing options are identified, most of the information in this report relates to the isolation of spent fuel in the form it is removed from the reactor. The characteristics of the waste management system and research which relate to spent fuel isolation are discussed. The differences between spent fuel and processed HLW which impact the waste isolation system are defined and evaluated for the nature and extent of that impact. What is known and what needs to be determined about spent fuel as a waste form to design a viable waste isolation system is presented. Other waste forms and programs such as geologic exploration, site characterization and licensing which are generic to all waste forms are also discussed. R and D is being carried out to establish the technical information to develop the methods used for disposal of spent fuel. All evidence to date indicates that there is no reason, based on safety considerations, that spent fuel should not be disposed of as a waste

  4. Safe disposal of prescribed medicines.

    Science.gov (United States)

    Bergen, Phillip J; Hussainy, Safeera Y; George, Johnson; Kong, David Cm; Kirkpatrick, Carl Mj

    2015-06-01

    The National Return and Disposal of Unwanted Medicines Program provides a free and safe method for the disposal of unwanted and expired medicines. This stops drugs being dumped in landfill and waterways. An audit showed that over 600 tonnes of medicines are returned through the program. A substantial proportion of these medicines were still within their expiry dates. Salbutamol, insulin and frusemide are the most commonly discarded medicines. More than $2 million of public money is wasted each year. Hoarding and non-adherence to treatment contribute to waste. Health professionals may be able to help minimise waste by informing patients about the importance of completing prescribed courses of treatment, and discouraging them from hoarding medicines after reaching the safety net threshold on the Pharmaceutical Benefits Scheme. Prescribe no more than the required quantity of medicines. When starting a new therapy, prescribe a minimal quantity in case the drug is unsuitable for the patient. Advise patients to return all unwanted medicines to a pharmacy for disposal. PMID:26648628

  5. Disposal of spent nuclear fuel

    Energy Technology Data Exchange (ETDEWEB)

    1979-12-01

    This report addresses the topic of the mined geologic disposal of spent nuclear fuel from Pressurized Water Reactors (PWR) and Boiling Water Reactors (BWR). Although some fuel processing options are identified, most of the information in this report relates to the isolation of spent fuel in the form it is removed from the reactor. The characteristics of the waste management system and research which relate to spent fuel isolation are discussed. The differences between spent fuel and processed HLW which impact the waste isolation system are defined and evaluated for the nature and extent of that impact. What is known and what needs to be determined about spent fuel as a waste form to design a viable waste isolation system is presented. Other waste forms and programs such as geologic exploration, site characterization and licensing which are generic to all waste forms are also discussed. R and D is being carried out to establish the technical information to develop the methods used for disposal of spent fuel. All evidence to date indicates that there is no reason, based on safety considerations, that spent fuel should not be disposed of as a waste.

  6. Hanford site grout disposal vaults

    International Nuclear Information System (INIS)

    The Grout Treatment Facility (GTF) completed processing and disposal of an initial 3,800 m3 of radioactive waste from the Hanford site's double-shell tanks (DSTs) on July 11, 1989. For the first time in the Hanford site's 46-yr history, tank wastes resulting from weapons-grade plutonium production were moved out of liquid storage and converted into a solid for environmentally safe disposal. In addition to the 3,800 m3 of nonhazardous, low-level waste processed in 1988 and 1989, ∼ 163,000 m3 of mixed waste will be treated for disposal between 1992 and 2013. These low-level wastes are radioactive, concentrated salt solutions classified as hazardous by the U.S. Environmental Protection Agency (EPA) and dangerous by the Washington State Department of Ecology. As feed for the grouting process they contain ∼ 11% sodium nitrate, 6% sodium hydroxide, 5% sodium nitrite, 3% sodium aluminate, 1% sodium phosphate, 0.5% sodium chloride, and 73% water. Many radionuclides are present, although 137Cs contributes more than 99% of the 0.3 Ci/l activity. From a long-term performance assessment standpoint, nitrate, 99Tc, and 129I are the primary contaminants of concern

  7. Solid waste disposal: a long-standing public health problem comes of age

    Energy Technology Data Exchange (ETDEWEB)

    Wands, R.C.

    1977-05-01

    An important step in the waste disposal issue was the passage of the Resource Conservation and Recovery Act of 1976. The chief aims of the Act are to encourage recycling of natural resources, to provide for the safe disposal of discarded materials, and to regulate the management of hazardous waste. Hazardous waste disposal can be controlled only if the public is informed of what wastes are hazardous and provided with an effective and convenient method for their disposal. By far the greatest source of hazardous waste, however, is industry, especially the metallurgical and chemical industries. Some pollution problems dscussed are those caused by polychlorinated biphenyls and kepone, sodium monofluoroacetate in sanitary landfills, leachate waters containing Pb, Se, Fe, and Hg, and shallow land burial of low-level radioactive wastes. Several industries are trying to solve the problems of solid waste disposal, either voluntarily or in response to regulatory and judicial pressures.

  8. A disposal strategy of industrial hazardous wastes in the Three Gorges Region

    Institute of Scientific and Technical Information of China (English)

    2003-01-01

    A large quantity of industrial hazardous wastes (IHWs) accumulates in the Three Gorges Region. This study found that approximately 15 000 t IHWs were piled in the region by October 2001. These IHWs came from various sources and were complex in composition, mostly toxic and difficult to be disposed. IHW is regarded as a potential threat to the ecological environment, water resources and survival of local residents. It is important and indispensable to dispose the waste properly. To meet the regulation requirements on the disposal of IHWs and to minimize environmental effects on the Three Gorges Region, a disposal strategy is proposed, according to which approximately 600 t of the IHWs can be disposed by chemical stabilization,incineration and other treatment measures, and the rest need be stockpiled in safe and reliable places situated above the 177 m impoundment line of the Three Gorges dam.

  9. U.S. program assessing nuclear waste disposal in space - A 1981 status report

    Science.gov (United States)

    Rice, E. E.; Edgecombe, D. S.; Best, R. E.; Compton, P. R.

    1982-01-01

    Concepts, current studies, and technology and equipment requirements for using the STS for space disposal of selected nuclear wastes as a complement to geological storage are reviewed. An orbital transfer vehicle carried by the Shuttle would kick the waste cannister into a 0.85 AU heliocentric orbit. One flight per week is regarded as sufficient to dispose of all high level wastes chemically separated from reactor fuel rods from 200 GWe nuclear power capacity. Studies are proceeding for candidate wastes, the STS system suited to each waste, and the risk/benefits of a space disposal system. Risk assessments are being extended to total waste disposal risks for various disposal programs with and without a space segment, and including side waste streams produced as a result of separating substances for launch.

  10. Social dimensions of nuclear waste disposal

    International Nuclear Information System (INIS)

    Nuclear waste disposal is a two-faceted challenge: a scientific and technological endeavour, on the one hand, and confronted with social dimensions, on the other. In this paper I will sketch the respective social dimensions and will give a plea for interdisciplinary research approaches. Relevant social dimensions of nuclear waste disposal are concerning safety standards, the disposal 'philosophy', the process of determining the disposal site, and the operation of a waste disposal facility. Overall, cross-cutting issues of justice, responsibility, and fairness are of major importance in all of these fields.

  11. Social dimensions of nuclear waste disposal

    Energy Technology Data Exchange (ETDEWEB)

    Grunwald, Armin [Karlsruhe Institute of Technology, Karlsruhe (Germany). Inst. for Technology Assessment and Systems Analysis

    2015-07-01

    Nuclear waste disposal is a two-faceted challenge: a scientific and technological endeavour, on the one hand, and confronted with social dimensions, on the other. In this paper I will sketch the respective social dimensions and will give a plea for interdisciplinary research approaches. Relevant social dimensions of nuclear waste disposal are concerning safety standards, the disposal 'philosophy', the process of determining the disposal site, and the operation of a waste disposal facility. Overall, cross-cutting issues of justice, responsibility, and fairness are of major importance in all of these fields.

  12. The use and disposal of household pesticides.

    Science.gov (United States)

    Grey, Charlotte N B; Nieuwenhuijsen, Mark J; Golding, Jean

    2005-01-01

    Most pesticides are synthetic chemicals manufactured specifically for their toxic properties to the target species, and widely used globally. Several epidemiological studies in the United States have suggested health concerns arising from the chronic exposure of young children to pesticides in the domestic environment. In the UK very little is currently known about how nonoccupational pesticides are being used or disposed of. Any use of pesticides is a potential risk factor for children's exposure, and any potential exposure is likely to be reduced by the parents' adopting precautionary behaviour when using these pesticide products. This was investigated using a sample of 147 parents from the Avon Longitudinal Study of Parents and Children cohort in and around Bristol, through an in-depth interview between August and November 2001. The results of this study add to the understanding of the underlying behaviour of parents applying pesticide products in the home environment in the UK. Pesticides are readily available, and are normally purchased in do-it-yourself shops and supermarkets and mostly disposed of in domestic waste. Safety was stated by 45% of parents to be the most important factor to consider when buying a pesticide. When buying pesticide products, labels were stated to be the most important source of information about pesticides. However, a third of parents stated they would not follow the product label exactly when using a product, just under half felt labels were both inadequate and hard to understand, and about 10% of parents would not take notice of warnings on the pesticide label. Less than half of parents would use gloves when applying a pesticide, although the use of protective equipment such as gloves during the application of pesticides could greatly reduce the exposure. It is a public health concern that the instructions on the labels of products may not always be understood or followed, and further understanding of user behaviour is needed.

  13. The use and disposal of household pesticides

    International Nuclear Information System (INIS)

    Most pesticides are synthetic chemicals manufactured specifically for their toxic properties to the target species, and widely used globally. Several epidemiological studies in the United States have suggested health concerns arising from the chronic exposure of young children to pesticides in the domestic environment. In the UK very little is currently known about how nonoccupational pesticides are being used or disposed of. Any use of pesticides is a potential risk factor for children's exposure, and any potential exposure is likely to be reduced by the parents' adopting precautionary behaviour when using these pesticide products. This was investigated using a sample of 147 parents from the Avon Longitudinal Study of Parents and Children cohort in and around Bristol, through an in-depth interview between August and November 2001. The results of this study add to the understanding of the underlying behaviour of parents applying pesticide products in the home environment in the UK. Pesticides are readily available, and are normally purchased in do-it-yourself shops and supermarkets and mostly disposed of in domestic waste. Safety was stated by 45% of parents to be the most important factor to consider when buying a pesticide. When buying pesticide products, labels were stated to be the most important source of information about pesticides. However, a third of parents stated they would not follow the product label exactly when using a product, just under half felt labels were both inadequate and hard to understand, and about 10% of parents would not take notice of warnings on the pesticide label. Less than half of parents would use gloves when applying a pesticide, although the use of protective equipment such as gloves during the application of pesticides could greatly reduce the exposure. It is a public health concern that the instructions on the labels of products may not always be understood or followed, and further understanding of user behaviour is needed

  14. Geochemical Characteristics of TP3 Mine Wastes at the Elizabeth Copper Mine Superfund Site, Orange County, Vermont

    Science.gov (United States)

    Hammarstrom, Jane M.; Piatak, Nadine M.; Seal, Robert R., II; Briggs, Paul H.; Meier, Allen L.; Muzik, Timothy L.

    2003-01-01

    Remediation of the Elizabeth mine Superfund site in the Vermont copper belt poses challenges for balancing environmental restoration goals with issues of historic preservation while adopting cost-effective strategies for site cleanup and long-term maintenance. The waste-rock pile known as TP3, at the headwaters of Copperas Brook, is especially noteworthy in this regard because it is the worst source of surface- and ground-water contamination identified to date, while also being the area of greatest historical significance. The U.S. Geological Survey (USGS) conducted a study of the historic mine-waste piles known as TP3 at the Elizabeth mine Superfund site near South Strafford, Orange County, VT. TP3 is a 12.3-acre (49,780 m2) subarea of the Elizabeth mine site. It is a focus area for historic preservation because it encompasses an early 19th century copperas works as well as waste from late 19th- and 20th century copper mining (Kierstead, 2001). Surface runoff and seeps from TP3 form the headwaters of Copperas Brook. The stream flows down a valley onto flotation tailings from 20th century copper mining operations and enters the West Branch of the Ompompanoosuc River approximately 1 kilometer downstream from the mine site. Shallow drinking water wells down gradient from TP3 exceed drinking water standards for copper and cadmium (Hathaway and others, 2001). The Elizabeth mine was listed as a Superfund site in 2001, mainly because of impacts of acid-mine drainage on the Ompompanoosuc River.

  15. Surface-Water Hydrology and Quality at the Pike Hill Superfund Site, Corinth, Vermont, October 2004 to December 2005

    Science.gov (United States)

    Kiah, Richard G.; Deacon, Jeffrey R.; Piatak, Nadine M.; Seal, Robert R., II; Coles, James F.; Hammarstrom, Jane M.

    2007-01-01

    The hydrology and quality of surface water in and around the Pike Hill Brook watershed, in Corinth, Vermont, was studied from October 2004 to December 2005 by the U.S. Geological Survey in cooperation with the U.S. Environmental Protection Agency (USEPA). Pike Hill was mined intermittently for copper from 1847 to 1919 and the site is known to be contributing trace elements and acidity to Pike Hill Brook and an unnamed tributary to Cookville Brook. The site has been listed as a Superfund site since 2004. Streamflow, specific conductance, pH, and water temperature were measured continuously and monthly at three sites on Pike Hill Brook to determine the variation in these parameters over an annual cycle. Synoptic water-quality sampling was done at 10 stream sites in October 2004, April 2005, and June 2005 and at 13 stream sites in August 2005 to characterize the quality of surface water in the watershed on a seasonal and spatial basis, as well as to assess the effects of wetlands on water quality. Samples for analysis of benthic macroinvertebrate populations were collected at 11 stream sites in August 2005. Water samples were analyzed for 5 major ions and 32 trace elements. Concentrations of trace elements at sites in the Pike Hill Brook watershed exceeded USEPA National Recommended Water Quality Criteria acute and chronic toxicity standards for aluminum, iron, cadmium, copper, and zinc. Concentrations of copper exceeded the chronic criteria in an unnamed tributary to Cookville Brook in one sample. Concentrations of sulfate, calcium, aluminum, iron, cadmium, copper, and zinc decreased with distance from a site directly downstream from the mine (site 1), as a result of dilution and through sorption and precipitation of the trace elements. Maximum concentrations of aluminum, iron, cadmium, copper, and zinc were observed during spring snowmelt. Concentrations of sulfate, calcium, cadmium, copper, and zinc, and instantaneous loads of calcium and aluminum were

  16. Geomechanical problems in study of radioactive wastes disposal

    International Nuclear Information System (INIS)

    Methods for both low-intermediate level radioactive wastes disposal and high level radioactive waste disposal were introduced briefly. Geomechanical problems in radioactive wastes disposal were discussed. Some suggestions were proposed for the radioactive wastes disposal in China

  17. Development of CANDU Spent Fuel Disposal Concepts for the Improvement of Disposal Efficiency

    International Nuclear Information System (INIS)

    There are two types of spent fuels generated from nuclear power plants, CANDU type and PWR type. PWR spent fuels which include a lot of reusable material can be considered to be recycled. CANDU spent fuels are considered to directly disposed in deep geological formation, since they have little reusable material. In this study, based on the Korean Reference spent fuel disposal System(KRS) which is to dispose both PWR and CANDU spent fuels, the more effective CANDU spent fuel disposal systems have been developed. To do this, the disposal canister has been modified to hold the storage basket which can load 60 spent fuel bundles. From these modified disposal canisters, the disposal systems to meet the thermal requirement for which the temperature of the buffer materials should not be over have been proposed. These new disposals have made it possible to introduce the concept of long term storage and retrievability and that of the two-layered disposal canister emplacement in one disposal hole. These disposal concepts have been compared and analyzed with the KRS CANDU spent fuel disposal system in terms of disposal effectiveness. New CANDU spent fuel disposal concepts obtained in this study seem to improve thermal effectiveness, U-density, disposal area, excavation volume, and closure material volume up to 30 - 40 %.

  18. Superfund Record of Decision (EPA Region 8): Sand Creek Industrial Site, operable unit 5, Commerce City, CO, (amendment), September 1993

    Energy Technology Data Exchange (ETDEWEB)

    1993-09-08

    This decision document is an amendment to the Record of Decision (ROD) signed September 28, 1990 (PB94-921479) and presents the new selected remedial action for cleanup of contaminated shallow soils at OU5 at the Sand Creek Industrial Superfund Site. OU5 is located immediately north of 52nd and Dahlia Street in Commerce City, Colorado. Based on new technical data and cost information obtained subsequent to the September 1990 ROD, EPA has reconsidered its decision to employ soil washing and incineration of the generated residuals as a source control measure for OU5.

  19. Chemical munitions dumped at sea

    Science.gov (United States)

    Edwards, Margo; Bełdowski, Jacek

    2016-06-01

    Modern chemical warfare is a byproduct of the industrial revolution, which created factories capable of rapidly producing artillery shells that could be filled with toxic chemicals such as chlorine, phosgene and mustard agent. The trench warfare of World War I inaugurated extensive deployments of modern chemical weapons in 1915. Concomitantly, the need arose to dispose of damaged, captured or excess chemical munitions and their constituents. Whereas today chemical warfare agents (CWA) are destroyed via chemical neutralization processes or high-temperature incineration in tandem with environmental monitoring, in the early to middle 20th century the options for CWA disposal were limited to open-air burning, burial and disposal at sea. The latter option was identified as the least likely of the three to impact mankind, and sea dumping of chemical munitions commenced. Eventually, the potential impacts of sea dumping human waste were recognized, and in 1972 an international treaty, the Convention on the Prevention of Marine Pollution by Dumping of Wastes and Other Matter, was developed to protect the marine environment from pollution caused by the dumping of wastes and other matter into the ocean. By the time this treaty, referred to as the London Convention, was signed by a majority of nations, millions of tons of munitions were known to have been disposed throughout the world's oceans.

  20. MAW and HTR fuel element test disposal in boreholes

    International Nuclear Information System (INIS)

    The Kernforschungsanlage Juelich, KFA, (Nuclear Research Center Juelich) has been handling a project since 1983 on 'Further Development of the Borehole Technology for the Disposal of Radioactive Wastes in Salt, with the Examples of Dissolver Sludge, Fuel Element Claddings, Fuel Hardware und HTR Fuel Elements'. The project is sponsored by the Bundesminister fuer Forschung und Technologie, BMFT, (Federal Ministry of Research and Technology) under the identification number KWA 5302 3 and bears the short title 'MAW and HTR Fuel Element Test Disposal in Boreholes'. The major objective of the project is to develop a technique for the disposal of the above mentioned wastes in unlined boreholes in salt and to test this technique in the Asse salt mine. The Institut fuer Chemische Technologie der Nuklearen Entsorgung, ICT (Institute of Chemical Technology) at the KFA is responsible for the scientific and organizational management of the project. The Institut fuer Tieflagerung, IfT, (Institute for Underground Disposal) of the Gesellschaft fuer Strahlen- und Umweltforschung mbH, GSF, (Society for Radiological and Environmental Research) is responsible for the geomechanical and mining activities in the project. It supervises the in-situ experiments, and as the owner of the Asse salt mine, it submits applications for the experiments to the licensing authorities. Geomechanical calculations are being carried out by the Bundesanstalt fuer Geowissenschaften und Rohstoffe, BGR, (Federal Institute for Geological Sciences and Natural Resources). (orig./RB)

  1. Greywater Disposal Practices in Northern Botswana--The Silent Spring?

    Science.gov (United States)

    Alexander, Kathleen A; Godrej, Adil

    2015-11-01

    Disposal of greywater is a neglected challenge facing rapidly growing human populations. Here, we define greywater as wastewater that originates from household activities (e.g., washing dishes, bathing, and laundry) but excludes inputs from the toilet. Pollutants in greywater can include both chemical and biological contaminates that can significantly impact human, animal, and environmental health under certain conditions. We evaluate greywater disposal practices in nonsewered, low-income residential areas in Kasane (264 dwellings/ha), Kazungula (100 du/ha), and Lesoma (99 du/ha) villages in Northern Botswana through household surveys (n = 30 per village). Traditional pit latrines were the dominant form of sanitation (69%, n = 90, 95% CI, 59%-79%) while 14% of households did not have access to onsite sanitation (95% CI 0%-22%). While greywater disposal practices varied across villages, respondents in all sites reported dumping greywater into the pit latrine. Frequency varied significantly across villages with the highest level reported in Kasane, where residential density was greatest (p resources. Challenges in greywater disposal and pit latrines must be addressed with urgency as health behaviors directed at minimizing negative aspects may amplify the environmental impacts of both greywater and pit latrine excreta. PMID:26580640

  2. Evaluation of Exposure to Radon Levels in Relation to Climatic Conditions at a Superfund Site.

    Science.gov (United States)

    Merrill, Elaine Alice

    1995-11-01

    Workers at a Superfund site have expressed concern that they may be exposed to elevated levels of radon gas, especially when meteorology is suitable. The site, formally a uranium processing site, stores the world's largest quantity of Ra-226 in two concrete silos. A layer of bentonite foam was placed over the contents of the silos in 1991 as a means to reduce the amount of radon emissions. Hourly real-time outdoor and indoor site radon data covering an entire year was statistically evaluated in relation to meteorological data covering the same time period. The hourly data was found to be lognormally distributed. Radon levels were highest during the early morning hours and during the summer months. Both outdoor and indoor concentrations were found to significantly vary with temporal and climatic factors, namely wind direction and relative humidity. Radon levels in the work areas were not found to be statistically different from off-site levels. Only radon levels in the vicinity of the storage silos, which is an exclusion zone, were significantly higher than levels off-site. Hence, the protective bentonite covering seems to be effective in reducing radon emissions. Two methods were used to calculate a hypothetical dose, based upon the annual average concentrations of radon in the work areas onsite, the BEIR IV method and the NCRP method, respectively. The BEIR IV method, which accounts for the activity ratio of radon and its daughter products, resulted in a slightly higher dose than the NCRP method. As expected, based on the mean concentrations, the hypothetical annual exposures from radon in the work areas of the site were below recommended exposure limits.

  3. Detection of environmentally persistent free radicals at a superfund wood treating site.

    Science.gov (United States)

    dela Cruz, Albert Leo N; Gehling, William; Lomnicki, Slawomir; Cook, Robert; Dellinger, Barry

    2011-08-01

    Environmentally persistent free radicals (EPFRs) have previously been observed in association with combustion-generated particles and airborne PM(2.5) (particulate matter, d 2.5um). The purpose of this study was to determine if similar radicals were present in soils and sediments at Superfund sites. The site was a former wood treating facility containing pentachlorophenol (PCP) as a major contaminant. Both contaminated and noncontaminated (just outside the contaminated area) soil samples were collected. The samples were subjected to the conventional humic substances (HS) extraction procedure. Electron paramagnetic resonance (EPR) spectroscopy was used to measure the EPFR concentrations and determine their structure for each sample fraction. Analyses revealed a ∼30× higher EPFR concentration in the PCP contaminated soils (20.2 × 10(17) spins/g) than in the noncontaminated soil (0.7 × 10(17) spins/g). Almost 90% of the EPFR signal originated from the minerals/clays/humins fraction. GC-MS analyses revealed ∼6500 ppm of PCP in the contaminated soil samples and none detected in the background samples. Inductively coupled plasma-atomic emission spectrophotometry (ICP-AES) analyses revealed ∼7× higher concentrations of redox-active transition metals, in the contaminated soils than the noncontaminated soil. Vapor phase and liquid phase dosing of the clays/minerals/humins fraction of the soil with PCP resulted in an EPR signal identical to that observed in the contaminated soil, strongly suggesting the observed EPFR is pentachlorophenoxyl radical. Chemisorption and electron transfer from PCP to transition metals and other electron sinks in the soil are proposed to be responsible for EPFR formation.

  4. Fracking, wastewater disposal, and earthquakes

    Science.gov (United States)

    McGarr, Arthur

    2016-03-01

    In the modern oil and gas industry, fracking of low-permeability reservoirs has resulted in a considerable increase in the production of oil and natural gas, but these fluid-injection activities also can induce earthquakes. Earthquakes induced by fracking are an inevitable consequence of the injection of fluid at high pressure, where the intent is to enhance permeability by creating a system of cracks and fissures that allow hydrocarbons to flow to the borehole. The micro-earthquakes induced during these highly-controlled procedures are generally much too small to be felt at the surface; indeed, the creation or reactivation of a large fault would be contrary to the goal of enhancing permeability evenly throughout the formation. Accordingly, the few case histories for which fracking has resulted in felt earthquakes have been due to unintended fault reactivation. Of greater consequence for inducing earthquakes, modern techniques for producing hydrocarbons, including fracking, have resulted in considerable quantities of coproduced wastewater, primarily formation brines. This wastewater is commonly disposed by injection into deep aquifers having high permeability and porosity. As reported in many case histories, pore pressure increases due to wastewater injection were channeled from the target aquifers into fault zones that were, in effect, lubricated, resulting in earthquake slip. These fault zones are often located in the brittle crystalline rocks in the basement. Magnitudes of earthquakes induced by wastewater disposal often exceed 4, the threshold for structural damage. Even though only a small fraction of disposal wells induce earthquakes large enough to be of concern to the public, there are so many of these wells that this source of seismicity contributes significantly to the seismic hazard in the United States, especially east of the Rocky Mountains where standards of building construction are generally not designed to resist shaking from large earthquakes.

  5. Generic Crystalline Disposal Reference Case

    Energy Technology Data Exchange (ETDEWEB)

    Painter, Scott Leroy [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Chu, Shaoping [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Harp, Dylan Robert [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Perry, Frank Vinton [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Wang, Yifeng [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2015-02-20

    A generic reference case for disposal of spent nuclear fuel and high-level radioactive waste in crystalline rock is outlined. The generic cases are intended to support development of disposal system modeling capability by establishing relevant baseline conditions and parameters. Establishment of a generic reference case requires that the emplacement concept, waste inventory, waste form, waste package, backfill/buffer properties, EBS failure scenarios, host rock properties, and biosphere be specified. The focus in this report is on those elements that are unique to crystalline disposal, especially the geosphere representation. Three emplacement concepts are suggested for further analyses: a waste packages containing 4 PWR assemblies emplaced in boreholes in the floors of tunnels (KBS-3 concept), a 12-assembly waste package emplaced in tunnels, and a 32-assembly dual purpose canister emplaced in tunnels. In addition, three failure scenarios were suggested for future use: a nominal scenario involving corrosion of the waste package in the tunnel emplacement concepts, a manufacturing defect scenario applicable to the KBS-3 concept, and a disruptive glaciation scenario applicable to both emplacement concepts. The computational approaches required to analyze EBS failure and transport processes in a crystalline rock repository are similar to those of argillite/shale, with the most significant difference being that the EBS in a crystalline rock repository will likely experience highly heterogeneous flow rates, which should be represented in the model. The computational approaches required to analyze radionuclide transport in the natural system are very different because of the highly channelized nature of fracture flow. Computational workflows tailored to crystalline rock based on discrete transport pathways extracted from discrete fracture network models are recommended.

  6. Radioactive wastes, disposal sites wanted

    International Nuclear Information System (INIS)

    Two towns that were selected by the French government to home a disposal site for low-level radioactive wastes, have withdrawn their bid. ANDRA (French national agency for the management of radioactive wastes) attributes this withdrawal to the unbearable pressure made by the opponents on the city councils despite the public information meetings that were held in the 2 cities. The selection rules included the presence of clay layers with a thickness of at least 50 m, the absence of seismic activity and zones containing exploitable resources like petroleum or metal ores were barred in order to avoid future unexpected drilling. (A.C.)

  7. Disposable optics for microscopy diagnostics.

    Science.gov (United States)

    Vilmi, Pauliina; Varjo, Sami; Sliz, Rafal; Hannuksela, Jari; Fabritius, Tapio

    2015-11-20

    The point-of-care testing (POCT) is having increasing role on modern health care systems due to a possibility to perform tests for patients conveniently and immediately. POCT includes lot of disposable devices because of the environment they are often used. For a disposable system to be reasonably utilized, it needs to be high in quality but low in price. Optics based POCT systems are interesting approach to be developed, and here we describe a low-cost fabrication process for microlens arrays for microscopy. Lens arrays having average lens diameter of 222 μm with 300 μm lens pitch were fabricated. The lenses were characterized to have standard deviation of 0.06 μm in height and 4.61 μm in diameter. The resolution limit of 3.9μm is demonstrated with real images, and the images were compared with ones made with glass and polycarbonate lens arrays. The image quality is at the same level than with the glass lenses and the manufacturing costs are very low, thus making them suitable for POCT applications.

  8. Disposable optics for microscopy diagnostics

    Science.gov (United States)

    Vilmi, Pauliina; Varjo, Sami; Sliz, Rafal; Hannuksela, Jari; Fabritius, Tapio

    2015-11-01

    The point-of-care testing (POCT) is having increasing role on modern health care systems due to a possibility to perform tests for patients conveniently and immediately. POCT includes lot of disposable devices because of the environment they are often used. For a disposable system to be reasonably utilized, it needs to be high in quality but low in price. Optics based POCT systems are interesting approach to be developed, and here we describe a low-cost fabrication process for microlens arrays for microscopy. Lens arrays having average lens diameter of 222 μm with 300 μm lens pitch were fabricated. The lenses were characterized to have standard deviation of 0.06 μm in height and 4.61 μm in diameter. The resolution limit of 3.9μm is demonstrated with real images, and the images were compared with ones made with glass and polycarbonate lens arrays. The image quality is at the same level than with the glass lenses and the manufacturing costs are very low, thus making them suitable for POCT applications.

  9. Management of low and intermediate level radioactive wastes with regard to their chemical toxicity

    International Nuclear Information System (INIS)

    A preliminary overview is provided of management options for low and intermediate level radioactive waste (LILW) with regard to its chemical toxicity. In particular, the following issues are identified and described associated with the management and safe disposal of chemically toxic materials in LILW: the origin and characteristics; the regulatory approaches; the pre-disposal management; the disposal; the safety assessment. Also included are: regulatory framework for chemically toxic low level wastes in the USA; pre-disposal processing options for LILW containing chemically toxic components; example treatment technologies for LILW containing chemically toxic components and safety assessment case studies for Germany, Belgium, France and Sweden

  10. Occurences and Fate of DDT Principal Isomers/Metabolites, DDA, and o,p'-DDD Enantiomers in Fish, Sediment and Water at a DDT-Impacted Superfund Site

    Science.gov (United States)

    In the 1950s and 60s, discharges from a DDT manufacturing plant contaminated a tributary system of the Tennessee River near Huntsville, Alabama, USA. Regulatory action resulted in declaring the area a Superfund site which required remediation and extensive monitoring. Monitoring ...

  11. Ethanol-Fed Or Solid-Phase Organic Sulfate Reducing Bioreactors For The National Tunnel Drainage, Clear Creek/Central City Superfund Site (Presentation)

    Science.gov (United States)

    The U.S. Environmental Protection Agency (EPA) is planning to treat mining influenced water (MIW) from the National Tunnel Adit that discharges to North Clear Creek near the City of Blackhawk, Colorado. North Clear Creek is part of the Clear Creek/Central City Superfund Site, an...

  12. Ethanol-Fed Or Solid-Phase Organic Sulfate Reducing Bioreactors For The National Tunnel Drainage, Clear Creek/Central City Superfund Site

    Science.gov (United States)

    The U.S. Environmental Protection Agency (EPA) is planning to treat mining influenced water (MIW) from the National Tunnel Adit that discharges to North Clear Creek near the City of Blackhawk, Colorado. North Clear Creek is part of the Clear Creek/Central City Superfund Site, an...

  13. Shallow land disposal of radioactive waste

    International Nuclear Information System (INIS)

    The application of basic radiation protection concepts and objectives to the disposal of radioactive wastes requires the development of specific reference levels or criteria for the radiological acceptance of each type of waste in each disposal option. This report suggests a methodology for the establishment of acceptance criteria for the disposal of low-level radioactive waste containing long-lived radionuclides in shallow land burial facilities

  14. Mechanical performance of disposable surgical needle holders.

    Science.gov (United States)

    Francis, E H; Towler, M A; Moody, F P; McGregor, W; Himel, H N; Rodeheaver, G T; Edlich, R F

    1992-01-01

    The mechanical performance of disposable Webster surgical needle holders supplied by three different surgical instrument companies was determined by recording the forces (clamping moment) applied by the different needle holder jaws to curved surgical needles. This investigation demonstrated that there was a large variability in the mechanical performance of the disposable needle holders supplied by each surgical instrument company. In addition, the mechanical performance of the disposable needle holder of each surgical instrument company was distinctly different.

  15. Recycling Engineering Of Disposal Of Waste Matter

    International Nuclear Information System (INIS)

    This book introduces conception of waste, generation of waste with generation and circulation of waste, waste generation amount, and classification of waste, management of waste, collection of waste on plan of collection, transportation and device of waste, waste management system such as extended producer responsibility, manifest system, exchange system of waste, volume-rate garbage disposal system, recycling of waste, including disposal technology for recycling waste, sanitary landfill, incineration, composting and human waste of disposal.

  16. Post-disposal safety assessment of toxic and radioactive waste: waste types, disposal practices, disposal criteria, assessment methods and post-disposal impacts

    International Nuclear Information System (INIS)

    The need for safety assessments of waste disposal stems not only from the implementation of regulations requiring the assessment of environmental effects, but also from the more general need to justify decisions on protection requirements. As waste-disposal methods have become more technologically based, through the application of more highly engineered design concepts and through more rigorous and specific limitations on the types and quantities of the waste disposed, it follows that assessment procedures also must become more sophisticated. It is the overall aim of this study to improve the predictive modelling capacity for post-disposal safety assessments of land-based disposal facilities through the development and testing of a comprehensive, yet practicable, assessment framework. This report records all the work which has been undertaken during Phase 1 of the study. Waste types, disposal practices, disposal criteria and assessment methods for both toxic and radioactive waste are reviewed with the purpose of identifying those features relevant to assessment methodology development. Difference and similarities in waste types, disposal practices, criteria and assessment methods between countries, and between toxic and radioactive wastes are highlighted and discussed. Finally, an approach to identify post-disposal impacts, how they arise and their effects on humans and the environment is described

  17. Safe, permanent disposal of used CANDU fuel

    International Nuclear Information System (INIS)

    AECL's assessment of nuclear fuel waste disposal deep in plutonic rock of the Canadian Precambrian Shield is now well advanced. A comprehensive understanding has evolved of the chemical and physical processes controlling the containment of radionuclides in used fuel. The following conclusions have been reached: containers with outer shells of titanium and copper can be expected to isolate used fuel from contact with groundwater for at least 500 years, the period during which the hazard is greatest; uranium oxide fuel can be expected to dissolve at a rate less than 10-8 per day, resulting in uranium concentrations less that 1 μg/L, which is consistent with observations of uranium oxide deposits in the earth's crust; movement of dissolved radionuclides away from the containers can be delayed for thousands of years by placing a compacted bentonite-clay layer between the container and the rock mass; and, the granite plutons of interest consist of relatively large rock volumes of low permeability separated by relatively thin fracture zones, and the low permeability volumes are sufficiently large to accommodate a vault design that will ensure radionuclides do not reach the surface in unacceptable concentrations

  18. Memorandum of Understanding Between U.S. EPA Superfund and U.S. NRC

    International Nuclear Information System (INIS)

    The Environmental Protection Agency (EPA) Office of Superfund Remediation and Technology Innovation (OSRTI) and the Nuclear Regulatory Commission (NRC) are responsible for implementing the 'Memorandum of Understanding Between the Environmental Protection Agency and the Nuclear Regulatory Commission: Consultation and Finality on Decommissioning and Decontamination of Contaminated Sites'. This paper provides a brief overview of the origin of the Memorandum of Understanding (MOU), the major features of the MOU, and how the MOU has been implemented site specifically. EPA and NRC developed the MOU in response to direction from the House Committee on Appropriations to EPA and NRC to work together to address the potential for dual regulation. The MOU was signed by EPA on September 30, 2002 and NRC on October 9, 2002. The two agencies had worked on the MOU since March 2000. While both EPA and NRC have statutory authority to clean up these sites, the MOU provides consultation procedures between EPA and NRC to eliminate dual regulation. Under the MOU, EPA and NRC identified the interactions of the two agencies for the decommissioning and decontamination of NRC-licensed sites and the ways in which those responsibilities will be exercised. Except for Section VI, which addresses corrective action under the Resource Conservation and Recovery Act (RCRA), this MOU is limited to the coordination between EPA, when acting under its CERCLA authority, and NRC, when a facility licensed by the NRC is undergoing decommissioning, or when a facility has completed decommissioning, and the NRC has terminated its license. EPA believes that implementation of the MOU between the two agencies will ensure that future confusion about dual regulation does not occur regarding the cleanup and reuse of NRC-licensed sites. NRC and EPA have so far exchanged MOU consultation letters on eight NRC-licensed sites. EPA has responded to each consultation request with a letter expressing its views on actions

  19. Nuclear waste disposal educational forum

    International Nuclear Information System (INIS)

    In keeping with a mandate from the US Congress to provide opportunities for consumer education and information and to seek consumer input on national issues, the Department of Energy's Office of Consumer Affairs held a three-hour educational forum on the proposed nuclear waste disposal legislation. Nearly one hundred representatives of consumer, public interest, civic and environmental organizations were invited to attend. Consumer affairs professionals of utility companies across the country were also invited to attend the forum. The following six papers were presented: historical perspectives; status of legislation (Senate); status of legislation (House of Representatives); impact on the legislation on electric utilities; impact of the legislation on consumers; implementing the legislation. All six papers have been abstracted and indexed for the Energy Data Base

  20. Stability of colistimethate sodium in a disposable elastomeric infusion device.

    Science.gov (United States)

    Abdulla, Alan; van Leeuwen, Roelof W F; de Vries Schultink, Aurelia H M; Koch, Birgit C P

    2015-01-01

    Infections of the respiratory tract with Pseudomonas aeruginosa in cystic fibrosis patients are frequently treated with colistimethate sodium (CMS). For the intravenous administration of CMS a disposable elastomeric pump is a convenient option. To date, there are no data available on the chemical stability of CMS solutions stored in elastomeric pumps. We evaluated the chemical stability of 0.8 mg/mL solutions of CMS by measuring the degradation over a period of 7 days. Test samples were prepared by diluting CMS with saline solution (0.9%). The preparations were transferred to 100-mL elastomeric pumps and stored at 4 °C. The chemical stability was measured by a high-performance liquid chromatography method with UV detection. There was no degradation of CMS (elastomeric pump. PMID:25863116

  1. Characterization and remediation of soil prior to construction of an on-site disposal facility at Fernald

    International Nuclear Information System (INIS)

    During the production years at the Feed Materials Production Center (FMPC), the soil of the site and the surrounding areas was surficially impacted by airborne contamination. The volume of impacted soil is estimated at 2.2 million cubic yards. During site remediation, this contamination will be excavated, characterized, and disposed of. In 1986 the US Environmental Protection Agency (EPA) and the Department of Energy (DOE) entered into a Federal Facility Compliance Agreement (FFCA) covering environmental impacts associated with the FMPC. A site wide Remedial Investigation/Feasibility Study (RI/FS) was initiated pursuant to the Comprehensive Environmental Response, Compensation, and Liability Act, as amended by the Superfund Amendments and Reauthorization Act (CERCLA). The DOE has completed the RI/FS process and has received approval of the final Records of Decision. The name of the facility was changed to the Fernald Environmental Management Project (FEMP) to emphasize the change in mission to environmental restoration. Remedial actions which address similar scopes of work or types of contaminated media have been grouped into remedial projects for the purpose of managing the remediation of the FEMP. The Soil Characterization and Excavation Project (SCEP) will address the remediation of FEMP soils, certain waste units, at- and below-grade material, and will certify attainment of the final remedial limits (FRLs) for the FEMP. The FEMP will be using an on-site facility for low level radioactive waste disposal. The facility will be an above-ground engineered structure constructed of geological material. The area designated for construction of the base of the on-site disposal facility (OSDF) is referred to as the footprint. Contaminated soil within the footprint must be identified and remediated. Excavation of Phase 1, the first of seven remediation areas, is complete

  2. Monitoring the Performance of an Alternative Landfill Cover at the Monticello, Utah, Uranium Mill Tailings Disposal Site

    International Nuclear Information System (INIS)

    The U.S. Department of Energy Office of Legacy Management (DOE) and the U.S. Environmental Protection Agency (EPA) collaborated on the design and monitoring of an alternative cover for the Monticello uranium mill tailings disposal cell, a Superfund site in southeastern Utah. Ground-water recharge is naturally limited at sites like Monticello where thick, fine-textured soils store precipitation until evaporation and plant transpiration seasonally return it to the atmosphere. The cover at Monticello uses local soils and a native plant community to mimic the natural soil water balance. The cover is fundamentally an evapotranspiration (ET) design with a capillary barrier. A 3-hectare drainage lysimeter was embedded in the cover during construction of the disposal cell in 2000. The lysimeter consists of a geo-membrane liner below the capillary barrier that directs percolation water to a monitoring system. Soil water storage is determined by integration of point water content measurements. Meteorological parameters are measured nearby. Plant cover, shrub density, and leaf area index (LAI) are monitored annually. The cover performed well over the 7-year monitoring period (2000-2007). The cumulative percolation was 4.2 mm (0.6 mm yr-1), satisfying an EPA goal of an average percolation of -1. Almost all percolation can be attributed to the exceptionally wet winter and spring of 2004-2005 when soil water content slightly exceeded the water storage capacity of the cover. The diversity, percent cover, and LAI of vegetation increased over the monitoring period, although the density of native shrubs that extract water from deeper in the cover has remained less than revegetation targets. DOE and EPA are applying the monitoring results to plan for long-term surveillance and maintenance and to evaluate alternative cover designs for other waste disposal sites. (authors)

  3. 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.

  4. TECHNO – ECONOMIC ACCEPTABILITY ANALISYS OF WASTE DISPOSAL BY INJECTION INTO APPROPRIATE FORMATION

    Directory of Open Access Journals (Sweden)

    Vladislav Brkić

    2013-12-01

    Full Text Available During exploration and production of oil and natural gas, various types of waste must be disposed in a permanent and safe way. There is a range of methods for processing and disposal of waste, such as disposal into landfills, solidification, namely chemical stabilization, thermal processing, appropriate formation injections uncovered by a deep well, disposal into salt domes and bioremediation. The method of waste disposal into appropriate formations is a method where strict geological and technical criteria must be satisfied when applied. A fundamental scientific hypothesis has been formulated whereby economic acceptability of the waste injection method, as a main method for waste disposal, is to be shown by an economic evaluation. The results of this research are relevant since there has been an intention in Croatia and worldwide to abandon wells permanently due to oil and gas reservoirs depletion and therefore it is essential to estimate economic impacts of the waste injection method application. In that way, profitability of using existing wells for waste disposal in oil industry has been increased, leading to the improvement of petroleum company’s business activities (the paper is published in Croatian.

  5. Magnox fuel dry storage and direct disposal assessment of CEGB/SSEB reports

    International Nuclear Information System (INIS)

    This report assesses the Boards' presented work in response to Recommendations 17 and 18 of the Environment Committee's First Report (Jan 86). The Boards have made an extensive study of the dry store design and also considered direct disposal. Their basic conclusion that the financial advantage is with continued reprocessing is accepted with the comment that their storage and disposal costs may be on the high side. The Boards statements on drying wet-stored fuel and on improvement of the fuel's chemical stability are accepted. The Boards coverage of fuel after disposal is considered to be too brief; the assessment expresses a more pessimistic view than the Boards' of the acceptability of direct disposal. (author)

  6. Preliminary Borehole Disposal In Medium Flow Hydrogeological Condition Using IAEA Screening Tools

    International Nuclear Information System (INIS)

    A screening tool developed by International Atomic Energy Agency (IAEA) has been used to provide means of improving the capacity of Malaysian Nuclear Agency (Nuclear Malaysia) in assessing the potential sites for Borehole Disposal for Disused Sealed Radioactive Sources. It allows the isolation provided by the capsule and disposal container to be evaluated. In addition, it has a conservative model of radionuclide transport with no retardation of radionuclide. Hence, rapid decisions can be made by providing an early indication of the potential suitability of sites based on their hydro-chemical characteristics. The objective of this paper is to identify and determine the types and radionuclide activities of inventory that can be disposed in the borehole. The results of the analysis show the volume of gas doses occur from the disposal and time taken for the cement to be corroded. (author)

  7. Modeling of low-level-waste disposal for environmental impact analysis

    International Nuclear Information System (INIS)

    A computer model was developed to analyze environmental impacts resulting from disposal of both radioactive and chemical wastes. The model simulates a waste-disposal system and includes infiltration through disposal cell caps, source leach rates, and solute transport in geologic media. The solute transport model used is a modified version of an analytical code originally developed at Oak Ridge National Laboratory. The solute transport code was modified based on the Group-Transfer Concentration concept developed by the author. The original model is applicable only to homogeneous media under saturated conditions, but the modified model extends applicability to nonhomogeneous media (layered soils and fractures) and partially saturated conditions. The modified model has broader applicability, e.g., it can be applied to both humid and arid waste-disposal sites, and it is also more practical for environmental impact analysis. 22 refs., 2 tabs

  8. Crystalline and Crystalline International Disposal Activities

    Energy Technology Data Exchange (ETDEWEB)

    Viswanathan, Hari S. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Chu, Shaoping [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Reimus, Paul William [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Makedonska, Nataliia [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Hyman, Jeffrey De' Haven [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Karra, Satish [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Dittrich, Timothy M. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2015-12-21

    This report presents the results of work conducted between September 2014 and July 2015 at Los Alamos National Laboratory in the crystalline disposal and crystalline international disposal work packages of the Used Fuel Disposition Campaign (UFDC) for DOE-NE’s Fuel Cycle Research and Development program.

  9. Hydrologic implications of solid-water disposal

    Science.gov (United States)

    Schneider, William Joseph

    1970-01-01

    The disposal of more than 1,400 million pounds of solid wastes in the United States each day is a major problem. This disposal in turn often leads to serious health, esthetic, and environmental problems. Among these is the pollution of vital ground-water resources.

  10. Radioactive waste products - suitability for final disposal

    International Nuclear Information System (INIS)

    48 papers were read at the conference. Separate records are available for all of them. The main problem in radioactive waste disposal was the long-term sealing to prevent pollution of the biosphere. Problems of conditioning, acceptance, and safety measures were discussed. Final disposal models and repositories were presented. (PW)

  11. Medications at School: Disposing of Pharmaceutical Waste

    Science.gov (United States)

    Taras, Howard; Haste, Nina M.; Berry, Angela T.; Tran, Jennifer; Singh, Renu F.

    2014-01-01

    Background: This project quantified and categorized medications left unclaimed by students at the end of the school year. It determined the feasibility of a model medication disposal program and assessed school nurses' perceptions of environmentally responsible medication disposal. Methods: At a large urban school district all unclaimed…

  12. Probabilistic safety assessment in radioactive waste disposal

    International Nuclear Information System (INIS)

    Probabilistic safety assessment codes are now widely used in radioactive waste disposal assessments. This report gives an overview of the current state of the field. The relationship between the codes and the regulations covering radioactive waste disposal is discussed and the characteristics of current codes is described. The problems of verification and validation are considered. (author)

  13. 7 CFR 2902.21 - Disposable containers.

    Science.gov (United States)

    2010-01-01

    ... Guideline, 40 CFR 247.10. EPA provides recovered materials content recommendations for paper and paper... 7 Agriculture 15 2010-01-01 2010-01-01 false Disposable containers. 2902.21 Section 2902.21... Items § 2902.21 Disposable containers. (a) Definition. Products designed to be used for...

  14. Tritium waste disposal technology in the US

    International Nuclear Information System (INIS)

    Tritium waste disposal methods in the US range from disposal of low specific activity waste along with other low-level waste in shallow land burial facilities, to disposal of kilocurie amounts in specially designed triple containers in 65' deep augered holes located in an aird region of the US. Total estimated curies disposed of are 500,000 in commercial burial sites and 10 million curies in defense related sites. At three disposal sites in humid areas, tritium has migrated into the ground water, and at one arid site tritium vapor has been detected emerging from the soil above the disposal area. Leaching tests on tritium containing waste show that tritium in the form of HTO leaches readily from most waste forms, but that leaching rates of tritiated water into polymer impregnated concrete are reduced by as much as a factor of ten. Tests on improved tritium containment are ongoing. Disposal costs for tritium waste are 7 to 10 dollars per cubic foot for shallow land burial of low specific activity tritium waste, and 10 to 20 dollars per cubic foot for disposal of high specific activity waste. The cost of packaging the high specific activity waste is 150 to 300 dollars per cubic foot. 18 references

  15. User's guide to the 'DISPOSALS' model

    International Nuclear Information System (INIS)

    This report provides a User's Guide to the 'DISPOSALS' computer model and includes instructions on how to set up and run a specific problem together with details of the scope, theoretical basis, data requirements and capabilities of the model. The function of the 'DISPOSALS' model is to make assignments of nuclear waste material in an optimum manner to a number of disposal sites each subject to a number of constraints such as limits on the volume and activity. The user is able to vary the number of disposal sites, the range and limits of the constraints to be applied to each disposal site and the objective function for optimisation. The model is based on the Linear Programming technique and uses CAP Scientific's LAMPS and MAGIC packages. Currently the model has been implemented on CAP Scientific's VAX 11/750 minicomputer. (author)

  16. Generic Argillite/Shale Disposal Reference Case

    Energy Technology Data Exchange (ETDEWEB)

    Zheng, Liange; Colon, Carlos Jové; Bianchi, Marco; Birkholzer, Jens

    2014-08-08

    Radioactive waste disposal in a deep subsurface repository hosted in clay/shale/argillite is a subject of widespread interest given the desirable isolation properties, geochemically reduced conditions, and widespread geologic occurrence of this rock type (Hansen 2010; Bianchi et al. 2013). Bianchi et al. (2013) provides a description of diffusion in a clay-hosted repository based on single-phase flow and full saturation using parametric data from documented studies in Europe (e.g., ANDRA 2005). The predominance of diffusive transport and sorption phenomena in this clay media are key attributes to impede radionuclide mobility making clay rock formations target sites for disposal of high-level radioactive waste. The reports by Hansen et al. (2010) and those from numerous studies in clay-hosted underground research laboratories (URLs) in Belgium, France and Switzerland outline the extensive scientific knowledge obtained to assess long-term clay/shale/argillite repository isolation performance of nuclear waste. In the past several years under the UFDC, various kinds of models have been developed for argillite repository to demonstrate the model capability, understand the spatial and temporal alteration of the repository, and evaluate different scenarios. These models include the coupled Thermal-Hydrological-Mechanical (THM) and Thermal-Hydrological-Mechanical-Chemical (THMC) models (e.g. Liu et al. 2013; Rutqvist et al. 2014a, Zheng et al. 2014a) that focus on THMC processes in the Engineered Barrier System (EBS) bentonite and argillite host hock, the large scale hydrogeologic model (Bianchi et al. 2014) that investigates the hydraulic connection between an emplacement drift and surrounding hydrogeological units, and Disposal Systems Evaluation Framework (DSEF) models (Greenberg et al. 2013) that evaluate thermal evolution in the host rock approximated as a thermal conduction process to facilitate the analysis of design options. However, the assumptions and the

  17. Transport and nuclear waste disposal

    International Nuclear Information System (INIS)

    The author assesses both past and future of nuclear waste disposal in Germany. The failure of the disposal concept is, he believes, mainly the fault of the Federal Government. On the basis of the Nuclear Energy Act, the government is obliged to ensure that ultimate-storage sites are established and operated. Up to the present, however, the government has failed - apart from the episode in Asse and Morsleben and espite existing feasible proposals in Konrad and Gorleben - to achieve this objective. This negative development is particularly evident from the projects which have had to be prematurely abandoned. The costs of such 'investment follies' meanwhile amount to several billion DM. At least 92% of the capacity in the intermediate-storage sites are at present unused. Following the closure of the ultimate-storage site in Morsleben, action must be taken to change over to long-term intermediate-storage of operational waste. The government has extensive intermediate-storage capacity at the intermediate-storage site Nord in Greifswald. There, the wate originally planned for storage in Morsleben could be intermediately stored at ERAM-rates. Nuclear waste transportation, too, could long ago have been resumed, in the author's view. For the purpose of improving the transport organisation, a new company was founded which represents exclusively the interests of the reprocessing firms at the nuclear power stations. The author's conclusion: The EVU have done their homework properly and implemented all necessary measures in order to be able to resume transport of fuel elements as soon as possible. The generating station operators favour a solution based upon agreement with the Federal Government. The EVU have already declared their willingness - in the event of unanimous agreement - to set up intermediate-storage sites near the power stations. The ponds in the generating stations, however, are unsuitable for use as intermediate-storage areas. If intermediate-storage areas for

  18. Proceedings of the 1981 subseabed disposal program. Annual workshop

    International Nuclear Information System (INIS)

    The 1981 Annual Workshop was the twelfth meeting of the principal investigators and program management personnel participating in the Subseabed Disposal Program (SDP). The first workshop was held in June 1973, to address the development of a program (initially known as Ocean Basin Floors Program) to assess the deep sea disposal of nuclear wastes. Workshops were held semi-annually until late 1977. Since November 1977, the workshops have been conducted following the end of each fiscal year so that the program participants could review and critique the total scope of work. This volume contains a synopsis, as given by each Technical Program Coordinator, abstracts of each of the talks, and copies of the visual materials, as presented by each of the principal investigators, for each of the technical elements of the SDP for the fiscal year 1981. The talks were grouped under the following categories; general topics; site studies; thermal response studies; emplacement studies; systems analysis; chemical response studies; biological oceanography studies; physical oceanographic studies; instrumentation development; transportation studies; social environment; and international seabed disposal

  19. Proceedings of the 1981 subseabed disposal program. Annual workshop

    Energy Technology Data Exchange (ETDEWEB)

    1982-01-01

    The 1981 Annual Workshop was the twelfth meeting of the principal investigators and program management personnel participating in the Subseabed Disposal Program (SDP). The first workshop was held in June 1973, to address the development of a program (initially known as Ocean Basin Floors Program) to assess the deep sea disposal of nuclear wastes. Workshops were held semi-annually until late 1977. Since November 1977, the workshops have been conducted following the end of each fiscal year so that the program participants could review and critique the total scope of work. This volume contains a synopsis, as given by each Technical Program Coordinator, abstracts of each of the talks, and copies of the visual materials, as presented by each of the principal investigators, for each of the technical elements of the SDP for the fiscal year 1981. The talks were grouped under the following categories; general topics; site studies; thermal response studies; emplacement studies; systems analysis; chemical response studies; biological oceanography studies; physical oceanographic studies; instrumentation development; transportation studies; social environment; and international seabed disposal.

  20. Retention Capability of Local Backfill Materials 1-Simulated Disposal Environment

    International Nuclear Information System (INIS)

    In Egypt, a shallow ground disposal facility was the chosen option for the disposal of low and and intermediate radioactive wastes. The impact of the waste disposal facility on the environment depends on the nature of the barriers, which intend to limit and control contaminant migration. Owing to their physical, chemical and mechanical characteristics. Local soil materials were studied to illustrate the role of the back fill as part of an optimized safety multi-barrier system, which can provide the required level of protection of the environment and meet economic and regulatory requirements. A theoretical model was proposed to calculate the transport phenomena through the backfill materials. The credibility and validity of the proposed model was checked by the experimental results obtained from a three-arms arrangement system. The obtained data for the distribution coefficient (Kd) and the apparent diffusion coefficient (Da) were in good agreement with those previously obtained in the literatures. Taking in consideration the prevailing initial conditions, the data calculated by the theoretical model applied show a reasonable agreement with the results obtained from experimental work. Prediction of radioactive cesium migration through the backfill materials using the proposed model was performed as a function of distance. The results obtained show that after 100 years, a fraction not exceeding 1E-9 of the original activity could be detected at 1m distance away from the waste material

  1. Selection of disposal contractor by multi criteria decision making methods

    Directory of Open Access Journals (Sweden)

    Cenker Korkmazer

    2016-08-01

    Full Text Available Hazardous waste is substance that threaten people and environment in case of improper storage, disposal and transport due to its concentration, physical and chemical properties. Companies producing hazardous waste as a result of several activities mostly do not have any own disposal facilities. In addition, they do not pay attention enough to determine the right contractor as a disposal facility. On the other hand, there are various qualitative and quantitative criteria affecting the selection of the contractor and conflicting with each other. The aim of the performed study is to assist one of these companies producing hazardous waste in the selection of the best contractor that eliminates hazardous waste economic and harmless way. In the study, contractor weights in percentage is calculated by using Analytic Network Process (ANP as one of the multi-criteria decision making (MCDM methods and widely used in the literature which considers both qualitative and quantitative criteria. In the next step, by the help of the mathematical model, contractors that will be given which type of hazardous waste are identified. This integrated approach can be used as a guide for similar firms.

  2. Comprehensive Environmental Response, Compensation, and Liability Act, as amended by the Superfund Amendments and Reauthorization Act Section 120(e)(5)

    International Nuclear Information System (INIS)

    The US Department of Energy (DOE) is committed to conducting its operations. In a safe and environmentally sound manner. High priorities for the Department are identifying and correcting environmental problems at DOE facilities that resulted from past operations, and preventing environmental problems from occurring during present and future operations. In this regard, the Department is committed to the 30-year goal of cleanup of all facilities by the year 2019. DOE has issued an Order and guidance establishing policy and procedures for activities conducted under the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA), as amended by the Superfund Amendments and Reauthorization Act (SARA), and has developed a Five-Year Plan, updated annually, that integrates planing for corrective activities, environmental restoration, and waste management operations at its facilities. During Calendar Year 1991 and early 1992, DOE made significant progress in reaching agreements with regulatory entities, undertaking cleanup actions, and initiating preventive measures designed to eliminate future environmental problems. These accomplishments are described

  3. Feasibility Study of Economics and Performance of Solar Photovoltaics at the Stringfellow Superfund Site in Riverside, California

    Energy Technology Data Exchange (ETDEWEB)

    Mosey, G.; Van Geet, O.

    2010-12-01

    This report presents the results of an assessment of the technical and economic feasibility of deploying a photovoltaics (PV) system on the Stringfellow Superfund Site in Riverside, California. The site was assessed for possible PV installations. The cost, performance, and site impacts of different PV options were estimated. The economics of the potential systems were analyzed using an electric rate of $0.13/kWh and incentives offered by Southern California Edison under the California Solar Initiative. According to the assessment, a government-owned, ground-mounted PV system represents a technically and economically feasible option. The report recommends financing options that could assist in the implementation of such a system.

  4. Investigation of total and hexavalent chromium in filtered and unfiltered groundwater samples at the Tucson International Airport Superfund Site

    Science.gov (United States)

    Tillman, Fred; McCleskey, R. Blaine; Hermosillo, Edyth

    2016-01-01

    Potential health effects from hexavalent chromium in groundwater have recently become a concern to regulators at the Tucson International Airport Area Superfund site. In 2016, the U.S. Geological Survey sampled 46 wells in the area to characterize the nature and extent of chromium in groundwater, to understand what proportion of total chromium is in the hexavalent state, and to determine if substantial differences are present between filtered and unfiltered chromium concentrations. Results indicate detectable chromium concentrations in all wells, over 75 % of total chromium is in the hexavalent state in a majority of wells, and filtered and unfiltered results differ substantially in only a few high-turbidity total chromium samples.

  5. Inspection of disposal canisters components

    International Nuclear Information System (INIS)

    This report presents the inspection techniques of disposal canister components. Manufacturing methods and a description of the defects related to different manufacturing methods are described briefly. The defect types form a basis for the design of non-destructive testing because the defect types, which occur in the inspected components, affect to choice of inspection methods. The canister components are to nodular cast iron insert, steel lid, lid screw, metal gasket, copper tube with integrated or separate bottom, and copper lid. The inspection of copper material is challenging due to the anisotropic properties of the material and local changes in the grain size of the copper material. The cast iron insert has some acoustical material property variation (attenuation, velocity changes, scattering properties), which make the ultrasonic inspection demanding from calibration point of view. Mainly three different methods are used for inspection. Ultrasonic testing technique is used for inspection of volume, eddy current technique, for copper components only, and visual testing technique are used for inspection of the surface and near surface area

  6. Processing Irradiated Beryllium For Disposal

    Energy Technology Data Exchange (ETDEWEB)

    T. J. Tranter; R. D. Tillotson; N. R. Mann; G. R. Longhurst

    2005-11-01

    The purpose of this research was to develop a process for decontaminating irradiated beryllium that will allow it to be disposed of through normal radwaste channels. Thus, the primary objectives of this ongoing study are to remove the transuranic (TRU) isotopes to less than 100 nCi/g and remove {sup 60}Co, and {sup 137}Cs, to levels that will allow the beryllium to be contact handled. One possible approach that appears to have the most promise is aqueous dissolution and separation of the isotopes by selected solvent extraction followed by precipitation, resulting in a granular form for the beryllium that may be fixed to prevent it from becoming respirable and therefore hazardous. Beryllium metal was dissolved in nitric and fluorboric acids. Isotopes of {sup 241}Am, {sup 239}Pu, {sup 85}Sr, and {sup 137}Cs were then added to make a surrogate beryllium waste solution. A series of batch contacts was performed with the spiked simulant using chlorinated cobalt dicarbollide (CCD) and polyethylene glycol diluted with sulfone to extract the isotopes of Cs and Sr. Another series of batch contacts was performed using a combination of octyl (phenyl)-N,N-diisobutylcarbamoylmethylphosphine oxide (CMPO) in tributyl phosphate (TBP) diluted with dodecane for extracting the isotopes of Pu and Am. The results indicate that greater than 99.9% removal can be achieved for each isotope with only three contact stages.

  7. Mine waste disposal and managements

    Energy Technology Data Exchange (ETDEWEB)

    Cheong, Young Wook; Min, Jeong Sik; Kwon, Kwang Soo; Kim, Ok Hwan; Kim, In Kee; Song, Won Kyong; Lee, Hyun Joo [Korea Institute of Geology Mining and Materials, Taejon (Korea)

    1998-12-01

    Acid Rock Drainage (ARD) is the product formed by the atmospheric oxidation of the relatively common pyrite and pyrrhotite. Waste rock dumps and tailings containing sulfide mineral have been reported at toxic materials producing ARD. Mining in sulphide bearing rock is one of activity which may lead to generation and release of ARD. ARD has had some major detrimental affects on mining areas. The purpose of this study was carried out to develop disposal method for preventing contamination of water and soil environment by waste rocks dump and tailings, which could discharge the acid drainage with high level of metals. Scope of this study was as following: environmental impacts by mine wastes, geochemical characteristics such as metal speciation, acid potential and paste pH of mine wastes, interpretation of occurrence of ARD underneath tailings impoundment, analysis of slope stability of tailings dam etc. The following procedures were used as part of ARD evaluation and prediction to determine the nature and quantities of soluble constituents that may be washed from mine wastes under natural precipitation: analysis of water and mine wastes, Acid-Base accounting, sequential extraction technique and measurement of lime requirement etc. In addition, computer modelling was applied for interpretation of slope stability od tailings dam. (author). 44 refs., 33 tabs., 86 figs.

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

    Energy Technology Data Exchange (ETDEWEB)

    Price, L. [Science Applications International Corp., Albuquerque, NM (United States)

    1994-09-01

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

  9. Post-Remediation Biomonitoring of Pesticides in Marine Waters Near the United Heckathorn Superfund Site, Richmond, California

    Energy Technology Data Exchange (ETDEWEB)

    LD Antrim; NP Kohn

    2000-09-05

    This report, PNNL-11911 Rev. 1, was published in July 2000 and replaces PNNL-11911, which was published in September 1998. The revision corrects tissue concentration units that were reported as dry weight but were actually wet weight, and updates conclusions based on the correct reporting units. Marine sediment remediation at the United Heckathorn Superfund Site was completed in April 1997. Water and mussel tissues were sampled in January 1998 from four stations near Lauritzen Canal in Richmond, California, for the first post-remediation monitoring of marine areas near the United Heckathorn Site. Dieldrin and DDT were analyzed in water samples, tissue samples from resident mussels, and tissue samples from transplanted mussels deployed for 4 months. Concentrations of dieldrin and total DDT in water and total DDT in tissue were compared to pre-remediation data available from the California State Mussel Watch program (tissues) and the Ecological Risk Assessment for the United Heckathorn Superfund Site (tissues and water). Chlorinated pesticide concentrations in water samples were similar to pre-remediation levels and did not meet remediation goals. Mean dieldrin concentrations in water ranged from 0.65 ng/L to 18.1 ng/L and were higher than the remediation goal (0.14 ng/L) at all stations. Mean total DDT concentrations in water ranged from 0.65 ng/L to 103 ng/L and exceeded the remediation goal of 0.59 ng/L. The highest concentrations of both pesticides were found in Lauritzen Canal, and the lowest levels were from the Richmond Inner Harbor Channel water. Unusual amounts of detritus in the water column at the time of sampling, particularly in Lauritzen Canal, could have contributed to the elevated pesticide concentrations and poor analytical precision.

  10. Post-Remediation Biomonitoring of Pesticides in Marine Waters Near the United Heckathorn Superfund Site, Richmond, California; TOPICAL

    International Nuclear Information System (INIS)

    This report, PNNL-11911 Rev. 1, was published in July 2000 and replaces PNNL-11911, which was published in September 1998. The revision corrects tissue concentration units that were reported as dry weight but were actually wet weight, and updates conclusions based on the correct reporting units. Marine sediment remediation at the United Heckathorn Superfund Site was completed in April 1997. Water and mussel tissues were sampled in January 1998 from four stations near Lauritzen Canal in Richmond, California, for the first post-remediation monitoring of marine areas near the United Heckathorn Site. Dieldrin and DDT were analyzed in water samples, tissue samples from resident mussels, and tissue samples from transplanted mussels deployed for 4 months. Concentrations of dieldrin and total DDT in water and total DDT in tissue were compared to pre-remediation data available from the California State Mussel Watch program (tissues) and the Ecological Risk Assessment for the United Heckathorn Superfund Site (tissues and water). Chlorinated pesticide concentrations in water samples were similar to pre-remediation levels and did not meet remediation goals. Mean dieldrin concentrations in water ranged from 0.65 ng/L to 18.1 ng/L and were higher than the remediation goal (0.14 ng/L) at all stations. Mean total DDT concentrations in water ranged from 0.65 ng/L to 103 ng/L and exceeded the remediation goal of 0.59 ng/L. The highest concentrations of both pesticides were found in Lauritzen Canal, and the lowest levels were from the Richmond Inner Harbor Channel water. Unusual amounts of detritus in the water column at the time of sampling, particularly in Lauritzen Canal, could have contributed to the elevated pesticide concentrations and poor analytical precision

  11. Evaluation of Dredged Material Proposed for Ocean Disposal from Port Chester, New York

    Energy Technology Data Exchange (ETDEWEB)

    Barrows, E.S.; Mayhew, H.L.; Word, J.Q.; Tokos, J.J.S. [Battelle Marine Sciences Laboratory, Sequim, WA (United States)

    1996-08-01

    Port Chester was one of seven waterways that the US Army Corps of Engineers-New York District requested the Battelle Marine Sciences Laboratory to sample and evaluate for dredging and disposal in March 1994. Tests and analyses were conducted on Port Chester sediment core samples. Because the Port Chester area is located on the border between New York and southeast Connecticut, its dredged material may also be considered for disposal at the Central Long Island Sound Disposal Site. The sediment evaluation consisted of bulk sediment chemical analyses, chemical analyses of site water and dredged material elutriate preparations, water-column and benthic acute toxicity tests, and bioaccumulation studies. Individual sediment core samples collected from Port Chester were analyzed for grain size, moisture content, and total organic carbon. In addition, sediment was analyzed for bulk density, specific gravity, metals, chlorinated pesticides, polychlorinated biphenyl congers, polynuclear aromatic hydrocarbons and 1,4-dichlorobenzene.

  12. The Dutch geologic radioactive waste disposal project

    International Nuclear Information System (INIS)

    The Final Report reviews the work on geologic disposal of radioactive waste performed in the Netherlands over the period 1 January 1978 to 31 December 1979. The attached four topical reports cover detailed subjects of this work. The radionuclide release consequences of an accidental flooding of the underground excavations during the operational period was studied by the institute for Atomic Sciences in Agriculture (Italy). The results of the quantitative examples made for different effective cross-sections of the permeable layer connecting the mine excavations with the boundary of the salt dome, are that under all circumstances the concentration of the waste nuclides in drinking water will remain well within the ICRP maximum permissible concentrations. Further analysis work was done on what minima can be achieved for both the maximum local rock salt temperatures at the disposal borehole walls and the maximum global rock salt temperatures halfway between a square of disposal boreholes. Different multi-layer disposal configurations were analysed and compared. A more detailed description is given of specific design and construction details of a waste repository such as the shaft sinking and construction, the disposal mine development, the mine ventilation and the different plugging and sealing procedures for both the disposal boreholes and the shafts. Thanks to the hospitality of the Gesellschaft fuer Strahlenforschung, an underground working area in the Asse mine became available for performing a dry drilling experiment, which resulted successfully in the drilling of a 300 m deep disposal borehole from a mine room at the -750 m level

  13. Spent nuclear fuel disposal liability insurance

    International Nuclear Information System (INIS)

    This thesis examines the social efficiency of nuclear power when the risks of accidental releases of spent fuel radionuclides from a spent fuel disposal facility are considered. The analysis consists of two major parts. First, a theoretical economic model of the use of nuclear power including the risks associated with releases of radionuclides from a disposal facility is developed. Second, the costs of nuclear power, including the risks associated with a radionuclide release, are empirically compared to the costs of fossil fuel-fired generation of electricity. Under the provisions of the Nuclear Waste Policy Act of 1982, the federally owned and operated spent nuclear fuel disposal facility is not required to maintain a reserve fund to cover damages from an accidental radionuclide release. Thus, the risks of a harmful radionuclide release are not included in the spent nuclear fuel disposal fee charged to the electric utilities. Since the electric utilities do not pay the full, social costs of spent fuel disposal, they use nuclear fuel in excess of the social optimum. An insurance mechanism is proposed to internalize the risks associated with spent fueled disposal. Under this proposal, the Federal government is required to insure the disposal facility against any liabilities arising from accidental releases of spent fuel radionuclides

  14. Geological aspects of radioactive waste disposal

    International Nuclear Information System (INIS)

    Geological formations suitable for burying various types of radioactive wastes are characterized applying criteria for the evaluation and selection of geological formations for building disposal sites for radioactive wastes issued in IAEA technical recommendations. They are surface disposal sites, disposal sites in medium depths and deep disposal sites. Attention is focused on geological formations usable for injecting self-hardening mixtures into cracks prepared by hydraulic decomposition and for injecting liquid radioactive wastes into permeable rocks. Briefly outlined are current trends of the disposal of radioactive wastes in Czechoslovakia and the possibilities are assessed from the geological point of view of building disposal sites for radioactive wastes on the sites of Czechoslovak nuclear power plants at Jaslovske Bohunice, Mochovce, Dukovany, Temelin, Holice (eastern Bohemia), Blahoutovice (northern Moravia) and Zehna (eastern Slovakia). It is stated that in order to design an optimal method of the burial of radioactive waste it will be necessary to improve knowledge of geological conditions in the potential disposal sites at the said nuclear plants. There is usually no detailed knowledge of geological and hydrological conditions at greater depths than 100 m. (Z.M.)

  15. The disposal of radioactive waste on land

    Energy Technology Data Exchange (ETDEWEB)

    None

    1957-09-01

    A committee of geologists and geophysicists was established by the National Academy of Sciences-National Research Council at the request of the Atomic Energy Commission to consider the possibilities of disposing of high level radioactive wastes in quantity within the continental limits of the United States. The group was charged with assembling the existing geologic information pertinent to disposal, delineating the unanswered problems associated with the disposal schemes proposed, and point out areas of research and development meriting first attention; the committee is to serve as continuing adviser on the geological and geophysical aspects of disposal and the research and development program. The Committee with the cooperation of the Johns Hopkins University organized a conference at Princeton in September 1955. After the Princeton Conference members of the committee inspected disposal installations and made individual studies. Two years consideration of the disposal problems leads to-certain general conclusions. Wastes may be disposed of safely at many sites in the United States but, conversely, there are many large areas in which it is unlikely that disposal sites can be found, for example, the Atlantic Seaboard. Disposal in cavities mined in salt beds and salt domes is suggested as the possibility promising the most practical immediate solution of the problem. In the future the injection of large volumes of dilute liquid waste into porous rock strata at depths in excess of 5,000 feet may become feasible but means of rendering, the waste solutions compatible with the mineral and fluid components of the rock must first be developed. The main difficulties, to the injection method recognized at present are to prevent clogging of pore space as the solutions are pumped into the rock and the prediction or control of the rate and direction of movement.

  16. Disposal of medical waste: a legal perspective.

    Science.gov (United States)

    Du Toit, Karen; Bodenstein, Johannes

    2013-09-03

    The Constitution of the Republic of South Africa provides that everyone has the right to an environment that is not harmful to their health and well-being. The illegal dumping of hazardous waste poses a danger to the environment when pollutants migrate into water sources and ultimately cause widespread infection or toxicity, endangering the health of humans who might become exposed to infection and toxins. To give effect to the Constitution, the safe disposal of hazardous waste is governed by legislation in South Africa. Reports of the illegal disposal of waste suggest a general lack of awareness and training in regard to the safe disposal of medical waste. 

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

    International Nuclear Information System (INIS)

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

  18. Superfund Record of Decision (EPA Region 2): Woodland Township Route 72 site, Burlington County, New Jersey (first remedial action), May 16, 1990

    International Nuclear Information System (INIS)

    The 12-acre Woodland Route 72 Dump site is an abandoned hazardous waste dump in Woodland Township, Burlington County, New Jersey. The site is being remediated concurrently with another abandoned dump. Several chemical manufacturing firms dumped chemicals and other wastes into trenches and lagoons or burned the waste at the sites from the early 1950s to 1962. The primary contaminants of concern affecting the surface soil, sediment, sludge, debris, and ground water are VOCs including benzene, toluene, TCE and xylenes; organics including PAHs, pesticides, and phenols; radionuclides (e.g., uranium and thorium series); and metals including lead and chromium. The selected remedial action for the site includes excavation, further characterization, and offsite disposal at a permitted facility of 54,000 cubic yards (total from both sites) of contaminated surface soil, sludges, debris and sediment; offsite disposal of 19 cubic yards (total from both sites) of radiologically contaminated surface materials including a drum of radioactive pellets; ground water pumping and treatment with treatment to be determined during design. The total estimated present worth cost for the concurrent remedial actions at the Route 72 and Route 532 sites is $142,200,000

  19. Spent fuel characteristics & disposal considerations

    Energy Technology Data Exchange (ETDEWEB)

    Oversby, V.M.

    1996-06-01

    The fuel used in commercial nuclear power reactors is uranium, generally in the form of an oxide. The gas-cooled reactors developed in England use metallic uranium enclosed in a thin layer of Magnox. Since this fuel must be processed into a more stable form before disposal, we will not consider the characteristics of the Magnox spent fuel. The vast majority of the remaining power reactors in the world use uranium dioxide pellets in Zircaloy cladding as the fuel material. Reactors that are fueled with uranium dioxide generally use water as the moderator. If ordinary water is used, the reactors are called Light Water Reactors (LWR), while if water enriched in the deuterium isotope of hydrogen is used, the reactors are called Heavy Water reactors. The LWRs can be either pressurized reactors (PWR) or boiling water reactors (BWR). Both of these reactor types use uranium that has been enriched in the 235 isotope to about 3.5 to 4% total abundance. There may be minor differences in the details of the spent fuel characteristics for PWRs and BWRs, but for simplicity we will not consider these second-order effects. The Canadian designed reactor (CANDU) that is moderated by heavy water uses natural uranium without enrichment of the 235 isotope as the fuel. These reactors run at higher linear power density than LWRs and produce spent fuel with lower total burn-up than LWRs. Where these difference are important with respect to spent fuel management, we will discuss them. Otherwise, we will concentrate on spent fuel from LWRs.

  20. Toward Hazardless Waste: A Guide for Safe Use and Disposal of Hazardous Household Products.

    Science.gov (United States)

    Toteff, Sally; Zehner, Cheri

    This guide is designed to help individuals make responsible decisions about safe use and disposal of household products. It consists of eight sections dealing with: (1) hazardous chemicals in the home, how hazaradous products become hazardous waste, and whether a hazardous waste problem exists in Puget Sound; (2) which household wastes are…

  1. Waste disposal options report. Volume 2

    International Nuclear Information System (INIS)

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

  2. Waste disposal options report. Volume 2

    Energy Technology Data Exchange (ETDEWEB)

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

    1998-02-01

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

  3. Timing of High-level Waste Disposal

    International Nuclear Information System (INIS)

    This study identifies key factors influencing the timing of high-level waste (HLW) disposal and examines how social acceptability, technical soundness, environmental responsibility and economic feasibility impact on national strategies for HLW management and disposal. Based on case study analyses, it also presents the strategic approaches adopted in a number of national policies to address public concerns and civil society requirements regarding long-term stewardship of high-level radioactive waste. The findings and conclusions of the study confirm the importance of informing all stakeholders and involving them in the decision-making process in order to implement HLW disposal strategies successfully. This study will be of considerable interest to nuclear energy policy makers and analysts as well as to experts in the area of radioactive waste management and disposal. (author)

  4. Design of the disposal facility 2012

    International Nuclear Information System (INIS)

    The spent nuclear fuel accumulated from the nuclear power plants in Olkiluoto in Eurajoki and in Haestholmen in Loviisa will be disposed of in Olkiluoto. A facility complex will be constructed at Olkiluoto, and it will include two nuclear waste facilities according to Government Degree 736/2008. The nuclear waste facilities are an encapsulation plant, constructed to encapsulate spent nuclear fuel and a disposal facility consisting of an underground repository and other underground rooms and above ground service spaces. The repository is planned to be excavated to a depth of 400 - 450 meters. Access routes to the disposal facility are an inclined access tunnel and vertical shafts. The encapsulated fuel is transferred to the disposal facility in the canister lift. The canisters are transferred from the technical rooms to the disposal area via central tunnel and deposited in the deposition holes which are bored in the floors of the deposition tunnels and are lined beforehand with compacted bentonite blocks. Two parallel central tunnels connect all the deposition tunnels and these central tunnels are inter-connected at regular intervals. The solution improves the fire safety of the underground rooms and allows flexible backfilling and closing of the deposition tunnels in stages during the operational phase of the repository. An underground rock characterization facility, ONKALO, is excavated at the disposal level. ONKALO is designed and constructed so that it can later serve as part of the repository. The goal is that the first part of the disposal facility will be constructed under the building permit phase in the 2010's and operations will start in the 2020's. The fuel from 4 operating reactors as well the fuel from the fifth nuclear power plant under construction, has been taken into account in designing the disposal facility. According to the information from TVO and Fortum, the amount of the spent nuclear fuel is 5,440 tU. The disposal facility is being excavated

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

    International Nuclear Information System (INIS)

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

  6. UNWANTED AGRICULTURAL PESTICIDES: STATE DISPOSAL SYSTEMS

    OpenAIRE

    Centner, Terence J.

    1997-01-01

    Millions of pounds of unwanted pesticides have accumulated in barns throughout our country. The potential environmental and health risks posed by this situation has garnered public attention and governmental action. The federal government has revised its Universal Waste Rule so that it is easier to dispose of unwanted pesticides rather than simply banned pesticides. Nearly every state has initiated efforts to collect and dispose of accumulated pesticides in a safe manner. While the possession...

  7. Ecological Risk Assessment of Jarosite Waste Disposal

    OpenAIRE

    Kerolli-Mustafa, Mihone; Ćurković, Lidija; Fajković, Hana; Rončević, Sanda

    2015-01-01

    Jarosite waste, originating from zinc extraction industry, is considered hazardous due to the presence and the mobility of toxic metals that it contains. Its worldwide disposal in many tailing damps has become a major ecological concern. Three different methods, namely modified Synthetic Precipitation Leaching Procedure (SPLP), three-stage BCR sequential extraction procedure and Potential Ecological Risk Index (PERI) Method were used to access the ecological risk of jarosite waste disposal in...

  8. Radioactive waste storage and disposal: the challenge

    International Nuclear Information System (INIS)

    Solutions to waste management problems are available. After radium is removed, tailings from uranium ores can be disposed of safely in well-designed retention areas. Work is being done on the processing of non-fuel reactor wastes through incineration, reverse osmosis, and evaporation. Spent fuels have been stored safely for years in pools; dry storage in concrete cannisters is being investigated. Ultimate disposal of high-level wastes will be in deep, stable geologic formations. (LL)

  9. Hotel to Phase out Disposable Articles

    Institute of Scientific and Technical Information of China (English)

    2002-01-01

    Several hotels in Changsha, Shanghai and Kunming have recently staged a Green Hotel campaign: hotels will not offer disposable toothbrushes, toothpaste, slippers, combs or bottled shampoo and body lotion to their guests unless requested. Meanwhile a Green Hotel Standard has been issued, proscribing "disposable articles, such as toothbrushes, soap, combs and slippers," and stipulating that "textiles, such as bathrobes, towels and pillowslips, in hotel rooms are to be changed strictly at the request of guests,

  10. US charts plans for nuclear waste disposal

    International Nuclear Information System (INIS)

    The Nuclear Waste Policy Act (NWPA) passed in 1982 defines long-term federal programs to dispose of the leftovers from nuclear power generation. A succession of interacting multiple barriers, both natural and man-made, is to protect the public. Inside a mined underground repository will go waste packages. The geological formations surrounding the repository will be the final barrier. The article discussed site selections, salt sites, and subseabed disposal. (DP)

  11. Waste disposal technologies: designs and evaluations

    International Nuclear Information System (INIS)

    Many states and compacts are presently in the throes of considering what technology to select for their low level waste disposal site. Both the technical and economic aspects of disposal technology are important considerations in these decisions. It is also important that they be considered in the context of the entire system. In the case of a nuclear power plant, that system encompasses the various individual waste streams that contain radioactivity, the processing equipment which reduces the volume and/or alters the form in which the radioisotopes are contained, the packaging of the processed wastes in shipment, and finally its disposal. One further part of this is the monitoring that takes place in all stages of this operation. This paper discusses the results of some research that has been sponsored by EPRI with the principal contractor being Rogers and Associates Engineering Corporation. Included is a description of the distinguishing features found in disposal technologies developed in a generic framework, designs for a selected set of these disposal technologies and the costs which have been derived from these designs. In addition, a description of the early efforts towards defining the performance of these various disposal technologies is described. 5 figures, 1 table

  12. Disposal facility data for the interim performance

    International Nuclear Information System (INIS)

    The purpose of this report is to identify and provide information on the waste package and disposal facility concepts to be used for the low-level waste tank interim performance assessment. Current concepts for the low-level waste form, canister, and the disposal facility will be used for the interim performance assessment. The concept for the waste form consists of vitrified glass cullet in a sulfur polymer cement matrix material. The waste form will be contained in a 2 x 2 x 8 meter carbon steel container. Two disposal facility concepts will be used for the interim performance assessment. These facility concepts are based on a preliminary disposal facility concept developed for estimating costs for a disposal options configuration study. These disposal concepts are based on vault type structures. None of the concepts given in this report have been approved by a Tank Waste Remediation Systems (TWRS) decision board. These concepts will only be used in th interim performance assessment. Future performance assessments will be based on approved designs

  13. Radioactive waste disposal in the United Kingdom

    International Nuclear Information System (INIS)

    Currently the policy of the United Kingdom Government is that HLW should be stored in a suitable facility for at least fifty years before considering further storage or final disposal. This period allows many short-lived radionuclides, but more importantly, the associated radioactive decay heat, to diminish ahead of disposal. For intermediate-level solid wastes current policy is to develop, as soon as possible, a suitable deep geological facility for its permanent disposal. LLW constitutes the majority by volume of all radioactive waste. The waste arises not only from the nuclear industry, but also from all users of radioactive substances, such as hospitals, research establishments and industry. At present, it is mainly disposed of at a 300-acre site at Drigg in Cumbria, operated by British Nuclear Fuels plc (BNEL). It is packed into containers and placed in concrete-lined trenches which are subsequently sealed. Drigg is expected to continue to take solid low-level wastes for many years. Original plans-term disposal route for LLW involved disposal in a new near-surface repository. However, in 1987, this proposal was abandoned, on cost-benefit arguments, and the Government agreed that a yet to be developed national deep repository should also be used for some LLW. Drigg is expected to continue to take solid low-level wastes for many years.

  14. Aquatic assessment of the Pike Hill Copper Mine Superfund site, Corinth, Vermont

    Science.gov (United States)

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

    2013-01-01

    The Pike Hill Copper Mine Superfund site in Corinth, Orange County, Vermont, includes the Eureka, Union, and Smith mines along with areas of downstream aquatic ecosystem impairment. The site was placed on the U.S. Environmental Protection Agency (USEPA) National Priorities List in 2004. The mines, which operated from about 1847 to 1919, contain underground workings, foundations from historical structures, several waste-rock piles, and some flotation tailings. The mine site is drained to the northeast by Pike Hill Brook, which includes several wetland areas, and to the southeast by an unnamed tributary that flows to the south and enters Cookville Brook. Both brooks eventually drain into the Waits River, which flows into the Connecticut River. The aquatic ecosystem at the site was assessed using a variety of approaches that investigated surface-water quality, sediment quality, and various ecological indicators of stream-ecosystem health. The degradation of surface-water quality is caused by elevated concentrations of copper, and to a lesser extent cadmium, with localized effects caused by aluminum, iron, and zinc. Copper concentrations in surface waters reached or exceeded the USEPA national recommended chronic water-quality criteria for the protection of aquatic life in all of the Pike Hill Brook sampling locations except for the location farthest downstream, in half of the locations sampled in the tributary to Cookville Brook, and in about half of the locations in one wetland area located in Pike Hill Brook. Most of these same locations also contained concentrations of cadmium that exceeded the chronic water-quality criteria. In contrast, surface waters at background sampling locations were below these criteria for copper and cadmium. Comparison of hardness-based and Biotic Ligand Model (BLM)-based criteria for copper yields similar results with respect to the extent or number of stations impaired for surface waters in the affected area. However, the BLM

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

    Science.gov (United States)

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

    2006-01-01

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

  16. Degradation Of Cementitious Materials Associated With Saltstone Disposal Units

    Energy Technology Data Exchange (ETDEWEB)

    Flach, G. P; Smith, F. G. III

    2013-03-19

    The Saltstone facilities at the DOE Savannah River Site (SRS) stabilize and dispose of low-level radioactive salt solution originating from liquid waste storage tanks at the site. The Saltstone Production Facility (SPF) receives treated salt solution and mixes the aqueous waste with dry cement, blast furnace slag, and fly ash to form a grout slurry which is mechanically pumped into concrete disposal cells that compose the Saltstone Disposal Facility (SDF). The solidified grout is termed “saltstone”. Cementitious materials play a prominent role in the design and long-term performance of the SDF. The saltstone grout exhibits low permeability and diffusivity, and thus represents a physical barrier to waste release. The waste form is also reducing, which creates a chemical barrier to waste release for certain key radionuclides, notably Tc-99. Similarly, the concrete shell of an SDF disposal unit (SDU) represents an additional physical and chemical barrier to radionuclide release to the environment. Together the waste form and the SDU compose a robust containment structure at the time of facility closure. However, the physical and chemical state of cementitious materials will evolve over time through a variety of phenomena, leading to degraded barrier performance over Performance Assessment (PA) timescales of thousands to tens of thousands of years. Previous studies of cementitious material degradation in the context of low-level waste disposal have identified sulfate attack, carbonation influenced steel corrosion, and decalcification (primary constituent leaching) as the primary chemical degradation phenomena of most relevance to SRS exposure conditions. In this study, degradation time scales for each of these three degradation phenomena are estimated for saltstone and concrete associated with each SDU type under conservative, nominal, and best estimate assumptions. The nominal value (NV) is an intermediate result that is more probable than the conservative

  17. Subseabed Disposal Program Plan. Volume I. Overview

    International Nuclear Information System (INIS)

    The primary objective of the Subseabed Disposal Program (SDP) is to assess the scientific, environmental, and engineering feasibility of disposing of processed and packaged high-level nuclear waste in geologic formations beneath the world's oceans. High-level waste (HLW) is considered the most difficult of radioactive wastes to dispose of in oceanic geologic formations because of its heat and radiation output. From a scientific standpoint, the understanding developed for the disposal of such HLW can be used for other nuclear wastes (e.g., transuranic - TRU - or low-level) and materials from decommissioned facilities, since any set of barriers competent to contain the heat and radiation outputs of high-level waste will also contain such outputs from low-level waste. If subseabed disposal is found to be feasible for HLW, then other factors such as cost will become more important in considering subseabed emplacement for other nuclear wastes. A secondary objective of the SDP is to develop and maintain a capability to assess and cooperate with the seabed nuclear waste disposal programs of other nations. There are, of course, a number of nations with nuclear programs, and not all of these nations have convenient access to land-based repositories for nuclear waste. Many are attempting to develop legislative and scientific programs that will avoid potential hazards to man, threats to other ocean uses, and marine pollution, and they work together to such purpose in meetings of the international NEA/Seabed Working Group. The US SDP, as the first and most highly developed R and D program in the area, strongly influences the development of subseabed-disposal-related policy in such nations

  18. Subseabed Disposal Program Plan. Volume I. Overview

    Energy Technology Data Exchange (ETDEWEB)

    None

    1981-07-01

    The primary objective of the Subseabed Disposal Program (SDP) is to assess the scientific, environmental, and engineering feasibility of disposing of processed and packaged high-level nuclear waste in geologic formations beneath the world's oceans. High-level waste (HLW) is considered the most difficult of radioactive wastes to dispose of in oceanic geologic formations because of its heat and radiation output. From a scientific standpoint, the understanding developed for the disposal of such HLW can be used for other nuclear wastes (e.g., transuranic - TRU - or low-level) and materials from decommissioned facilities, since any set of barriers competent to contain the heat and radiation outputs of high-level waste will also contain such outputs from low-level waste. If subseabed disposal is found to be feasible for HLW, then other factors such as cost will become more important in considering subseabed emplacement for other nuclear wastes. A secondary objective of the SDP is to develop and maintain a capability to assess and cooperate with the seabed nuclear waste disposal programs of other nations. There are, of course, a number of nations with nuclear programs, and not all of these nations have convenient access to land-based repositories for nuclear waste. Many are attempting to develop legislative and scientific programs that will avoid potential hazards to man, threats to other ocean uses, and marine pollution, and they work together to such purpose in meetings of the international NEA/Seabed Working Group. The US SDP, as the first and most highly developed R and D program in the area, strongly influences the development of subseabed-disposal-related policy in such nations.

  19. Passive in-situ chemical sensor

    Science.gov (United States)

    Morrell, Jonathan S.; Ripley, Edward B.

    2012-02-14

    A chemical sensor for assessing a chemical of interest. In typical embodiments the chemical sensor includes a first thermocouple and second thermocouple. A reactive component is typically disposed proximal to the second thermal couple, and is selected to react with the chemical of interest and generate a temperature variation that may be detected by a comparison of a temperature sensed by the second thermocouple compared with a concurrent temperature detected by the first thermocouple. Further disclosed is a method for assessing a chemical of interest and a method for identifying a reaction temperature for a chemical of interest in a system.

  20. 36 CFR 228.57 - Types of disposal.

    Science.gov (United States)

    2010-07-01

    ... 36 Parks, Forests, and Public Property 2 2010-07-01 2010-07-01 false Types of disposal. 228.57... Disposal of Mineral Materials Types and Methods of Disposal § 228.57 Types of disposal. Except as provided... qualified bidder after formal advertising and other appropriate public notice; (b) Sale by...

  1. Influence of a chlor-alkali superfund site on mercury bioaccumulation in periphyton and low-trophic level fauna

    Science.gov (United States)

    Buckman, Kate L.; Marvin-DiPasquale, Mark C.; Taylor, Vivien F.; Chalmers, Ann T.; Broadley, Hannah J.; Agee, Jennifer L.; Jackson, Brian P.; Chen, Celia Y.

    2015-01-01

    In Berlin, New Hampshire, USA, the Androscoggin River flows adjacent to a former chlor-alkali facility that is a US Environmental Protection Agency Superfund site and source of mercury (Hg) to the river. The present study was conducted to determine the fate and bioaccumulation of methylmercury (MeHg) to lower trophic-level taxa in the river. Surface sediment directly adjacent to the source showed significantly elevated MeHg (10–40× increase, mean ± standard deviation [SD]: 20.1 ± 24.8 ng g–1 dry wt) and total mercury (THg; 10–30× increase, mean ± SD: 2045 ± 2669 ng g–1 dry wt) compared with all other reaches, with sediment THg and MeHg from downstream reaches elevated (3–7× on average) relative to the reference (THg mean ± SD: 33.5 ± 9.33 ng g–1 dry wt; MeHg mean ± SD: 0.52 ± 0.21 ng g–1 dry wt). Water column THg concentrations adjacent to the point source for both particulate (0.23 ng L–1) and dissolved (0.76 ng L–1) fractions were 5-fold higher than at the reference sites, and 2-fold to 5-fold higher than downstream. Methylmercury production potential of periphyton material was highest (2–9 ng g–1 d–1 dry wt) adjacent to the Superfund site; other reaches were close to or below reporting limits (0. 1 ng g–1 d–1 dry wt). Total Hg and MeHg bioaccumulation in fauna was variable across sites and taxa, with no clear spatial patterns downstream of the contamination source. Crayfish, mayflies, and shiners showed a weak positive relationship with porewater MeHg concentration.

  2. History of geological disposal concept (3). Implementation phase of geological disposal (2000 upward)

    International Nuclear Information System (INIS)

    Important standards and concept about geological disposal have been arranged as an international common base and are being generalized. The authors overview the concept of geological disposal, and would like this paper to help arouse broad discussions for promoting the implementation plan of geological disposal projects in the future. In recent years, the scientific and technological rationality of geological disposal has been recognized internationally. With the addition of discussions from social viewpoints such as ethics, economy, etc., geological disposal projects are in the stage of starting after establishment of social consensus. As an international common base, the following consolidated and systematized items have been presented as indispensable elements in promoting business projects: (1) step-by-step approach, (2) safety case, (3) reversibility and recovery potential, and (4) trust building and communications. This paper outlines the contents of the following cases, where international common base was reflected on the geological disposal projects in Japan: (1) final disposal method and safety regulations, and (2) impact of the Great East Japan Earthquake and Fukushima Daiichi Nuclear Power Station accident on geological disposal plan. (A.O.)

  3. Chemical treatment of radioactive wastes

    International Nuclear Information System (INIS)

    This is the third manual of three commissioned by the IAEA on the three principal techniques used in concentrating radioactive liquid wastes, namely chemical precipitation, evaporation and ion exchange. The present manual deals with chemical precipitation by coagulation-flocculation and sedimentation, commonly called ''chemical treatment'' of low-activity wastes. Topics discussed in the manual are: (i) principles of coagulation on flocculation and sedimentation and associated processes; (ii) process and equipment; (iii) conditioning and disposal of flocculation sludge; (iv) sampling and the equipment required for experiments; and (v) factors governing the selection of processes. 99 refs, 17 figs, 4 tabs

  4. Waste disposal aspects of actinide separation

    International Nuclear Information System (INIS)

    Two recent NRPB reports are summarized (Camplin, W.C., Grimwood, P.D. and White, I.F., The effects of actinide separation on the radiological consequences of disposal of high-level radioactive waste on the ocean bed, Harwell, National Radiological Protection Board, NRPB-R94 (1980), London, HMSO; Hill, M.D., White, I.F. and Fleishman, A.B., The effects of actinide separation on the radiological consequences of geologic disposal of high-level waste. Harwell, National Radiological Protection Board, NRPB-R95 (1980), London, HMSO). They describe preliminary environmental assessments relevant to waste arising from the reprocessing of PWR fuel. Details are given of the modelling of transport of radionuclides to man, and of the methodology for calculating effective dose equivalents in man. Emphasis has been placed on the interaction between actinide separation and the disposal options rather than comparison of disposal options. The reports show that the effects of actinide separation do depend on the disposal method. Conditions are outlined where the required substantial further research and development work on actinide separation and recycle would be justified. Toxicity indices or 'toxic potentials' can be misleading and should not be used to guide research and development. (U.K.)

  5. Operational technology for greater confinement disposal

    International Nuclear Information System (INIS)

    Procedures and methods for the design and operation of a greater confinement disposal facility using large-diameter boreholes are discussed. It is assumed that the facility would be located at an operating low-level waste disposal site and that only a small portion of the wastes received at the site would require greater confinement disposal. The document is organized into sections addressing: facility planning process; facility construction; waste loading and handling; radiological safety planning; operations procedures; and engineering cost studies. While primarily written for low-level waste management site operators and managers, a detailed economic assessment section is included that should assist planners in performing cost analyses. Economic assessments for both commercial and US government greater confinement disposal facilities are included. The estimated disposal costs range from $27 to $104 per cubic foot for a commercial facility and from $17 to $60 per cubic foot for a government facility. These costs are based on average site preparation, construction, and waste loading costs for both contact- and remote-handled wastes. 14 figures, 22 tables

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

    International Nuclear Information System (INIS)

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

  7. The disposal of Canada's nuclear fuel waste: site screening and site evaluation technology

    International Nuclear Information System (INIS)

    carefully characterized to understand the groundwater flow conditions in the rock. This understanding would be used to situate the disposal vault in the rock so as to allow the flow and chemical characteristics of the groundwater to enhance the safety of the disposal system. The geoscience methods for characterizing the conditions within plutonic rocks of the Canadian Shield have been developed and tested by AECL at geologic research areas on the Shield. This report presents examples of the site characterization methods which are drawn from the studies at these research areas. The geoscience work performed at the Whiteshell Research Area (WRA) on the Shield in southeastern Manitoba comes closest to illustrating the spatial coverage of characterization that would be required for siting an actual nuclear fuel waste disposal vault in a candidate area of the Shield. The characterization work done at the site of the Underground Research Laboratory (URL) in the WRA demonstrates how to evaluate the geoscience conditions of the rock at a candidate disposal site, and illustrates how that information would be used to confirm the suitability of the site for disposal. This report presents evidence from case studies at the URL and the geologic research areas that the surface-based, borehole and underground site characterization methods developed by AECL are now sufficiently developed that they can be used to obtain the geoscience information needed for siting a disposal vault in plutonic rock of the Canadian Shield. We expect that these site characterization methods will continue to be improved and that new methods will be developed during the long time period required for implementation of the disposal project. Improvements and new developments are continuing through ongoing research at the site of the URL and at the other geologic research areas on the Shield. However the methods that are currently available are sufficiently well developed to allow siting to commence. (author)

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

    Energy Technology Data Exchange (ETDEWEB)

    Romano, Stephen; Welling, Steven; Bell, Simon

    2003-02-27

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

  9. Selected remedy at the Queen City Farms superfund site: A risk management approach

    International Nuclear Information System (INIS)

    A risk management approach at a former industrial waste disposal site in western Washington resulted in a selected remedy that is cost-effective and that meets the CERCLA threshold criterion of protecting human health and the environment. The proposed remedy, which addresses contamination in soil and groundwater, does not require an ARARs waiver and received state and community acceptance. By analyzing the current and potential risk at the site, a proposed remedy was chosen that would control the source and naturally attenuate the groundwater plume. Source control will include removal and treatment of some light nonaqueous phase liquid (LNAPL) and some soil, followed by isolation of the remaining soil and LNAPL within a slurry wall and beneath a multilayer cap. A contingent groundwater extraction and treatment system was included to address uncertainty in the risk characterization. Implementing source control is predicted to result in a steady decline in volatile organic compound levels in the drinking water aquifer through adsorption, degradation, and dispersion. Exposure to groundwater during the period of natural attenuation will be controlled by monitoring, institutional controls, and a thorough characterization of the plume and receptors. 7 figs., 1 tab

  10. Overview of low-level radioactive waste disposal facilities subsidence

    International Nuclear Information System (INIS)

    The result of a case study of the Sheffield, Illinois, waste disposal facility, and literature reviews on problems at waste disposal facilities are presented. The types of problems, causes of the problems, and approaches to mitigate the problems are evaluated. The problems identified were surface subsidence, surface erosion, leachate and gas. Leachate resulted from water entry into trenches where subsidence occurred. Subsidence was attributed to random placement of waste containers into trenches leaving voids. The poorly compacted cover soil initially bridged the voids and subsequently collapsed and siphoned into the voids. Surface potholes and slumps resulted. Extensive potholding occurred during and after precipitation when the Sheffield loess soil piped into the voids. Long-term soil consolidation also resulted in area settlement. Potholes and slumps along the tops of walls between trenches constructed of fill were attributed to collapse of the walls into voids. Long-term subsidence was predicted as waste containers degraded and collapsed causing further slumps and potholes over a 50-year period. Excessive surface erosion resulted from poor vegetation cover and inadequacy of drainage controls. Approaches evaluated to stabilize disposal site trenches by compaction included dynamic consolidation, pile driving, surface surcharging, and surface compaction. Stabilization and leachate control by solidification with compaction grouting and chemical grouting were deemed effective but expensive. Accelerated degradation of the wastes by aerobic decomposition of organics and in-situ incineration were found to be less effective. Impervious trench caps were analyzed as a final moisture infiltration and leachate control method after stabilization was achieved. Recommendations for long-term trench maintenance were developed

  11. Radium and Other Radiological Chemicals: Drinking Water Treatment Strategies

    Science.gov (United States)

    Radium and Other Radiological Chemicals: Drinking Water Treatment Technologies Topics include: Introduction to Rad Chemistry, Summary of the Rad, Regulations Treatment Technology, and Disposal. The introductions cover atoms, ions, radium and uranium and the removal of radioac...

  12. Waste Water Disposal Design And Management III

    International Nuclear Information System (INIS)

    This book gives descriptions of underlying chemistry, chemical conditioning, facilities, sterilization and special water treatment. It includes chemical combination and a chemical equation, molarity, normality, application of normality, chemical evaluation and law of mass action. It deals with chemical conditioning for design and management of waste water treatment.

  13. Environmental assistance for tailings disposal

    Energy Technology Data Exchange (ETDEWEB)

    Boswell, J.E.S.; Sobkowicz, J.C. [Thurber Engineering, Calgary, AB (Canada)

    2010-07-01

    Increasing solids content and reducing water content prior to deposition has become increasingly important in the development of tailings management. In the treatment of fine tailings, traditional dewatering methods such as thickening, flocculation and centrifugation employed to reduce water content and improve consolidation behaviour, have fallen short of final requirements. A new role has been found for the continued and optimal use of environmental methods especially in improving dewatering of tailings deposits. This paper described the salient environmental techniques and benefits in the management of tailings and discussed the quantification of the improvement required in target solids contents and shear strengths for certain oil sands tailings materials. Specifically, the paper discussed environmental methods of dewatering oil sands tailings, with particular reference to solar evaporation; evaporative desiccation; freeze thaw; and biological methods. A geotechnical perspective on dewatering tailings was also presented. Two issues were addressed from this perspective, notably the desirable end-points in terms of solids content and strength for various tailings products; and the improvements in strength that could be obtained by environmental effects during thin-lift deposition. It was concluded that in the medium term, electro-mechanical or chemical methods may prove successful in dewatering and consolidating oil sands tailings. However, in the longer term, environmental methods will continue to be pursued and employed, in the drive to reduce the cost of tailings placement and reclamation. 12 refs., 4 figs.

  14. Cements in Radioactive Waste Disposal

    International Nuclear Information System (INIS)

    The use of cement and concrete to immobilise radioactive waste is complicated by the wide- ranging nature of inorganic cementing agents available as well as the range of service environments in which cement is used and the different functions expected of cement. For example, Portland cement based concretes are widely used as structural materials for construction of vaults and tunnels. These constructions may experience a long pre-closure performance lifetime during which they are required to protect against collapse and ingress of water: strength and impermeability are key desirable characteristics. On the other hand, cement and concrete may be used to form backfills, ranging in permeability. Permeable formulations allow gas readily to escape, while impermeable barriers retard radionuclide transport and reduce access of ground water to the waste. A key feature of cements is that, while fresh, they pass through a fluid phase and can be formed into any shape desired or used to infiltrate other materials thereby enclosing them into a sealed matrix. Thereafter, setting and hardening is automatic and irreversible. Where concrete is used to form structural elements, it is also natural to use cement in other applications as it minimises potential for materials incompatibility. Thus cement- mainly Portland cement- has been widely used as an encapsulant for storage, transport and as a radiation shield for active wastes. Also, to form and stabilise structures such as vaults and silos. Relative to other potential matrices, cement also has a chemical immobilisation potential, reacting with and binding with many radionuclides. The chemical potential of cements is essentially sacrificial, thus limiting their performance lifetime. However performance may also be required in the civil engineering sense, where strength is important, so many factors, including a geochemical description of service conditions, may require to be assessed in order to predict performance lifetime. The

  15. Public values associated with nuclear waste disposal

    International Nuclear Information System (INIS)

    This report presents the major findings from a study designed to assess public attitudes and values associated with nuclear waste disposal. The first objective was to obtain from selected individuals and organizations value and attitude information which would be useful to decision-makers charged with deciding the ultimate disposal of radioactive waste materials. A second research objective was to obtain information that could be structured and quantified for integration with technical data in a computer-assisted decision model. The third general objective of this research was to test several attitude-value measurement procedures for their relevance and applicability to nuclear waste disposal. The results presented in this report are based on questionnaire responses from 465 study participants

  16. Design, Manufacturing, and Performance estimation of a Disposal Canister for the Ceramic Waste from Pyroprocessing

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Min Soo; Choi, Heui Joo; Lee, Jong Youl; Choi, Jong Won [Korea Atomic Energy Institute, Daejeon (Korea, Republic of)

    2012-09-15

    A pyroprocess is currently being developed by KAERI to cope with a highly accumulated spent nuclear fuel in Korea. The pyroprocess produces a certain amount of high-level radioactive waste (HLW), which is solidified by a ceramic binder. The produced ceramic waste will be confined in a secure disposal canister and then placed in a deep geologic formation so as not to contaminate human environment. In this paper, the development of a disposal canister was overviewed by discussing mainly its design premises, constitution, manufacturing methods, corrosion resistance in a deep geologic environment, radiation shielding, and structural stability. The disposal canister should be safe from thermal, chemical, mechanical, and biological invasions for a very long time so as not to release any kind of radionuclides.

  17. Design, Manufacturing, and Performance estimation of a Disposal Canister for the Ceramic Waste from Pyroprocessing

    International Nuclear Information System (INIS)

    A pyroprocess is currently being developed by KAERI to cope with a highly accumulated spent nuclear fuel in Korea. The pyroprocess produces a certain amount of high-level radioactive waste (HLW), which is solidified by a ceramic binder. The produced ceramic waste will be confined in a secure disposal canister and then placed in a deep geologic formation so as not to contaminate human environment. In this paper, the development of a disposal canister was overviewed by discussing mainly its design premises, constitution, manufacturing methods, corrosion resistance in a deep geologic environment, radiation shielding, and structural stability. The disposal canister should be safe from thermal, chemical, mechanical, and biological invasions for a very long time so as not to release any kind of radionuclides.

  18. Challenges in spent nuclear fuel final disposal:conceptual design models

    Institute of Scientific and Technical Information of China (English)

    Mukhtar Ahmed RANA

    2008-01-01

    The disposal of spent nuclear fuel is a long-standing issue in nuclear technology. Mainly, UO2 and metallic U are used as a fuel in nuclear reactors. Spent nuclear fuel contains fission products and transuranium elements, which would remain radioactive for 104 to 108 years. In this brief communication, essential concepts and engineering elements related to high-level nuclear waste disposal are described. Conceptual design models are described and discussed considering the long-time scale activity of spent nuclear fuel or high level waste. Notions of physical and chemical barriers to contain nuclear waste are highlightened. Concerns regarding integrity, self-irradiation induced decomposition and thermal effects of decay heat on the spent nuclear fuel are also discussed. The question of retrievability of spent nuclear fuel after disposal is considered.

  19. Potential for de-regulated disposal of very low level wastes from nuclear power plants

    International Nuclear Information System (INIS)

    The purpose of the study discussed in this paper was to review the characteristics of low level waste streams generated in commercial nuclear power facilities to determine which may be suitable for disposal by methods other than transfer to a facility licensed by the Nuclear Regulatory Commission (NRC) and to evaluate the benefits, risks, and costs of exempting such very low level wastes (VLW) from the disposal requirements of 10 CFR Part 61. Of course, wastes that no longer require regulation of their radiological properties are still subject to the regulatory controls - federal, state, or local - that affect non-radioactive wastes of similar chemical and physical properties and similar origins. This study addressed radiological aspects only, and assumed, in its evaluations, that the wastes can and will be disposed of in accordance with all other applicable requirements. 4 references, 1 figure, 6 tables

  20. Disposal of disused sealed sources in Belgium

    International Nuclear Information System (INIS)

    It is not foreseen by the Belgian operator to dispose radioactive sealed sources in Near Surface Disposal Facility. The adaptation of the generic safety assessment in order to take in account the presence of sealed sources has been made. The level of concern in the context of the long term safety of a near surface disposal is assessed. On the base of the Belgium exemption level and the extrapolation for the disused sources the range of values above which sources could be considered as to have a significant radiological impact is determined. The number of significant medical sources after 300 years is estimated to be 294. For long term safety after 300 years it is obtained the reduction by a factor 10 of the number of sources, when only three radionuclides 241Am, 137Cs and 226Ra should be taken into account for the long term safety (only α and γemitters). The Belgian Near Surface Disposal Concept is presented. Long Term Safety Assessment including assumptions, generic concept, classification, scenarios (Human intrusion scenario) is presented. It is concluded that high actives of long-lived radionuclides sources should be avoided in a near surface disposal facility regarding the human intrusion scenario. If sources are still foreseen, activity limits should be specified together with requirements on their management. Specific limits could be derived from safety or security scenario. Attempts to distribute other sources in each module of the disposal and to set out the monoliths containing sources away from the intruder possible access could be made. Stylised human intrusion scenarios including sources should be developed by discussions with the safety authority. Scenario addressing the Operational phase should include the presence of sources

  1. AFCI Storage & Disposal FY-06 Progress Report

    Energy Technology Data Exchange (ETDEWEB)

    Halsey, W G; Wigeland, R; Dixon, B

    2006-09-27

    AFCI Storage and Disposal participants at LLNL, ANL and INL provide assessment of how AFCI technology can optimize the future evolution of the fuel cycle, including optimization of waste management. Evaluation of material storage and repository disposal technical issues provides feedback on criteria and metrics for AFCI, and evaluation of AFCI waste streams provides technical alternatives for future repository optimization. LLNL coordinates this effort that includes repository analysis at ANL and incorporation of repository impacts into AFCI criteria at INL. Cooperative evaluation with YMP staff is pursued to provide a mutually agreed technical base. Cooperation with select international programs is supported.

  2. Environmental restoration waste materials co-disposal

    International Nuclear Information System (INIS)

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

  3. Radioactive waste disposal into the ground

    International Nuclear Information System (INIS)

    Disposal into ground has sometimes proved to be an expedient and simple method. Where ground disposal has become an established practice, the sites have so far been limited to those remote from population centres; but in other respects, such as in climate and soil conditions, their characteristics vary widely. Experience gained at these sites has illustrated the variety of problems in radioactive waste migration and the resulting pollution and environmental radiation levels that may reasonably be anticipated at other sites, whether remote from population centres or otherwise.

  4. Radioactive metals disposal and recycling impact modelling

    International Nuclear Information System (INIS)

    Screening life cycle assessment models developed to investigate hypothetical disposal and recycling options for the Windscale Advanced Gas-cooled Reactor heat exchangers were used to generate more complex models addressing the main UK radioactive metals inventory. Both studies show there are significant environmental advantages in the metals recycling promoted by the current low level waste disposal policies, strategies and plans. Financial benefits from current metals treatment options are supported and offer even greater benefits when applied to the UK radioactive metals inventory as a whole. (authors)

  5. Electrochemical apparatus comprising modified disposable rectangular cuvette

    Science.gov (United States)

    Dattelbaum, Andrew M; Gupta, Gautam; Morris, David E

    2013-09-10

    Electrochemical apparatus includes a disposable rectangular cuvette modified with at least one hole through a side and/or the bottom. Apparatus may include more than one cuvette, which in practice is a disposable rectangular glass or plastic cuvette modified by drilling the hole(s) through. The apparatus include two plates and some means of fastening one plate to the other. The apparatus may be interfaced with a fiber optic or microscope objective, and a spectrometer for spectroscopic studies. The apparatus are suitable for a variety of electrochemical experiments, including surface electrochemistry, bulk electrolysis, and flow cell experiments.

  6. Treatment and disposal of refinery sludges: Indian scenario.

    Science.gov (United States)

    Bhattacharyya, J K; Shekdar, A V

    2003-06-01

    Crude oil is a major source of energy and feedstock for petrochemicals. Oily sludge, bio-sludge and chemical sludge are the major sludges generated from the processes and effluent treatment plants of the refineries engaged in crude oil refining operations. Refineries in India generate about 28,220 tons of sludge per annum. Various types of pollutants like phenols, heavy metals, etc. are present in the sludges and they are treated as hazardous waste. Oily sludge, which is generated in much higher amount compared to other sludges, contains phenol (90-100 mg/kg), nickel (17-25 mg/kg), chromium (27-80 mg/kg), zinc (7-80 mg/kg), manganese (19-24 mg/kg), cadmium (0.8-2 mg/kg), copper (32-120 mg/kg) and lead (0.001-0.12 mg/ kg). Uncontrolled disposal practices of sludges in India cause degradation of environmental and depreciation of aesthetic quality. Environmental impact due to improper sludge management has also been identified. Salient features of various treatment and disposal practices have been discussed. Findings of a case study undertaken by the authors for Numaligarh Refinery in India have been presented. Various system alternatives have been identified for waste management in Numaligarh Refinery. A ranking exercise has been carried out to evaluate the alternatives and select the appropriate one. A detailed design of the selected waste management system has been presented. PMID:12870645

  7. The potential significance of microbial activity in radioactive waste disposal

    International Nuclear Information System (INIS)

    The aim of this report is to assess the potential significance of microbial activity in radioactive waste disposal. It outlines the major factors which need to be considered in order to evaluate the importance of microbiological action. These include water and nutritional sources (particularly carbon) hostile conditions (particularly the effects of radiation and pH), the establishment of pH micro-environments and the degradative effect of microbial metabolic by-products on the disposed waste forms. Before an active microbial population can develop there are certain basic requirements for life. These are outlined and the possibility of colonisation occurring within the chemical, radiological and nutritional constraints of a repository are considered. Once colonisation is assumed, the effect of microbial activity is discussed under five headings, i.e. (i) direct attack, (ii) physical disruption (which includes consideration of fissuring processes and void formation), (iii) gas generation (which may be of particular importance), (iv) radionuclide uptake and finally (v) alteration of groundwater chemistry. Particular attention is paid to the possibility of environments becoming established both within the waste form itself (allowing microbes to attack from the inside of the repository outward) or attack on the encapsulant materials (microbes attacking from the outside inward). (author)

  8. 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

  9. 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.

  10. Disposal of Radioactive Wastes. Vol. I. Proceedings of the Scientific Conference on the Disposal of Radioactive Wastes

    International Nuclear Information System (INIS)

    Almost every human activity creates some kind of waste. Whether it is harmful, inconvenient, neutral or even positively useful in some other activity depends largely on its nature, which can often be changed by some fairly simple chemical process so as to neutralize harmful wastes, render inconvenient wastes useful, and so on. Radioactive ''waste'' can be extremely harmful or useful, again depending on its form and the way it is handled; but its essential nature cannot be changed or destroyed by any means at present under the control of man. Furthermore, the harmful waste of today may well become the useful raw material of tomorrow. As more and more countries embark on programs of nuclear research and nuclear power, the quantities of radioactive material to be disposed of are rapidly increasing and the problems of safeguarding humanity on the one hand and of storing possibly useful material on the other are assuming great importance. It was for these reasons that the International Atomic Energy Agency and the United Nations Educational, Scientific and Cultural Organization combined their forces in sponsoring and organizing, with the co-operation of the Food and Agricultural Organization of the United Nations, a large scientific conference devoted to the subject of the disposal of radioactive wastes. The Conference was held from 16 to 21 November 1959 at the Oceanographic Museum in Monaco, in deference to the leading position of this institution in the field of oceanography, which is an extremely important discipline in relation to the disposal of wastes into the sea. A total of 283 scientists attended, representing 31 countries and 11 international organizations. It is with the consciousness of offering scientific information of great value to the future progress of an extremely important field of knowledge that I now commend these Proceedings to the earnest attention of all workers in that field

  11. Disposal of Radioactive Wastes. Vol. II. Proceedings of the Scientific Conference on the Disposal of Radioactive Wastes

    International Nuclear Information System (INIS)

    Almost every human activity creates some kind of waste. Whether it is harmful, inconvenient, neutral or even positively useful in some other activity depends largely on its nature, which can often be changed by some fairly simple chemical process so as to neutralize harmful wastes, render inconvenient wastes useful, and so on. Radioactive ''waste'' can be extremely harmful or useful, again depending on its form and the way it is handled; but its essential nature cannot be changed or destroyed by any means at present under the control of man. Furthermore, the harmful waste of today may well become the useful raw material of tomorrow. As more and more countries embark on programs of nuclear research and nuclear power, the quantities of radioactive material to be disposed of are rapidly increasing and the problems of safeguarding humanity on the one hand and of storing possibly useful material on the other are assuming great importance. It was for these reasons that the International Atomic Energy Agency and the United Nations Educational, Scientific and Cultural Organization combined their forces in sponsoring and organizing, with the co-operation of the Food and Agricultural Organization of the United Nations, a large scientific conference devoted to the subject of the disposal of radioactive wastes. The Conference was held from 16 to 21 November 1959 at the Oceanographic Museum in Monaco, in deference to the leading position of this institution in the field of oceanography, which is an extremely important discipline in relation to the disposal of wastes into the sea. A total of 283 scientists attended, representing 31 countries and 11 international organizations. It is with the consciousness of offering scientific information of great value to the future progress of an extremely important field of knowledge that I now commend these Proceedings to the earnest attention of all workers in that field

  12. CONTAINMENT OF LOW-LEVEL RADIOACTIVE WASTE AT THE DOE SALTSTONE DISPOSAL FACILITY

    Energy Technology Data Exchange (ETDEWEB)

    Jordan, J.; Flach, G.

    2012-03-29

    As facilities look for permanent storage of toxic materials, they are forced to address the long-term impacts to the environment as well as any individuals living in affected area. As these materials are stored underground, modeling of the contaminant transport through the ground is an essential part of the evaluation. The contaminant transport model must address the long-term degradation of the containment system as well as any movement of the contaminant through the soil and into the groundwater. In order for disposal facilities to meet their performance objectives, engineered and natural barriers are relied upon. Engineered barriers include things like the design of the disposal unit, while natural barriers include things like the depth of soil between the disposal unit and the water table. The Saltstone Disposal Facility (SDF) at the Savannah River Site (SRS) in South Carolina is an example of a waste disposal unit that must be evaluated over a timeframe of thousands of years. The engineered and natural barriers for the SDF allow it to meet its performance objective over the long time frame. Some waste disposal facilities are required to meet certain standards to ensure public safety. These type of facilities require an engineered containment system to ensure that these requirements are met. The Saltstone Disposal Facility (SDF) at the Savannah River Site (SRS) is an example of this type of facility. The facility is evaluated based on a groundwater pathway analysis which considers long-term changes to material properties due to physical and chemical degradation processes. The facility is able to meet these performance objectives due to the multiple engineered and natural barriers to contaminant migration.

  13. Evaluation of the Acceptability of Potential Depleted Uranium Hexafluoride Conversion Products at the Envirocare Disposal Site

    International Nuclear Information System (INIS)

    The purpose of this report is to review and document the capability of potential products of depleted UF6 conversion to meet the current waste acceptance criteria and other regulatory requirements for disposal at the facility in Clive, Utah, owned by Envirocare of Utah, Inc. The investigation was conducted by identifying issues potentially related to disposal of depleted uranium (DU) products at Envirocare and conducting an initial analysis of them. Discussions were then held with representatives of Envirocare, the state of Utah (which is a NRC Agreement State and, thus, is the cognizant regulatory authority for Envirocare), and DOE Oak Ridge Operations. Provisional issue resolution was then established based on the analysis and discussions and documented in a draft report. The draft report was then reviewed by those providing information and revisions were made, which resulted in this document. Issues that were examined for resolution were (1) license receipt limits for U isotopes; (2) DU product classification as Class A waste; (3) use of non-DOE disposal sites for disposal of DOE material; (4) historical NRC views; (5) definition of chemical reactivity; (6) presence of mobile radionuclides; and (7) National Environmental Policy Act coverage of disposal. The conclusion of this analysis is that an amendment to the Envirocare license issued on October 5, 2000, has reduced the uncertainties regarding disposal of the DU product at Envirocare to the point that they are now comparable with uncertainties associated with the disposal of the DU product at the Nevada Test Site that were discussed in an earlier report

  14. Evaluation of the Acceptability of Potential Depleted Uranium Hexafluoride Conversion Products at the Envirocare Disposal Site

    Energy Technology Data Exchange (ETDEWEB)

    Croff, A.G.

    2001-01-11

    The purpose of this report is to review and document the capability of potential products of depleted UF{sub 6} conversion to meet the current waste acceptance criteria and other regulatory requirements for disposal at the facility in Clive, Utah, owned by Envirocare of Utah, Inc. The investigation was conducted by identifying issues potentially related to disposal of depleted uranium (DU) products at Envirocare and conducting an initial analysis of them. Discussions were then held with representatives of Envirocare, the state of Utah (which is a NRC Agreement State and, thus, is the cognizant regulatory authority for Envirocare), and DOE Oak Ridge Operations. Provisional issue resolution was then established based on the analysis and discussions and documented in a draft report. The draft report was then reviewed by those providing information and revisions were made, which resulted in this document. Issues that were examined for resolution were (1) license receipt limits for U isotopes; (2) DU product classification as Class A waste; (3) use of non-DOE disposal sites for disposal of DOE material; (4) historical NRC views; (5) definition of chemical reactivity; (6) presence of mobile radionuclides; and (7) National Environmental Policy Act coverage of disposal. The conclusion of this analysis is that an amendment to the Envirocare license issued on October 5, 2000, has reduced the uncertainties regarding disposal of the DU product at Envirocare to the point that they are now comparable with uncertainties associated with the disposal of the DU product at the Nevada Test Site that were discussed in an earlier report.

  15. Chemical Emergencies

    Science.gov (United States)

    When a hazardous chemical has been released, it may harm people's health. Chemical releases can be unintentional, as in the case of an ... the case of a terrorist attack with a chemical weapon. Some hazardous chemicals have been developed by ...

  16. Environmental impacts of options for disposal of depleted uranium tetrafluoride (UF4)

    International Nuclear Information System (INIS)

    The U.S. Department of Energy (DOE) evaluated options for managing its depleted uranium hexafluoride (UF6) inventory in the Programmatic Environmental Impact Statement for the Long-Term Management and Use of Depleted Uranium Hexafluoride (PEIS) of April 1999. Along with the impacts from other management options, the PEIS discussed the environmental impacts from the disposal of depleted uranium oxide, which could result from the chemical conversion of depleted UF6. It has been suggested that the depleted UF6 could also be converted to uranium tetrafluoride (UF4) and disposed of. This report considers the potential environmental impacts from the disposal of DOE's depleted UF6 inventory after its conversion to UF4. The impacts were evaluated for the same three disposal facility options that were considered in the PEIS for uranium oxide: shallow earthen structures, belowground vaults, and mines. They were evaluated for a dry environmental setting representative of the western United States. To facilitate comparisons and future decision making, the depleted UF4 disposal analyses performed and the results presented in this report are at the same level of detail as that in the PEIS

  17. Isotopic dilution of 233U with depleted uranium for criticality safety in processing and disposal

    International Nuclear Information System (INIS)

    The disposal of excess 233U as waste is being considered. Because 233U is a fissile material, a key requirement for processing 233U to a final waste form and disposing of it is the avoidance of nuclear criticality. For many processing and disposal options, isotopic dilution is the most feasible and preferred option to avoid nuclear criticality. Isotopic dilution is dilution of fissile 233U with nonfissile 238U. The use of isotopic dilution removes any need to control nuclear criticality in process or disposal facilities through geometry or chemical composition. Isotopic dilution allows the use of existing waste management facilities that are not designed for significant quantities of fissile materials to be used for processing and disposing of 233U. The amount of isotopic dilution required to reduce criticality concerns to reasonable levels was determined in this study to be approximately 0.53 wt % 233U. The numerical calculations used to define this limit consisted of a homogeneous system of silicon dioxide (SiO2), water (H2O), 233U and depleted uranium (DU) in which the ratio of each component was varied to learn the conditions of maximum nuclear reactivity. About 188 parts of DU (0.2 wt % 235U) are required to dilute 1 part of 233U to this limit in a water-moderated system with no SiO2 present. Thus for the U.S. inventory of 233U, several hundred metric tons of DU would be required for isotopic dilution

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

    Energy Technology Data Exchange (ETDEWEB)

    SAMS TL; EDGE JA; SWANBERG DJ; ROBBINS RA

    2011-01-13

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

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

  1. Management, treatment and final disposal of solid hazardous hospital wastes

    International Nuclear Information System (INIS)

    Medical Waste is characterized by its high risk to human health and the environment. The main risk is biological, due to the large amount of biologically contaminated materials present in such waste. However, this does not mean that the chemical and radioactive wastes are less harmful just because they represent a smaller part of the total waste. Hazardous wastes from hospitals can be divided in 3 main categories: Solid Hazardous Hospital Wastes (S.H.H.W.), Liquid Hazardous Hospital Wastes (L.H.H.W.) and Gaseous Hazardous Hospital Wastes (G.H.H.W.) Most gaseous and liquid hazardous wastes are discharged to the environment without treatment. Since this inappropriate disposal practice, however, is not visible to society, there is no societal reaction to such problem. On the contrary, hazardous solid wastes (S.H.H.W.) are visible to society and create worries in the population. As a result, social and political pressures arise, asking for solutions to the disposal problems of such wastes. In response to such pressures and legislation approved by Costa Rica on waste handling and disposal, the Caja Costarricense de Seguro Social developed a plan for the handling, treatment, and disposal of hazardous solid wastes at the hospitals and clinics of its system. The objective of the program is to reduce the risk to society of such wastes. In this thesis a cost-effectiveness analysis was conducted to determine the minimum cost at which it is possible to reach a maximum level of reduction in hazardous wastes, transferring to the environment the least possible volume of solid hazardous wastes, and therefore, reducing risk to a minimum. It was found that at the National Children's Hospital the internal handling of hazard solid wastes is conducted with a high level of effectiveness. However, once out of the hospital area, the handling is not effective, because hazardous and common wastes are all mixed together creating a larger amount of S.H.H.W. and reducing the final efficiency

  2. 78 FR 37222 - Columbia Organic Chemical Company Site, Columbia, Richland County, South Carolina; Notice of...

    Science.gov (United States)

    2013-06-20

    ... States Environmental Protection Agency has entered into a settlement with Stephen Reichlyn concerning the.... Anita L. Davis, Chief, Superfund Enforcement & Information Management Branch, Superfund Division. BILLING CODE 6560-50-P...

  3. Deep underground disposal of radioactive wastes: Near field effects

    International Nuclear Information System (INIS)

    This report reviews the important near-field effects of the disposal of wastes in deep rock formations. The basic characteristics of waste form, container and package, buffer and backfill materials and potential host-rock types are discussed from the perspective of the performance requirements of the total repository system. Effects of waste emplacement on the separate system components and on the system as a whole are discussed. The effects include interactions between groundwater and brines and the other system components, thermal and thermo-mechanical effects, and chemical and geochemical reactions. Special consideration is given to the radiation field that exists in proximity to the waste containers and also to the coupled effects of different phenomena

  4. Earth Construction and Landfill Disposal Options for Slaker Grits

    Directory of Open Access Journals (Sweden)

    Risto Pöykiö

    2010-12-01

    Full Text Available Slaker grits, an industrial residue originating from the chemical recovery process at sulfate (kraft pulp mills, are typically disposed of to landfill in Finland. However, due to the relatively low total heavy metal and low leachable heavy metal, chloride, fluoride, sulfate, Dissolved O rganic Carbon (DOC and Total Dissolved Solids (TDS concentrations, the residue is a potential earth construction material. This paper gives an overview of the relevant Finnish legislation on the use of industrial waste as an earth construction agent, the classification of waste into one of three classes: hazardous waste, non-hazardous waste and inert waste, as well as the broad waste policy goals under EU law that affects their management.

  5. Disposal of Surplus Weapons Grade Plutonium

    International Nuclear Information System (INIS)

    The Office of Fissile Materials Disposition is responsible for disposing of inventories of surplus US weapons-usable plutonium and highly enriched uranium as well as providing, technical support for, and ultimate implementation of, efforts to obtain reciprocal disposition of surplus Russian plutonium. On January 4, 2000, the Department of Energy issued a Record of Decision to dispose of up to 50 metric tons of surplus weapons-grade plutonium using two methods. Up to 17 metric tons of surplus plutonium will be immobilized in a ceramic form, placed in cans and embedded in large canisters containing high-level vitrified waste for ultimate disposal in a geologic repository. Approximately 33 metric tons of surplus plutonium will be used to fabricate MOX fuel (mixed oxide fuel, having less than 5% plutonium-239 as the primary fissile material in a uranium-235 carrier matrix). The MOX fuel will be used to produce electricity in existing domestic commercial nuclear reactors. This paper reports the major waste-package-related, long-term disposal impacts of the two waste forms that would be used to accomplish this mission. Particular emphasis is placed on the possibility of criticality. These results are taken from a summary report published earlier this year

  6. Low level tank waste disposal study

    Energy Technology Data Exchange (ETDEWEB)

    Mullally, J.A.

    1994-09-29

    Westinghouse Hanford Company (WHC) contracted a team consisting of Los Alamos Technical Associates (LATA), British Nuclear Fuel Laboratories (BNFL), Southwest Research Institute (SwRI), and TRW through the Tank Waste Remediation System (TWRS) Technical Support Contract to conduct a study on several areas concerning vitrification and disposal of low-level-waste (LLW). The purpose of the study was to investigate how several parameters could be specified to achieve full compliance with regulations. The most restrictive regulation governing this disposal activity is the National Primary Drinking Water Act which sets the limits of exposure to 4 mrem per year for a person drinking two liters of ground water daily. To fully comply, this constraint would be met independently of the passage of time. In addition, another key factor in the investigation was the capability to retrieve the disposed waste during the first 50 years as specified in Department of Energy (DOE) Order 5820.2A. The objective of the project was to develop a strategy for effective long-term disposal of the low-level waste at the Hanford site.

  7. Recycling disposable cups into paper plastic composites.

    Science.gov (United States)

    Mitchell, Jonathan; Vandeperre, Luc; Dvorak, Rob; Kosior, Ed; Tarverdi, Karnik; Cheeseman, Christopher

    2014-11-01

    The majority of disposable cups are made from paper plastic laminates (PPL) which consist of high quality cellulose fibre with a thin internal polyethylene coating. There are limited recycling options for PPLs and this has contributed to disposable cups becoming a high profile, problematic waste. In this work disposable cups have been shredded to form PPL flakes and these have been used to reinforce polypropylene to form novel paper plastic composites (PPCs). The PPL flakes and polypropylene were mixed, extruded, pelletised and injection moulded at low temperatures to prevent degradation of the cellulose fibres. The level of PPL flake addition and the use of a maleated polyolefin coupling agent to enhance interfacial adhesion have been investigated. Samples have been characterised using tensile testing, dynamic mechanical analysis (DMA) and thermogravimetric analysis. Use of a coupling agent allows composites containing 40 wt.% of PPL flakes to increase tensile strength of PP by 50% to 30 MPa. The Young modulus also increases from 1 to 2.5 GPa and the work to fracture increases by a factor of 5. The work demonstrates that PPL disposable cups have potential to be beneficially reused as reinforcement in novel polypropylene composites.

  8. Low level tank waste disposal study

    International Nuclear Information System (INIS)

    Westinghouse Hanford Company (WHC) contracted a team consisting of Los Alamos Technical Associates (LATA), British Nuclear Fuel Laboratories (BNFL), Southwest Research Institute (SwRI), and TRW through the Tank Waste Remediation System (TWRS) Technical Support Contract to conduct a study on several areas concerning vitrification and disposal of low-level-waste (LLW). The purpose of the study was to investigate how several parameters could be specified to achieve full compliance with regulations. The most restrictive regulation governing this disposal activity is the National Primary Drinking Water Act which sets the limits of exposure to 4 mrem per year for a person drinking two liters of ground water daily. To fully comply, this constraint would be met independently of the passage of time. In addition, another key factor in the investigation was the capability to retrieve the disposed waste during the first 50 years as specified in Department of Energy (DOE) Order 5820.2A. The objective of the project was to develop a strategy for effective long-term disposal of the low-level waste at the Hanford site

  9. Urban garbage disposal and management in China

    Institute of Scientific and Technical Information of China (English)

    2003-01-01

    This paper, probing into the present situation of urban domestic garbage by analyzing its growing trend, compositional change andregional difference, reveals the problems existing in its disposal and management in China. Meanwhile, a questionnaire was conducted in fivebig cities around China for surveying urban residents' attitudes towards garbage disposal and management policies and measures. Results showedthe output of urban domestic garbage in Chinese cities is ever increasing, and the recoverable materials and energy in garbage composition arealso increasing. The population growth, economic development, and increase of residents' expenditure level are the main factors influencing thegrowing output and changing composition of the garbage. Information acquired from the questionnaire showed that majority of the urban residentsare in favor of the garbage reduction policies and managerial measures and are willing to collaborate with municipal government in battlingagainst garbage.Based on the analysis and questionnaire, some polieymaking-oriented suggestions such as operating the garbage disposal from a socialwelfare service to a sector of profit-gaining enterprises, transferring the garbage management from passive end control to active source control,promoting the classified garbage collection in cities around China, and charging garbage fees for its cleanup and disposal, have also been putforward in the paper.

  10. Subseabed Disposal Program plan. Volume I. Overview

    International Nuclear Information System (INIS)

    Some of the most stable geologic formations are underneath the deep oceans. Purpose of this program is to assess the technical, environmental, and engineering feasibility of disposing of packaged high-level waste and/or repackaged spent reactor fuel in these formations

  11. Nuclear energy: the disposal situation in Germany

    International Nuclear Information System (INIS)

    Suitable interim storage sites and ultimate radwaste disposal sites are needed regardless of the future course of nuclear energy. Beside the radwaste due to return from reprocessing abroad, considerable amounts of radwaste are also produced outside the electricity economy (medicine, research). The proponents of a complete phase-out will probably find it hard surendering to the fact that the need for storage capacities (wastes from decommissioning, whole reactor cores) will become all the more urgent the sooner the phase-out of nuclear energy is to take place. The prospective costs of reprocessing forbid holding on to this option. Economically, it would be best to go over to direct ultimate disposal as fast as possible. However, the requirement to furnish proof of adequate provisions having been made for ultimate disposal may yet cause problems, as the dispute over the Gorleben site is still not settled. A viable solution may be to prolong interim storage. This is certainly sensible from the economic viewpoint. The most important advantage of this option is that it can offer some political breathing space. It would take away the pressure to make immediate decisious that might prove wrong in retrospect. The time thus gained could be used to soberly think over the future of nuclear energy and arrive at an overall concept. All options would be retained, e.g., the exploration of other possible ultimate disposal sites, a later return to reprocessing; and, most important of all, a more reflective assessment of nuclear energy. (orig.)

  12. Disposal of Canada's nuclear fuel waste

    International Nuclear Information System (INIS)

    In 1978, the governments of Canada and Ontario established the Nuclear Fuel Waste Management program. As of the time of the conference, the research performed by AECL was jointly funded by AECL and Ontario Hydro through the CANDU owners' group. Ontario Hydro have also done some of the research on disposal containers and vault seals. From 1978 to 1992, AECL's research and development on disposal cost about C$413 million, of which C$305 was from funds provided to AECL by the federal government, and C$77 million was from Ontario Hydro. The concept involves the construction of a waste vault 500 to 1000 metres deep in plutonic rock of the Canadian Precambrian Shield. Used fuel (or possibly solidified reprocessing waste) would be sealed into containers (of copper, titanium or special steel) and emplaced (probably in boreholes) in the vault floor, surrounded by sealing material (buffer). Disposal rooms might be excavated on more than one level. Eventually all excavated openings in the rock would be backfilled and sealed. Research is organized under the following headings: disposal container, waste form, vault seals, geosphere, surface environment, total system, assessment of environmental effects. A federal Environmental Assessment Panel is assessing the concept (holding public hearings for the purpose) and will eventually make recommendations to assist the governments of Canada and Ontario in deciding whether to accept the concept, and how to manage nuclear fuel waste. 16 refs., 1 tab., 3 figs

  13. Russian low-level waste disposal program

    Energy Technology Data Exchange (ETDEWEB)

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

    1993-03-01

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

  14. Ocean disposal of heat generating waste

    International Nuclear Information System (INIS)

    A number of options for the disposal of vitrified heat generating waste are being studied to ensure that safe methods are available when the time comes for disposal operations to commence. This study has considered the engineering and operational aspects of the Penetrator Option for ocean disposal to enable technical comparisons with other options to be made. In the Penetrator Option concept, waste would be loaded into carefully designed containers which would be launched at a suitable deep ocean site where they would fall freely through the water and would embed themselves completely within the seabed sediments. Radiological protection would be provided by a multi-barrier system including the vitrified waste form, the penetrator containment, the covering sediment and the ocean. Calculations and demonstration have shown that penetrators could easily achieve embedment depths in excess of 30m and preliminary radiological assessments indicate that 30m of intact sediment would be an effective barrier for radionuclide isolation. The study concludes that a 75mm thickness of low carbon steel appears to be sufficient to provide a containment life of 500 to 1000 years during which time the waste heat output would have decayed to an insignificant level. Disposal costs have been assessed. (author)

  15. Economic analysis of alternative LLW disposal methods

    International Nuclear Information System (INIS)

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

  16. Stabilization of a mixed waste sludge for land disposal

    International Nuclear Information System (INIS)

    A solidification and stabilization technique was developed for a chemically complex mixed waste sludge containing nitrate processing wastes, sewage sludge and electroplating wastewaters, among other wastes. The sludge is originally from a solar evaporation pond and has high concentrations of nitrate salts; cadmium, chromium, and nickel concentrations of concern; and low levels of organic constituents and alpha and beta emitters. Sulfide reduction of nitrate and precipitation of metallic species, followed by evaporation to dryness and solidification of the dry sludge in recycled high density polyethylene with added lime was determined to be a satisfactory preparation for land disposal in a mixed waste repository. The application of post-consumer polyethylene has the added benefit of utilizing another problem-causing waste product. A modified Toxicity Characteristic Leaching Procedure was used to determine required treatment chemical dosages and treatment effectiveness. The waste complexity prohibited use of standard chemical equilibrium methods for prediction of reaction products during treatment. Waste characterization followed by determination of thermodynamic feasibility of oxidation and reduction products. These calculations were shown to be accurate in laboratory testing. 13 refs., 3 figs., 2 tabs

  17. Field study of disposed solid wastes from advanced coal processes

    International Nuclear Information System (INIS)

    Radian Corporation and the North Dakota Energy and Environmental Research Center (EERC) are funded to develop information to be used by private industry and government agencies for managing solid wastes produced by advanced coal combustion processes. This information will be developed by conducting several field studies on disposed wastes from these processes. Data will be collected to characterize these wastes and their interactions with the environments in which they are disposed. Three sites were selected for the field studies: Colorado Ute's fluidized bed combustion (FBC) unit in Nucla, Colorado; Ohio Edison's limestone injection multistage burner (LIMB) retrofit in Lorain, Ohio; and Freeman United's mine site in central Illinois with wastes supplied by the nearby Midwest Grain FBC unit. During the past year, field monitoring and sampling of the four landfill test cases constructed in 1989 and 1991 has continued. Option 1 of the contract was approved last year to add financing for the fifth test case at the Freeman United site. The construction of the Test Case 5 cells is scheduled to begin in November, 1992. Work during this past year has focused on obtaining data on the physical and chemical properties of the landfilled wastes, and on developing a conceptual framework for interpreting this information. Results to date indicate that hydration reactions within the landfilled wastes have had a major impact on the physical and chemical properties of the materials but these reactions largely ceased after the first year, and physical properties have changed little since then. Conditions in Colorado remained dry and no porewater samples were collected. In Ohio, hydration reactions and increases in the moisture content of the waste tied up much of the water initially infiltrating the test cells

  18. The borehole disposal of spent sources (BOSS)

    International Nuclear Information System (INIS)

    During the International Atomic Energy Agency (IAEA) Regional Training Course on 'The Management of Low-Level Radioactive Waste from Hospitals and Other Nuclear Applications' hosted by the Atomic Energy Corporation of SA Ltd. (AEC), now NECSA, during July/August 1995, the African delegates reviewed their national radioactive waste programmes. Among the issues raised, which are common to most African countries, were the lack of adequate storage facilities, lack of disposal solutions and a lack of equipment to implement widely used disposal concepts to dispose of their spent sources. As a result of this meeting, a Technical Co-operation (TC) project was launched to look at the technical feasibility and economic viability of such a concept. Phase I and II of the project have been completed and the results can be seen in three reports produced by NECSA. The Safety Assessment methodology used in the evaluation of the concept was that developed during the ISAM programme and detailed in Van Blerk's PhD thesis. This methodology is specifically developed for shallow land repositories, but was used in this case as the borehole need not be more than 100m deep and could fit into the definition of a shallow land disposal system. The studies found that the BOSS concept would be suitable for implementation in African countries as the borehole has a large capacity for sources and it is possible that an entire country's disused sources can be placed in a single borehole. The costs are a lot lower than for a shallow land trench, and the concept was evaluated using radium (226) sources as the most limiting inventory. The conclusion of the initial safety assessment was that the BOSS concept is robust, and provides a viable alternative for the disposal of radium needles. The concept is expected to provide good assurance of safety at real sites. The extension of the safety assessment to other types of spent sources is expected to be relatively straightforward. Disposal of radium needles

  19. Modeling Coupled Processes in Clay Formations for Radioactive Waste Disposal

    International Nuclear Information System (INIS)

    As a result of the termination of the Yucca Mountain Project, the United States Department of Energy (DOE) has started to explore various alternative avenues for the disposition of used nuclear fuel and nuclear waste. The overall scope of the investigation includes temporary storage, transportation issues, permanent disposal, various nuclear fuel types, processing alternatives, and resulting waste streams. Although geologic disposal is not the only alternative, it is still the leading candidate for permanent disposal. The realm of geologic disposal also offers a range of geologic environments that may be considered, among those clay shale formations. Figure 1-1 presents the distribution of clay/shale formations within the USA. Clay rock/shale has been considered as potential host rock for geological disposal of high-level nuclear waste throughout the world, because of its low permeability, low diffusion coefficient, high retention capacity for radionuclides, and capability to self-seal fractures induced by tunnel excavation. For example, Callovo-Oxfordian argillites at the Bure site, France (Fouche et al., 2004), Toarcian argillites at the Tournemire site, France (Patriarche et al., 2004), Opalinus clay at the Mont Terri site, Switzerland (Meier et al., 2000), and Boom clay at Mol site, Belgium (Barnichon et al., 2005) have all been under intensive scientific investigations (at both field and laboratory scales) for understanding a variety of rock properties and their relations with flow and transport processes associated with geological disposal of nuclear waste. Clay/shale formations may be generally classified as indurated and plastic clays (Tsang et al., 2005). The latter (including Boom clay) is a softer material without high cohesion; its deformation is dominantly plastic. For both clay rocks, coupled thermal, hydrological, mechanical and chemical (THMC) processes are expected to have a significant impact on the long-term safety of a clay repository. For

  20. Modeling Coupled Processes in Clay Formations for Radioactive Waste Disposal

    Energy Technology Data Exchange (ETDEWEB)

    Liu, Hui-Hai; Rutqvist, Jonny; Zheng, Liange; Sonnenthal, Eric; Houseworth, Jim; Birkholzer, Jens

    2010-08-31

    As a result of the termination of the Yucca Mountain Project, the United States Department of Energy (DOE) has started to explore various alternative avenues for the disposition of used nuclear fuel and nuclear waste. The overall scope of the investigation includes temporary storage, transportation issues, permanent disposal, various nuclear fuel types, processing alternatives, and resulting waste streams. Although geologic disposal is not the only alternative, it is still the leading candidate for permanent disposal. The realm of geologic disposal also offers a range of geologic environments that may be considered, among those clay shale formations. Figure 1-1 presents the distribution of clay/shale formations within the USA. Clay rock/shale has been considered as potential host rock for geological disposal of high-level nuclear waste throughout the world, because of its low permeability, low diffusion coefficient, high retention capacity for radionuclides, and capability to self-seal fractures induced by tunnel excavation. For example, Callovo-Oxfordian argillites at the Bure site, France (Fouche et al., 2004), Toarcian argillites at the Tournemire site, France (Patriarche et al., 2004), Opalinus clay at the Mont Terri site, Switzerland (Meier et al., 2000), and Boom clay at Mol site, Belgium (Barnichon et al., 2005) have all been under intensive scientific investigations (at both field and laboratory scales) for understanding a variety of rock properties and their relations with flow and transport processes associated with geological disposal of nuclear waste. Clay/shale formations may be generally classified as indurated and plastic clays (Tsang et al., 2005). The latter (including Boom clay) is a softer material without high cohesion; its deformation is dominantly plastic. For both clay rocks, coupled thermal, hydrological, mechanical and chemical (THMC) processes are expected to have a significant impact on the long-term safety of a clay repository. For

  1. COMPILATION OF DISPOSABLE SOLID WASTE CASK EVALUATIONS

    Energy Technology Data Exchange (ETDEWEB)

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

    2007-06-21

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

  2. COMPILATION OF DISPOSABLE SOLID WASTE CASK EVALUATIONS

    International Nuclear Information System (INIS)

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

  3. Intercomparison of numerical simulation codes for geologic disposal of CO2

    Energy Technology Data Exchange (ETDEWEB)

    Pruess, Karsten; Garcia, Julio; Kovscek, Tony; Oldenburg, Curt; Rutqvist, Jonny; Steefel, Carl; Xu, Tianfu

    2002-11-27

    Numerical simulation codes were exercised on a suite of eight test problems that address CO2 disposal into geologic storage reservoirs, including depleted oil and gas reservoirs, and brine aquifers. Processes investigated include single- and multi-phase flow, gas diffusion, partitioning of CO2 into aqueous and oil phases, chemical interactions of CO2 with aqueous fluids and rock minerals, and mechanical changes due to changes in fluid pressures. Representation of fluid properties was also examined. In most cases results obtained from different simulation codes were in satisfactory agreement, providing confidence in the ability of current numerical simulation approaches to handle the physical and chemical processes that would be induced by CO2 disposal in geologic reservoirs. Some discrepancies were also identified and can be traced to differences in fluid property correlations, and space and time discretization.

  4. Standard guide for characterization of spent nuclear fuel in support of geologic repository disposal

    CERN Document Server

    American Society for Testing and Materials. Philadelphia

    2009-01-01

    1.1 This guide provides guidance for the types and extent of testing that would be involved in characterizing the physical and chemical nature of spent nuclear fuel (SNF) in support of its interim storage, transport, and disposal in a geologic repository. This guide applies primarily to commercial light water reactor (LWR) spent fuel and spent fuel from weapons production, although the individual tests/analyses may be used as applicable to other spent fuels such as those from research and test reactors. The testing is designed to provide information that supports the design, safety analysis, and performance assessment of a geologic repository for the ultimate disposal of the SNF. 1.2 The testing described includes characterization of such physical attributes as physical appearance, weight, density, shape/geometry, degree, and type of SNF cladding damage. The testing described also includes the measurement/examination of such chemical attributes as radionuclide content, microstructure, and corrosion product c...

  5. Microbial processes in radioactive waste disposal

    Energy Technology Data Exchange (ETDEWEB)

    Pedersen, Karsten [Goeteborg Univ. (Sweden). Dept. of Cell and Molecular Biology, Microbiology

    2000-04-15

    Independent scientific work has unambiguously demonstrated life to be present in most deep geological formations investigated, down to depths of several kilometres. Microbial processes have consequently become an integral part of the performance safety assessment of high-level radioactive waste (HLW) repositories. This report presents the research record from the last decade of the microbiology research programme of the Swedish Nuclear Fuel and Waste Management Company (SKB) and gives current perspectives of microbial processes in HLW disposal. The goal of the microbiology programme is to understand how microbes may interact with the performance of a future HLW repository. First, for those who are not so familiar with microbes and their ways of living, the concept of 'microbe' is briefly defined. Then, the main characteristics of recognised microbial assemblage and microbial growth, activity and survival are given. The main part of the report summarises data collected during the research period of 1987-1999 and interpretations of these data. Short summaries introduce the research tasks, followed by reviews of the results and insight gained. Sulphate-reducing bacteria (SRB) produce sulphide and have commonly been observed in groundwater environments typical of Swedish HLW repositories. Consequently, the potential for sulphide corrosion of the copper canisters surrounding the HLW must be considered. The interface between the copper canister and the buffer is of special concern. Despite the fact that nowhere are the environmental constraints for life as strong as here, it has been suggested that SRB could survive and locally produce sulphide in concentrations large enough to cause damage to the canister. Experiments conducted thus far have indicated the opposite. Early studies in the research programme revealed previously unknown microbial ecosystems in igneous rock aquifers at depths exceeding 1000 m. This discovery triggered a thorough exploration of the

  6. Microbial processes in radioactive waste disposal

    International Nuclear Information System (INIS)

    Independent scientific work has unambiguously demonstrated life to be present in most deep geological formations investigated, down to depths of several kilometres. Microbial processes have consequently become an integral part of the performance safety assessment of high-level radioactive waste (HLW) repositories. This report presents the research record from the last decade of the microbiology research programme of the Swedish Nuclear Fuel and Waste Management Company (SKB) and gives current perspectives of microbial processes in HLW disposal. The goal of the microbiology programme is to understand how microbes may interact with the performance of a future HLW repository. First, for those who are not so familiar with microbes and their ways of living, the concept of 'microbe' is briefly defined. Then, the main characteristics of recognised microbial assemblage and microbial growth, activity and survival are given. The main part of the report summarises data collected during the research period of 1987-1999 and interpretations of these data. Short summaries introduce the research tasks, followed by reviews of the results and insight gained. Sulphate-reducing bacteria (SRB) produce sulphide and have commonly been observed in groundwater environments typical of Swedish HLW repositories. Consequently, the potential for sulphide corrosion of the copper canisters surrounding the HLW must be considered. The interface between the copper canister and the buffer is of special concern. Despite the fact that nowhere are the environmental constraints for life as strong as here, it has been suggested that SRB could survive and locally produce sulphide in concentrations large enough to cause damage to the canister. Experiments conducted thus far have indicated the opposite. Early studies in the research programme revealed previously unknown microbial ecosystems in igneous rock aquifers at depths exceeding 1000 m. This discovery triggered a thorough exploration of the

  7. The disposal of Canada's nuclear fuel waste: postclosure assessment of a reference system

    International Nuclear Information System (INIS)

    The concept for disposal of Canada's nuclear fuel waste is based on a vault located deep in plutonic rock of the Canadian Shield. We document in this report a method to assess the long-term impacts of a disposal facility for nuclear fuel waste. The assessment integrates relevant information from engineering design studies, site investigations, laboratory studies, expert judgment and detailed mathematical analyses to evaluate system performance in terms of safety criteria, guidelines and standards. The method includes the use of quantitative tools such as the Systems Variability Analysis computer Code (SYVAC) to deal with parameter uncertainty and the use of reasoned arguments based on well-established scientific principles. We also document the utility of the method by describing its application to a hypothetical implementation of the concept called the reference disposal system. The reference disposal system generally conforms to the overall characteristics of the concept, except we have made some specific site and design choices so that the assessment would be more realistic. To make the reference system more representative of a real system, we have used the geological observations of the AECL's Whiteshell Research Area located near Lac du Bonnet, Manitoba, to define the characteristics of the geosphere and the groundwater flow system. This research area has been subject to more than a decade of geological and hydrological studies. The analysis of the reference disposal system provides estimates of radiological and chemical toxicity impacts on members of a critical group and estimates of possible impacts on the environment. The latter impacts include estimates of radiation dose to nonhuman organisms. Other quantitative analyses examine the use of derived constraints to improve the margin of safety, the effectiveness of engineered and natural barriers, and the sensitivity of the results to influential features, events, and processes of the reference disposal

  8. Dredge spoil disposal off Kavaratti Island, Lakshadweep, India

    Digital Repository Service at National Institute of Oceanography (India)

    Chandramohan, P.; SanilKumar, V.; Jayakumar, S.

    Maintenance dredging has been carried out along the navigational channel at Kavaratii Island and dredge spoil is disposed in the open sea. This paper describes the movement of sediment plume while dredging and disposal. The study indicates...

  9. Grout Treatment Facility Land Disposal Restriction Management Plan

    International Nuclear Information System (INIS)

    This document establishes management plans directed to result in the land disposal of grouted wastes at the Hanford Grout Facilities in compliance with Federal, State of Washington, and Department of Energy land disposal restrictions. 9 refs., 1 fig

  10. Crushing leads to waste disposal savings for FUSRAP

    Energy Technology Data Exchange (ETDEWEB)

    Darby, J. [Department of Energy, Oak Ridge, TN (United States)

    1997-02-01

    In this article the author discusses the application of a rock crusher as a means of implementing cost savings in the remediation of FUSRAP sites. Transportation and offsite disposal costs are at present the biggest cost items in the remediation of FUSRAP sites. If these debris disposal problems can be handled in different manners, then remediation savings are available. Crushing can result in the ability to handle some wastes as soil disposal problems, which have different disposal regulations, thereby permitting cost savings.

  11. 20 CFR 209.16 - Disposal of payroll records.

    Science.gov (United States)

    2010-04-01

    ... 20 Employees' Benefits 1 2010-04-01 2010-04-01 false Disposal of payroll records. 209.16 Section... RAILROAD EMPLOYERS' REPORTS AND RESPONSIBILITIES § 209.16 Disposal of payroll records. Employers may dispose of payroll records for periods subsequent to 1936, provided that the payroll records are more...

  12. 25 CFR 91.13 - Health, sanitation, and sewerage disposal.

    Science.gov (United States)

    2010-04-01

    ... 25 Indians 1 2010-04-01 2010-04-01 false Health, sanitation, and sewerage disposal. 91.13 Section... INDIAN VILLAGES, OSAGE RESERVATION, OKLAHOMA § 91.13 Health, sanitation, and sewerage disposal. Health, sanitation, and sewerage disposal problems within the village reserves shall be subject to and controlled...

  13. Designing open water disposal for dredged muddy sediments

    Science.gov (United States)

    McAnally, William H.; Adamec, Stephen A.

    1987-11-01

    Open water disposal of muddy sediments in the estuarine environment is practiced to minimize dredging costs and to preserve contained disposal site capacity. Open water sites are usually either dispersive or retentive. Dispersive sites are used in the expectation that disposed sediments will not remain there, but will be transported out of the site, leaving room for additional disposal. Retentive sites are designed to ensure that disposed sediments mostly remain within the site. Choice of one of these approaches depends on the site character, sediment character, and disposal quantities. Design of disposal management plans for both site types is accomplished by use of field observations, laboratory tests, and numerical modeling. Three disposal site studies illustrate the methods used. At the Alcatraz site in San Francisco Bay, a dispersive condition is maintained by use of constraints on dredged mud characteristics that were developed from laboratory tests on erosion rates and from numerical modeling of the dump process. Field experiments were designed to evaluate the management procedure. In Corpus Christi Bay a numerical model was used to determine how much disposed sediment returns to the navigation channel, and to devise a location for disposal that will minimize that return. In Puget Sound a model has been used to ensure that most of the disposed material remains in the site. New techniques, including a piped disposal through 60 m of water, were investigated.

  14. 48 CFR 45.606 - Disposal of scrap.

    Science.gov (United States)

    2010-10-01

    ... 48 Federal Acquisition Regulations System 1 2010-10-01 2010-10-01 false Disposal of scrap. 45.606 Section 45.606 Federal Acquisition Regulations System FEDERAL ACQUISITION REGULATION CONTRACT MANAGEMENT GOVERNMENT PROPERTY Reporting, Reutilization, and Disposal 45.606 Disposal of scrap....

  15. 48 CFR 45.604-1 - Disposal methods.

    Science.gov (United States)

    2010-10-01

    ... 48 Federal Acquisition Regulations System 1 2010-10-01 2010-10-01 false Disposal methods. 45.604-1 Section 45.604-1 Federal Acquisition Regulations System FEDERAL ACQUISITION REGULATION CONTRACT MANAGEMENT GOVERNMENT PROPERTY Reporting, Reutilization, and Disposal 45.604-1 Disposal methods. (a) Except as...

  16. 5 CFR 581.401 - Aggregate disposable earnings.

    Science.gov (United States)

    2010-01-01

    ... 5 Administrative Personnel 1 2010-01-01 2010-01-01 false Aggregate disposable earnings. 581.401 Section 581.401 Administrative Personnel OFFICE OF PERSONNEL MANAGEMENT CIVIL SERVICE REGULATIONS... § 581.401 Aggregate disposable earnings. The “aggregate disposable earnings”, when used in reference...

  17. Radioactive waste disposal and public acceptance aspects

    International Nuclear Information System (INIS)

    Part of the public opinion around the world considers the wastes generated due to nuclear applications as the biggest environmental problem of the present time. The development of a solution that satisfies everybody is a great challenge, in that obtaining public acceptance for nuclear enterprises is much more challenging than solving the technical issues involved. Considering that the offering of a final solution that closes the radioactive waste cycle has a potentially positive impact on public opinion, the objective of this work is to evaluate the amount of the radioactive waste volume disposed in a five-year period in several countries and gauge the public opinion regarding nuclear energy. The results show that the volume of disposed radioactive waste increased, a fact that stresses the importance of promoting discussions about repositories and public acceptance. (author)

  18. Design of near surface disposal facilities

    Energy Technology Data Exchange (ETDEWEB)

    Han, K.W.; Bonne, A.A.; Tamborini, J. [International Atomic Energy Agency, Vienna (Austria)

    1995-12-31

    The overall objectives and essential features including technical requirements and processes for the design of near surface disposal facilities are discussed based on a technical document which has been prepared by the IAEA to provide Member States with technical guidance for developing such repositories. Emphasis is on the integrated aspect of the design requirements considering functions and characteristics of waste, engineered barriers and site, and taking into account disposal implementation activities including construction, operation, closure and post-closure control. Also the multi-staged iterative aspect of the design processes in conjunction with siting, waste characterization and performance assessment is explained. The designer may need to consider an overall waste management system, ensure that a clear definition of regulatory and operational requirements is given early in the process, and identify and take into account, as soon as practicably possible, all of the data/parameters required to achieve the final design.

  19. Ocean disposal of heat generating radioactive waste

    International Nuclear Information System (INIS)

    The operational and technical feasibility of the penetrator option for HGW disposal has been reviewed and the areas where research is required to confirm feasibility have been identified. The research requirements have been presented against the Department's ocean disposal programme timescale on a series of bar charts. The bar charts show the need for theoretical and experimental studies of the basic mechanisms governing hole closure and the development of suitable instrumentation to assess the actual behaviour of the remoulded sediment in deep ocean trials. Detailed planning of deep ocean trials in sufficient time to develop strategy, models and instrumentation, identification of site investigation requirements and thermal response studies of sediments are also required. (author)

  20. Radioactive waste containing vessel for underground disposal

    International Nuclear Information System (INIS)

    A canister and an over packing vessel for containing the canister are assembled. Preceding to underground disposal, a sealing medium under a pressurized state is sealed to the space in the overpacking vessel. As the sealing medium, non-compressible medium of a liquid or a fluid such as a mineral oil, vegetable oil, cement mortar is used in an ordinary cases. Alternatively, gases such as of nitrogen or argon are applied for the purpose of increasing pressure of the space portion to more than the pressure of underground water and the like. In the state of the underground disposal, difference of pressure between the external pressure such as of underground water and a pressure of the sealed medium is applied to the wall of the over packing vessel. With such a constitution, since the wall of the over packing vessel can be reduced, the weight and the cost can be reduced. (I.N.)

  1. Nuclear fuel waste disposal. Canada's consultative approach

    International Nuclear Information System (INIS)

    Over the past two decades, society has increasingly demanded more public participation and public input into decision-making by governments. Development of the Canadian concept for deep geological disposal of used nuclear fuel has proceeded in a manner that has taken account of the requirements for social acceptability as well as technical excellence. As the agency responsible for development of the disposal concept, Atomic Energy of Canada Limited (AECL) has devoted considerable effort to consultation with the various publics that have an interest in the concept. This evolutionary interactive and consultative process, which has been underway for some 14 years, has attempted to keep the public informed of the technical development of the concept and to invite feedback. This paper describes the major elements of this evolutionary process, which will continue throughout the concept assessment and review process currently in progress. (author)

  2. Status of Swiss waste disposal projects

    International Nuclear Information System (INIS)

    For almost 10 years now, Swiss work on planning and implementing of radioactive waste disposal has been heavily influenced by political and legislative requirements. In the years 1978-1979, continued use of expansion of nuclear power was made dependent upon the provision of projects demonstrating the technical feasibility an the long-term safety of disposal of all types of radioactive waste in Switzerland. This led in January 1985 to the submission to the Swiss Government of the extensive documentation on Project Gewahr 1985, as has been summarized at an earlier Waste Management conference. (Since the english translation Guarantee of the word Gewahr does not convey the full meaning of the german word, the original project denomination is used in this paper)

  3. Improvement of BWR radioactive waste disposal system

    International Nuclear Information System (INIS)

    Description is made here about the improvement of the disposal systems for liquid and solid radioactive waste in recent BWR plants. Regarding the improvement of liquid waste disposal systems in Toshiba, emphasis was laid on crud removal and laundry drain treatment; as a result, a crud removal system utilizing a centrifugal separation mechanism and an evaporative enriching system using anti-foaming agent have been practicalized. An important problem left for solution is the method of volume reduction of solid waste. A method attracting attention of late is the plastic solidification which is far superior to the conventional cement and bitumen solidification. In Toshiba, this method is promising to be practicalized, in which the waste is dried and then solidified with thermosetting resin. (author)

  4. Ocean CO{sub 2} disposal

    Energy Technology Data Exchange (ETDEWEB)

    Shindo, Yuji; Hakuta, Toshikatsu [National Inst. of Materials and Chemical Research, AIST, MITI, Higashi, Tsukuba, Ibaraki (Japan)

    1993-12-31

    Most countries in the world will continue to depend on fossil fuels for their main energy at least for half a country, even in the confrontation with the threat of global warming. This indicates that the development of CO{sub 2} removal technologies such as recovering CO{sub 2} from flue gases and sequestering it of in the deep oceans or subterranean sites is necessary, at least until non-fossil fuel dependent society is developed. Ocean CO{sub 2} disposal is one of the promising options for the sequestration of CO{sub 2} recovered from flue gases. Oceans have sufficient capacity to absorb all the CO{sub 2} emitted in the world. It is very significant to research and develop the technologies for ocean CO{sub 2} disposal.

  5. Technologies for immobilization and disposal of tritium

    International Nuclear Information System (INIS)

    This study was done within a program one of whose objectives was to know the state of the technology development for tritium separation in the moderator circuit at HWR and to define the possible technologies to be applied to the Argentine nuclear power plants. Within this framework the strategies adopted by each country and the available technologies for a safe disposal of tritium, not only in its gaseous state tritium but also as tritiated water were analyzed. It is considered that if the selected separation method is such that the tritium is in its gaseous state, the hydride formation for long periods of immobilization should be studied. whereas if it were triated water immobilization should be studied to choose the technology between cementation and drying agents, in both cases the final disposal site will have to be selected. (author). 8 refs

  6. Periglacial phenomena affecting nuclear waste disposal

    Directory of Open Access Journals (Sweden)

    Niini, H.

    1997-12-01

    Full Text Available Slow future changes in astronomic phenomena seem to make it likely that Finland nll suffer several cold periods during the next 100,000 years. The paper analyses the characteristics of the periglacial factors that are most likely to influence the long-term safety of high-level radioactive waste disposed of in bedrock. These factors and their influences have been divided into two categories, natural and human. It is concluded that the basically natural phenomena are theoretically better understood than the complicated phenomena caused by man. It is therefore important in future research into periglacial phenomena, as well as of the disposal problem, to emphasize not only the proper applications of the results of natural sciences, but especially the effects and control of mankind's own present and future activities.

  7. Overview of the Subseabed Disposal Program

    International Nuclear Information System (INIS)

    This presentation addresses the rationale, history, strategy, and management techniques used in the development of the US Subseabed Disposal Program (SDP) for both high level waste and spent fuel. The three subsections will summarize first, the US Department of Energy (DOE) high level waste and spent fuel waste disposal strategy and the position that the SDP occupies within that strategy; second, the technical and administrative tools developed to support the long range research and engineering plans defined by the DOE, program management, and program participants and employed to facilitate the day-to-day operation of the SDP; and third, the current studies and plans for addressing the legal, political, and international uncertainties that must be addressed before the SDP reaches the final engineering phases

  8. Fuel corrosion processes under waste disposal conditions

    International Nuclear Information System (INIS)

    The release of the majority of radionuclides from spent nuclear fuel under permanent disposal conditions will be controlled by the rate of dissolution of the UO2 fuel matrix. In this manuscript the mechanism of the coupled anodic (fuel dissolution) and cathodic (oxidant reduction) reactions which constitute the overall fuel corrosion process is reviewed, and the many published observations on fuel corrosion under disposal conditions discussed. The primary emphasis is on summarizing the overall mechanistic behaviour and establishing the primary factors likely to control fuel corrosion. Included are discussions on the influence of various oxidants including radiolytic ones, pH, temperature, groundwater composition, and the formation of corrosion product deposits. The relevance of the data recorded on unirradiated UO2 to the interpretation of spent fuel behaviour is included. Based on the review, the data used to develop fuel corrosion models under the conditions anticipated in Yucca Mountain (NV, USA) are evaluated

  9. Radioactive waste disposal and public acceptance aspects

    Energy Technology Data Exchange (ETDEWEB)

    Ulhoa, Barbara M.A.; Aleixo, Bruna L.; Mourao, Rogerio P.; Ferreira, Vinicius V.M., E-mail: mouraor@cdtn.b, E-mail: vvmf@cdtn.b [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil)

    2011-07-01

    Part of the public opinion around the world considers the wastes generated due to nuclear applications as the biggest environmental problem of the present time. The development of a solution that satisfies everybody is a great challenge, in that obtaining public acceptance for nuclear enterprises is much more challenging than solving the technical issues involved. Considering that the offering of a final solution that closes the radioactive waste cycle has a potentially positive impact on public opinion, the objective of this work is to evaluate the amount of the radioactive waste volume disposed in a five-year period in several countries and gauge the public opinion regarding nuclear energy. The results show that the volume of disposed radioactive waste increased, a fact that stresses the importance of promoting discussions about repositories and public acceptance. (author)

  10. Ocean disposal of heat generating radioactive waste

    International Nuclear Information System (INIS)

    The feasibility of safe ocean disposal options for heat-generating radioactive waste relies on the existence of suitable disposal sites. This review considers the status of the development of site selection criteria and the results of the study area investigations carried out under various national and international research programmes. In particular, the usefulness of the results obtained is related to the data needed for environmental and emplacement modelling. Preliminary investigations have identified fifteen potential deep ocean study areas in the North Atlantic. From these Great Meteor East (GME), Southern Nares Abyssal Plan (SNAP) and Kings Trough Flank (KTF) were selected for further investigation. The review includes appraisals of regional geology, geophysical studies, sedimentology, geotechnical studies, geochemical studies and oceanography. (author)

  11. Disposal modes for Mars transfer nuclear propulsion

    Science.gov (United States)

    Stancati, Michael L.; Friedlander, Alan L.

    1991-01-01

    A managed disposal approach is proposed that would place the nuclear stage or vehicle in a highly stable orbit at modest cost to mission performance. The approach requires only a small increase in initial mass in LEO, but should be included in preliminary trajectory design and performance calculations. The mass penalty is expected to be larger for all-up flight profiles, or in cases of high-thrust propulsion systems for the cargo vehicle.

  12. Commercial radioactive waste disposal: marriage or divorce

    International Nuclear Information System (INIS)

    It is shown that the state (South Carolina) is doing a good job in regulating the South Carolina disposal facility of Chemo-Nuclear Inc., and that there is no need for the NRC to reassert Federal control. The efforts in developing a low-level site in New Mexico are described. The NRC Task Force report on Federal/state regulation of commercial low-level radioactive waste burial grounds is discussed

  13. Disposal of Hanford site tank wastes

    International Nuclear Information System (INIS)

    Between 1943 and 1986, 149 single-shell tanks (SSTs) and 28 double-shell tanks (DSTs) were built and used to store radioactive wastes generated during reprocessing of irradiated uranium metal fuel elements at the U.S. Department of Energy (DOE) Hanford Site in Southeastern Washington state. The 149 SSTs, located in 12 separate areas (tank farms) in the 200 East and 200 West areas, currently contain about 1.4 x 105 m3 of solid and liquid wastes. Wastes in the SSTs contain about 5.7 x 1018 Bq (170 MCi) of various radionuclides including 90Sr, 99Tc, 137Cs, and transuranium (TRU) elements. The 28 DSTs also located in the 200 East and West areas contain about 9 x 104 m3 of liquid (mainly) and solid wastes; approximately 4 x 1018Bq (90 MCi) of radionuclides are stored in the DSTs. Important characteristics and features of the various types of SST and DST wastes are described in this paper. However, the principal focus of this paper is on the evolving strategy for final disposal of both the SST and DST wastes. Also provided is a chronology which lists key events and dates in the development of strategies for disposal of Hanford Site tank wastes. One of these strategies involves pretreatment of retrieved tank wastes to separate them into a small volume of high-level radioactive waste requiring, after vitrification, disposal in a deep geologic repository and a large volume of low-level radioactive waste which can be safely disposed of in near-surface facilities at the Hanford Site. The last section of this paper lists and describes some of the pretreatment procedures and processes being considered for removal of important radionuclides from retrieved tank wastes

  14. The management and disposal of radioactive waste

    International Nuclear Information System (INIS)

    This article describes the origin and nature of high, intermediate and low-level radioactive wastes and discusses the NIREX proposals for the effective packaging, storage and disposal of these wastes. The transportation of packaged wastes from their source of origin to a repository and the possible radiation hazards to workers and the public are discussed. The importance of careful selection of repository sites based on local geology, population density and scenic interest are also discussed. (U.K.)

  15. Social impacts of radioactive waste disposal

    International Nuclear Information System (INIS)

    In this report an approach is developed for the assessment of socio-economic impacts from radioactive waste disposal. The approach provides recommendations on procedures to be used in identification and prediction of impacts. Two decision-aiding methods are also included. The first provides for the identification of key issues and the illustration of the trade-offs involved in the decision. Multi-attribute scoring and weighting techniques are then proposed for the illustration of impacts using quantitative measures. (author)

  16. Thermal loading effects on geological disposal

    International Nuclear Information System (INIS)

    A joint study on the thermal loading effects on geological disposal was carried out within the European Community Programme on Management and Storage of Radioactive Waste by several laboratories in Belgium, France and the Federal Republic of Germany. The purpose of the work was to review the thermal effects induced by the geological disposal of high-level wastes and to assess their consequences on the 'admissible thermal loading' and on waste management in general. Three parallel studies dealt separately with the three geological media being considered for HLW disposal within the CEC programme: granite (leadership: Commissariat a l'energie atomique (CEA), France), salt (leadership: Gesellschaft fuer Strahlen- und Umweltforschung (GSF), Federal Republic of Germany), and clay (leadership: Centre d'etude de l'energie nucleaire (CEN/SCK), Belgium). The studies were based on the following items: only vitrified high-level radioactive waste was considered; the multi-barrier confinement concept was assumed (waste glass, container (with or without overpack), buffer material, rock formation); the disposal was foreseen in a deep mined repository, in an 'in-land' geological formation; only normal situations and processes were covered, no 'accident' scenario being taken into account. Although reasonably representative of a wide variety of situations, the data collected and the results obtained are generic for granite, formation-specific for salt (i.e. related to the north German Zechstein salt formation), and site-specific for clay (i.e. concentrated on the Boom clay layer at the Mol site, Belgium). For each rock type, realistic temperature limits were set, taking into account heat propagation, thermo-mechanical effects inside the rock formations, induced or modified groundwater or brine movement, effects on the buffer material as well as effects on the waste glass and canister, and finally, nuclide transport

  17. Geological disposal of heat generating radioactive waste

    International Nuclear Information System (INIS)

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

  18. Maintenance of records for radioactive waste disposal

    International Nuclear Information System (INIS)

    The safety of the radioactive waste disposal concepts does not rely on long term institutional arrangements. However, future generations may need information related to repositories and the wastes confined in them. The potentially needed information therefore has to be identified and collected. A suitable system for the preservation of that information needs to be created as a part of the disposal concept beginning with the planning phase. The IAEA has prepared this technical report to respond to the needs of Member States having repositories or involved in or considering the development of repositories. In many countries policies and systems for record keeping and maintenance of information related to disposal are the subjects of current interest. This report describes the requirements for presenting information about repositories for radioactive waste including long lived and transuranic waste and spent fuel if it is declared as a waste. The report discussed topics of identification, transfer and long term retention of high level information pertaining to the repository in a records management system (RMS) for retrieval if it becomes necessary in the future

  19. Seismic safety in nuclear-waste disposal

    International Nuclear Information System (INIS)

    Seismic safety is one of the factors that must be considered in the disposal of nuclear waste in deep geologic media. This report reviews the data on damage to underground equipment and structures from earthquakes, the record of associated motions, and the conventional methods of seismic safety-analysis and engineering. Safety considerations may be divided into two classes: those during the operational life of a disposal facility, and those pertinent to the post-decommissioning life of the facility. Operational hazards may be mitigated by conventional construction practices and site selection criteria. Events that would materially affect the long-term integrity of a decommissioned facility appear to be highly unlikely and can be substantially avoided by conservative site selection and facility design. These events include substantial fault movement within the disposal facility and severe ground shaking in an earthquake epicentral region. Techniques need to be developed to address the question of long-term earthquake probability in relatively aseismic regions, and for discriminating between active and extinct faults in regions where earthquake activity does not result in surface ruptures

  20. Mined Geologic Disposal System Requirements Document

    International Nuclear Information System (INIS)

    This Mined Geologic Disposal System Requirements Document (MGDS-RD) describes the functions to be performed by, and the requirements for, a Mined Geologic Disposal System (MGDS) for the permanent disposal of spent nuclear fuel (SNF) (including SNF loaded in multi-purpose canisters (MPCs)) and commercial and defense high-level radioactive waste (HLW) in support of the Civilian Radioactive Waste Management System (CRWMS). The purpose of the MGDS-RD is to define the program-level requirements for the design of the Repository, the Exploratory Studies Facility (ESF), and Surface Based Testing Facilities (SBTF). These requirements include design, operation, and decommissioning requirements to the extent they impact on the physical development of the MGDS. The document also presents an overall description of the MGDS, its functions (derived using the functional analysis documented by the Physical System Requirements (PSR) documents as a starting point), its segments as described in Section 3.1.3, and the requirements allocated to the segments. In addition, the program-level interfaces of the MGDS are identified. As such, the MGDS-RD provides the technical baseline for the design of the MGDS

  1. Management evaluations of waste disposal programs

    International Nuclear Information System (INIS)

    This presentation will discuss one approach to performing a management evaluation of waste disposal programs by: describing how the Department of Energy environment, safety and health (ES and H) oversight activities evolved into a management evaluation program based on three guiding principles showing how these three guiding principles provide a programmatic approach to determine the effectiveness of environment (including waste management), safety and health programs; exploring a process that can be used to conduct a management evaluation of your waste disposal programs using these guiding principles; and describing how these guiding principles are used in performing Safety Management Evaluations at Department of Energy sites. These guiding principles: focusing on line management responsibilities, identification of requirements, and skills and knowledge of the work force; provide a management verses compliance approach to evaluating safety programs (including environmental programs). The Department of Energy approach, which addressed these three guiding principles for conducting Safety Management Evaluations, can serve as a frame work for other federal agencies, public organizations and private companies. Also, although this presentation will focus primarily on waste disposal programs, the approach works equally well in evaluating other environment, safety and health programs

  2. Security of geological disposal in Japan

    International Nuclear Information System (INIS)

    The waste with high radioactivity that cannot be reused in the reprocessing of uranium or plutonium is converted to vitrified waste with a stable form. The vitrified waste as high-level radioactive waste is planned to be stored on the ground for 30 to 50 years, and then delivered to the Nuclear Waste Management Organization of Japan (NUMO), which will store it at deep underground. For vitrified waste, measures are required not to give impact on the living environment of human for more than tens of thousands years. The overpack encapsulating vitrified waste completely cut off the vitrified waste from groundwater. The outside of the overpack is surrounded by bentonite hard to penetrate water. For geological disposal, a simulation has been obtained that even though an active fault directly attacks the vitrified waste 1000 years later and the radioactive materials contained in it reach the ground surface together with groundwater, exposure level would remain at about 10 μSv/year. The safety during operation and transport would meet the standards of IAEA and the Nuclear Regulation Authority. As for the disposal site, surveys to dig tunnels up to the disposal depth are scheduled to be carefully carried out in about 20 years. Even after the promising candidate sites have been disclosed, the reasons and site selection process that respects the wishes of the municipalities will be explained. (A.O.)

  3. Management and disposal of graphite waste

    International Nuclear Information System (INIS)

    A technological and radiological assessment has been made of the management options for irradiated graphite wastes from the decommissioning of Magnox and Advanced Gas-cooled Reactors. The main contribution to the radionuclide inventory of irradiated graphite is from activation of the graphite and its stable impurities. Three different packaging methods for graphite have been described; each could be used for either sea or land disposal, and each is logistically feasible and could be achieved at reasonable cost. Leaching tests have been carried out on irradiated graphite, under a variety of conditions including those of the deep ocean bed; the different conditions had little effect on the observed leach rates of radiologically significant radionuclides. Radiological assessments were made of four generic options for disposal of packaged graphite: on the deep ocean bed, in deep geologic repositories at two different types of site, and by shallow land burial. Incineration of graphite was also considered, though this option presents logistical problems additional to those of direct disposal. With appropriate precautions during the lifetime of the 60Co content of the graphite, any of the options considered could give acceptably low doses to individuals, and all the options would merit further investigation in site-specific contexts. (author)

  4. Geological disposal of heat generating radioactive waste

    International Nuclear Information System (INIS)

    A number of options for the disposal of vitrified heat-generating radioactive waste are being studied to ensure that safe methods are available when the time comes for disposal operations to commence. This study has considered the feasibility of three designs for containers which would isolate the waste from the environment for a minimum period of 500 to 1000 years. The study was sub-divided into the following major sections: manufacturing feasibility; stress analysis; integrity in accidents; cost benefit review. The candidate container designs were taken from the results of a previous study by Ove Arup and Partners (1985) and were developed as the study progressed. Their major features can be summarised as follows: (A) a thin-walled corrosion-resistant metal shell filled with lead or cement grout. (B) an unfilled thick-walled carbon steel shell. (C) an unfilled carbon steel shell planted externally with corrosion-resistant metal. Reference repository conditions in clay, granite and salt, reference disposal operations and metals corrosion data have been taken from various European Community radioactive waste management research and engineering projects. The study concludes that design Types A and B are feasible in manufacturing terms but design Type C is not. It is recommended that model containers should be produced to demonstrate the proposed methods of manufacture and that they should be tested to validate the analytical techniques used. (author)

  5. International low level waste disposal practices and facilities

    International Nuclear Information System (INIS)

    The safe management of nuclear waste arising from nuclear activities is an issue of great importance for the protection of human health and the environment now and in the future. The primary goal of this report is to identify the current situation and practices being utilized across the globe to manage and store low and intermediate level radioactive waste. The countries included in this report were selected based on their nuclear power capabilities and involvement in the nuclear fuel cycle. This report highlights the nuclear waste management laws and regulations, current disposal practices, and future plans for facilities of the selected international nuclear countries. For each country presented, background information and the history of nuclear facilities are also summarized to frame the country's nuclear activities and set stage for the management practices employed. The production of nuclear energy, including all the steps in the nuclear fuel cycle, results in the generation of radioactive waste. However, radioactive waste may also be generated by other activities such as medical, laboratory, research institution, or industrial use of radioisotopes and sealed radiation sources, defense and weapons programs, and processing (mostly large scale) of mineral ores or other materials containing naturally occurring radionuclides. Radioactive waste also arises from intervention activities, which are necessary after accidents or to remediate areas affected by past practices. The radioactive waste generated arises in a wide range of physical, chemical, and radiological forms. It may be solid, liquid, or gaseous. Levels of activity concentration can vary from extremely high, such as levels associated with spent fuel and residues from fuel reprocessing, to very low, for instance those associated with radioisotope applications. Equally broad is the spectrum of half-lives of the radionuclides contained in the waste. These differences result in an equally wide variety of

  6. International low level waste disposal practices and facilities

    Energy Technology Data Exchange (ETDEWEB)

    Nutt, W.M. (Nuclear Engineering Division)

    2011-12-19

    The safe management of nuclear waste arising from nuclear activities is an issue of great importance for the protection of human health and the environment now and in the future. The primary goal of this report is to identify the current situation and practices being utilized across the globe to manage and store low and intermediate level radioactive waste. The countries included in this report were selected based on their nuclear power capabilities and involvement in the nuclear fuel cycle. This report highlights the nuclear waste management laws and regulations, current disposal practices, and future plans for facilities of the selected international nuclear countries. For each country presented, background information and the history of nuclear facilities are also summarized to frame the country's nuclear activities and set stage for the management practices employed. The production of nuclear energy, including all the steps in the nuclear fuel cycle, results in the generation of radioactive waste. However, radioactive waste may also be generated by other activities such as medical, laboratory, research institution, or industrial use of radioisotopes and sealed radiation sources, defense and weapons programs, and processing (mostly large scale) of mineral ores or other materials containing naturally occurring radionuclides. Radioactive waste also arises from intervention activities, which are necessary after accidents or to remediate areas affected by past practices. The radioactive waste generated arises in a wide range of physical, chemical, and radiological forms. It may be solid, liquid, or gaseous. Levels of activity concentration can vary from extremely high, such as levels associated with spent fuel and residues from fuel reprocessing, to very low, for instance those associated with radioisotope applications. Equally broad is the spectrum of half-lives of the radionuclides contained in the waste. These differences result in an equally wide variety of

  7. The remedial investigation of marine sediment at the United Heckathorn Superfund site

    Energy Technology Data Exchange (ETDEWEB)

    White, P.J.; Kohn, N.P.; Gardiner, W.W.; Word, J.Q. [Battelle/Marine Sciences Lab., Sequim, WA (United States)

    1994-02-01

    The former United Heckathom site in Richmond, California, was used to process and package chlorinated pesticides from the 1940s to the mid-1960s. These activities resulted in the contamination of upland soils and marine sediment in the adjacent waterways. Battelle/Marine Sciences Laboratory (MSL) was requested by USEPA to conduct a remedial investigation and feasibility study (RI/FS). of the marine portion of the site. The objectives of this RI are to determine the extent of pesticide contamination in inner Richmond Harbor, estimate the total volume of contaminated sediment, characterize the subsurface geology; characterize the biological effects of contaminated sediment; and characterize the quality of effluent derived from dewatered sediment through treatability testing. Sediment cores were collected from 53 stations. Vertical subsamples from each sediment core were analyzed for chlorinated pesticides. Sediment from selected cores was also analyzed for other contaminants. Younger Bay Mud (YBM) sediment from multiple stations was mixed to form composite samples representing various segments of the study area. These composites were used for solid-phase toxicity and bioaccumulation tests, and the preparation of liquid-phase samples for treatability testing. The probable quality of effluent produced by dewatering sediment was evaluated by chemical and toxicological testing of suspended-particulate-phase (SPP) and elutriate samples.

  8. HEPA Filter Disposal Write-Up 10/19/16

    Energy Technology Data Exchange (ETDEWEB)

    Loll, C. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

    2016-10-20

    Process knowledge (PK) collection on HEPA filters, is handled via the same process as other waste streams at LLNL. The Field technician or Characterization point of contact creates an information gathering document (IGD) in the IGD database, with input provided from the generator, and submits it for electronic approval. This document is essentially a waste generation profile, detailing the physical, chemical as well as radiological characteristics, and hazards, of a waste stream. It will typically contain a general, but sometimes detailed, description of the work processes which generated the waste. It will contain PK as well as radiological, and industrial hygiene analytical swipe results, and any other analytical or other supporting knowledge related to characterization. The IGD goes through an electronic approval process to formalize the characterization and to ensure the waste has an appropriate disposal path. The waste generator is responsible for providing initial process knowledge information, and approves the IGD before it routed to chemical and radiological waste characterization professionals. This is the standard characterization process for LLNL generated HEPA Filters.

  9. Evaluation of dredged material proposed for ocean disposal from Buttermilk Channel, New York

    Energy Technology Data Exchange (ETDEWEB)

    Gardiner, W.W.; Barrows, E.S.; Antrim, L.D; Gruendell, B.D.; Word, J.Q.; Tokos, J.J.S. [Battelle/Marine Sciences Lab., Sequim, WA (United States)

    1996-08-01

    Buttermilk Channel was one of seven waterways that was sampled and evaluated for dredging and sediment disposal. Sediment samples were collected and analyses were conducted on sediment core samples. The evaluation of proposed dredged material from the channel included bulk sediment chemical analyses, chemical analyses of site water and elutriate, water column and benthic acute toxicity tests, and bioaccumulation studies. Individual sediment core samples were analyzed for grain size, moisture content, and total organic carbon. A composite sediment samples, representing the entire area proposed for dredging, was analyzed for bulk density, polynuclear aromatic hydrocarbons, and 1,4-dichlorobenzene. Site water and elutriate were analyzed for metals, pesticides, and PCBs.

  10. Radioactive waste disposal fees—Methodology for calculation

    International Nuclear Information System (INIS)

    This paper summarizes the methodological approach used for calculation of fee for low- and intermediate-level radioactive waste disposal and for spent fuel disposal. The methodology itself is based on simulation of cash flows related to the operation of system for waste disposal. The paper includes demonstration of methodology application on the conditions of the Czech Republic. - Highlights: • Policy of radioactive waste management in the Czech Republic. • Methodology for calculation of fees for radioactive waste disposal. • Comparison of fee for radioactive waste disposal for selected countries. • The most important factors influencing fee-case example of the Czech Republic

  11. Chemical Emergency

    Science.gov (United States)

    ... waste collection facility. Many facilities accept pesticides, fertilizers, household cleaners, oil-based paints, drain and pool cleaners, antifreeze, and brake fluid. Some products can be recycled, which is better for our environment. If you have questions about how to dispose ...

  12. Mass-sensitive chemical preconcentrator

    Science.gov (United States)

    Manginell, Ronald P.; Adkins, Douglas R.; Lewis, Patrick R.

    2007-01-30

    A microfabricated mass-sensitive chemical preconcentrator actively measures the mass of a sample on an acoustic microbalance during the collection process. The microbalance comprises a chemically sensitive interface for collecting the sample thereon and an acoustic-based physical transducer that provides an electrical output that is proportional to the mass of the collected sample. The acoustic microbalance preferably comprises a pivot plate resonator. A resistive heating element can be disposed on the chemically sensitive interface to rapidly heat and release the collected sample for further analysis. Therefore, the mass-sensitive chemical preconcentrator can optimize the sample collection time prior to release to enable the rapid and accurate analysis of analytes by a microanalytical system.

  13. Disposal and utilization of broiler slaughter waste by composting

    Directory of Open Access Journals (Sweden)

    N Bharathy

    2012-12-01

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

  14. Assessing farmers' practices on disposal of pesticide waste after use

    International Nuclear Information System (INIS)

    Common practices of farmers on disposal of pesticide waste after use were surveyed in five regions of the rural area of Pieria in northern Greece using a structured questionnaire administered via personal interviews. Concerning leftover spray solutions, most farmers reported that they normally re-spray the treated field area until the spraying tank is empty (54.9%) or they apply the leftover spray solutions to another crop listed on the product label (30.2%). A minority of the farmers (4.3%) mentioned that they often release the leftover spray solutions near or into irrigation canals and streams. As regards rinsates generated from washing the application equipment, most farmers reported that they release the rinsates over a non-cropped area (45.7%) or they drop the rinsates near or into irrigation canals and streams (40.7%). Moreover, a great proportion of the farmers stated that they dump the empty containers by the field (30.2%) or they throw them near or into irrigation canals and streams (33.3%). Burning the empty containers in open fire (17.9%) or throwing the empty containers in common waste places (11.1%) was also reported. Several farmers stated that they continue to use old pesticides for spraying (35.8%). Training programs which raise awareness of farmers of the potential hazards of pesticide use and particularly of the proper management of waste products, recycling programs and collection systems for unwanted agricultural chemicals to prevent inappropriate waste disposal, as well as improving packaging of pesticides to minimize waste production are essential for promoting safety during all phases of pesticide handling

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

    Science.gov (United States)

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

  16. Disposal systems evaluations and tool development : Engineered Barrier System (EBS) evaluation.

    Energy Technology Data Exchange (ETDEWEB)

    Rutqvist, Jonny (LBNL); Liu, Hui-Hai (LBNL); Steefel, Carl I. (LBNL); Serrano de Caro, M. A. (LLNL); Caporuscio, Florie Andre (LANL); Birkholzer, Jens T. (LBNL); Blink, James A. (LLNL); Sutton, Mark A. (LLNL); Xu, Hongwu (LANL); Buscheck, Thomas A. (LLNL); Levy, Schon S. (LANL); Tsang, Chin-Fu (LBNL); Sonnenthal, Eric (LBNL); Halsey, William G. (LLNL); Jove-Colon, Carlos F.; Wolery, Thomas J. (LLNL)

    2011-01-01

    Key components of the nuclear fuel cycle are short-term storage and long-term disposal of nuclear waste. The latter encompasses the immobilization of used nuclear fuel (UNF) and radioactive waste streams generated by various phases of the nuclear fuel cycle, and the safe and permanent disposition of these waste forms in geological repository environments. The engineered barrier system (EBS) plays a very important role in the long-term isolation of nuclear waste in geological repository environments. EBS concepts and their interactions with the natural barrier are inherently important to the long-term performance assessment of the safety case where nuclear waste disposition needs to be evaluated for time periods of up to one million years. Making the safety case needed in the decision-making process for the recommendation and the eventual embracement of a disposal system concept requires a multi-faceted integration of knowledge and evidence-gathering to demonstrate the required confidence level in a deep geological disposal site and to evaluate long-term repository performance. The focus of this report is the following: (1) Evaluation of EBS in long-term disposal systems in deep geologic environments with emphasis on the multi-barrier concept; (2) Evaluation of key parameters in the characterization of EBS performance; (3) Identification of key knowledge gaps and uncertainties; and (4) Evaluation of tools and modeling approaches for EBS processes and performance. The above topics will be evaluated through the analysis of the following: (1) Overview of EBS concepts for various NW disposal systems; (2) Natural and man-made analogs, room chemistry, hydrochemistry of deep subsurface environments, and EBS material stability in near-field environments; (3) Reactive Transport and Coupled Thermal-Hydrological-Mechanical-Chemical (THMC) processes in EBS; and (4) Thermal analysis toolkit, metallic barrier degradation mode survey, and development of a Disposal Systems

  17. Toxicity tests and sediment chemistry at Site 9 (Neptune Drive Disposal Site) - U.S. Naval Air Station, Brunswick, Maine

    Data.gov (United States)

    US Fish and Wildlife Service, Department of the Interior — During a remedial investigation of the U.S. Naval Air Station Superfund Site in Brunswick, Maine (NASB), elevated concentrations of total polycyclic aromatic...

  18. Long-Term Performance of Silo Concrete in Low- and Intermediate-Level Waste (LILW) Disposal Facility

    International Nuclear Information System (INIS)

    Concrete has been considered one of the engineered barriers in the geological disposal facility for low- and intermediate-level wastes (LILW). The concrete plays major role as structural support, groundwater infiltration barrier, and transport barrier of radionuclides dissolved from radioactive wastes. It also works as a chemical barrier due to its high pH condition. However, the performance of the concrete structure decrease over a period of time because of several physical and chemical processes. After a long period of time in the future, the concrete would lose its effectiveness as a barrier against groundwater inflow and the release of radionuclides. An subsurface environment below the frost depth should be favorable for concrete longevity as temperature and moisture variation should be minimal, significantly reducing the potential of cracking due to drying shrinkage and thermal expansion and contraction. Therefore, the concrete structures of LILW disposal facilities below groundwater table are expected to have relatively longer service life than those of near-surface or surface concrete structures. LILW in Korea is considered to be disposed of in the Wolsong LILW Disposal Center which is under construction in geological formation. 100,000 waste packages are expected to be disposed in the 6 concrete silos below EL -80m in the Wolsong LILW Disposal Center as first stage. The concrete silo has been considered the main engineered barrier which plays a role to inhibit water inflow and the release of radionuclides to the environments. Although a number of processes are responsible for the degradation of the silo concrete, it is concluded that a reinforcing steel corrosion cause the failure of the silo concrete. Therefore, a concrete silo failure time is calculated based on a corrosion initiation time which takes for chloride ions to penetrate through the concrete cover, and a corrosion propagation time. This paper aims to analyze the concrete failure time in the

  19. Organic contaminant release from a mixed waste disposal site: A computer simulation study of transport through the vadose zone and site remediation

    International Nuclear Information System (INIS)

    Migration of organic contaminants from mixed waste disposal sites is emerging as a increasingly significant environmental problem. Organic contaminants, particularly in the vapor phase, can pose a health hazard to workers in the vicinity of the disposal site and can cause contamination of the underlying aquifer. Volatile organic chemicals such as carbon tetrachloride, chloroform, and trichloroethylene are frequently encountered at waste sites. These chlorinated hydrocarbons are relatively common chemicals and widely used as industrial solvents. Problems with organic vapors have been noted at waste disposal sites at a number of US Department of Energy (DOE) facilities. At the Idaho National Engineering Laboratory, for example, problems with organic vapors (Laney, et al., 1988) have occurred at the Radioactive Waste Management Complex (RWMC). Analyses of soil-gas samples and groundwater samples indicate that organic vapors are being emitted from disposal pits in the Subsurface Disposal Area (SDA) of the RWMC. The primary source of the organic vapor has been determined to be organic wastes that were disposed at the site in the mid-1960's. To address the organic problems at the RWMC, a multi-task activity was initiated. The first task involved a records search to determine the quantities and distribution of organic wastes. The second task consisted of a detailed soil-gas survey to identify the specific disposal areas that are producing the organic vapors

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1995-12-31

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