WorldWideScience

Sample records for preliminary siting criteria

  1. Preliminary safety criteria for organic watch list tanks at the Hanford site

    International Nuclear Information System (INIS)

    Webb, A.B.; Stewart, J.L.; Turner, O.A.; Plys, M.G.; Malinovic, B.; Grigsby, J.M.; Camaioni, D.M.; Heasler, P.G.; Samuels, W.O.; Toth, J.J.

    1995-11-01

    Condensed-phase, rapid reactions of organic salts with nitrates/nitrites in Hanford High Level Radioactive Waste single-shell tanks could lead to structural failure of the tanks resulting in significant releases of radionuclides and toxic materials. This report establishes appropriate preliminary safety criteria to ensure that tank wastes will be maintained safe. These criteria show that if actual dry wastes contain less than 1.2 MJ/kg of reactants reaction energy or less 4.5 wt % of total organic carbon, then the waste will be safe and will not propagate if ignited. Waste moisture helps to retard reactions; when waste moisture exceeds 20 wt %, rapid reactions are prevented, regardless of organic carbon concentrations. Aging and degradation of waste materials has been considered to predict the types and amounts to organic compounds present in the waste. Using measurements of 3 waste phases (liquid, salt cake, and sludge) obtained from tank waste samples analyzed in the laboratory, analysis of variance (ANOVA) models were used to estimate waste states for unmeasured tanks. The preliminary safety criteria are based upon calorimetry and propagation testing of likely organic compounds which represent actual tank wastes. These included sodium salts of citrate, formate, acetate and hydroxyethylethylenediaminetricetate (HEDTA). Hot cell tests of actual tank wastes are planned for the future to confirm propagation tests performed in the laboratory. The effects of draining liquids from the tanks which would remove liquids and moisture were considered because reactive waste which is too dry may propagate. Evaporation effects which could remove moisture from the tanks were also calculated. The various ways that the waste could be heated or ignited by equipment failures or tank operations activities were considered and appropriate monitoring and controls were recommended

  2. Preliminary safety criteria for organic watch list tanks at the Hanford site

    Energy Technology Data Exchange (ETDEWEB)

    Webb, A.B.; Stewart, J.L.; Turner, O.A. [Westinghouse Hanford Co., Richland, WA (United States); Plys, M.G.; Malinovic, B. [Fauske and Associates, Inc., Burr Ridge, IL (United States); Grigsby, J.M. [G & P Consulting, Inc. (United States); Camaioni, D.M.; Heasler, P.G.; Samuels, W.O.; Toth, J.J. [Pacific Northwest Lab., Portland, OR (United States)

    1995-11-01

    Condensed-phase, rapid reactions of organic salts with nitrates/nitrites in Hanford High Level Radioactive Waste single-shell tanks could lead to structural failure of the tanks resulting in significant releases of radionuclides and toxic materials. This report establishes appropriate preliminary safety criteria to ensure that tank wastes will be maintained safe. These criteria show that if actual dry wastes contain less than 1.2 MJ/kg of reactants reaction energy or less 4.5 wt % of total organic carbon, then the waste will be safe and will not propagate if ignited. Waste moisture helps to retard reactions; when waste moisture exceeds 20 wt %, rapid reactions are prevented, regardless of organic carbon concentrations. Aging and degradation of waste materials has been considered to predict the types and amounts to organic compounds present in the waste. Using measurements of 3 waste phases (liquid, salt cake, and sludge) obtained from tank waste samples analyzed in the laboratory, analysis of variance (ANOVA) models were used to estimate waste states for unmeasured tanks. The preliminary safety criteria are based upon calorimetry and propagation testing of likely organic compounds which represent actual tank wastes. These included sodium salts of citrate, formate, acetate and hydroxyethylethylenediaminetricetate (HEDTA). Hot cell tests of actual tank wastes are planned for the future to confirm propagation tests performed in the laboratory. The effects of draining liquids from the tanks which would remove liquids and moisture were considered because reactive waste which is too dry may propagate. Evaporation effects which could remove moisture from the tanks were also calculated. The various ways that the waste could be heated or ignited by equipment failures or tank operations activities were considered and appropriate monitoring and controls were recommended.

  3. CCS site characterisation criteria

    Energy Technology Data Exchange (ETDEWEB)

    Bachu, S.; Hawkes, C.; Lawton, D.; Pooladi-Darvish, M.; Perkins, E.

    2009-12-15

    IEA GHG recently commissioned the Alberta Research Counil in Canada to conduct a review of storage site selection criteria and site characterisation methods in order to produce a synthesis report. This report reviews the literature on the subject on the site seleciton and characterisation since the publication of the IPCC Special Report on CCS, and provides a synthesis and classification of criteria. 161 refs.

  4. Preliminary siting criteria for the proposed mixed and low-level waste treatment facility at the Idaho National Engineering Laboratory

    International Nuclear Information System (INIS)

    Jorgenson-Waters, M.

    1992-09-01

    The Mixed and Low-Level Waste Treatment Facility project was established in 1991 by the US Department of Energy Idaho Field Office. This facility will provide treatment capabilities for Idaho National Engineering Laboratory (INEL) low-level mixed waste and low-level waste. This report identifies the siting requirements imposed on facilities that treat and store these waste types by Federal and State regulatory agencies and the US Department of Energy. Site selection criteria based on cost, environmental, health and safety, archeological, geological and service, and support requirements are presented. These criteria will be used to recommend alternative sites for the new facility. The National Environmental Policy Act process will then be invoked to evaluate the alternatives and the alternative sites and make a final site determination

  5. Criteria of site assessment

    International Nuclear Information System (INIS)

    Gibbs, P.; Fuchs, H.

    1975-01-01

    The criteria which lead to the choice of a particular site for a nuclear power station are in general very similar to those which would apply to any other type of power station. The principal differences derive from the simpler transport problems for the fuel compared with, say, solid fuel and the special safety considerations which attach to nuclear reactors. The search for a suitable site obviously starts by considering where the power is needed, i.e. where the load centers are and also the existing transmission network which may help to bring the power from a more remote site to the load centers. This economic incentive to put the plant close to loads conflicts directly with the nuclear safety argument which favours more remote siting, and part of the problem of site selection is to reconcile these two matters. In addition, there are many other important matters which will be considered later concerning the adequacy of cooling water supplies, foundation conditions, etc., all of which must be examined in considerable detail. (orig./TK) [de

  6. Preliminary Site Suitability Evaluation

    International Nuclear Information System (INIS)

    J. L. King

    2001-01-01

    Commercial electric power generation, nuclear weapons production, the operation of naval reactors, and research and development activities produce spent nuclear fuel and high-level radioactive waste. Spent nuclear fuel and high-level radioactive waste have been accumulating at commercial reactor sites and storage facilities across the country since 1957. Spent nuclear fuel and high-level radioactive waste have been accumulating at sites now managed by U.S. Department of Energy (DOE) since the mid-1940s. The DOE has the statutory obligation to dispose of these wastes. The U.S. has studied methods for the safe storage and disposal of radioactive waste for more than 40 years. Many organizations and government agencies have participated in these studies. In the 1950s, the U.S. Atomic Energy Commission requested the National Academy of Sciences to evaluate options for land disposal of radioactive waste. The U.S. Atomic Energy Commission and its successor agencies, the Energy Research and Development Administration and the DOE, continued to analyze radioactive waste management options throughout the 1960s and 1970s. In 1979, an Interagency Review Group that included representatives of 14 federal government entities provided findings and recommendations to the President. After analyzing a range of options, disposal in a geologic repository emerged as the preferred long-term environmental solution. This consensus is reflected in the Nuclear Waste Policy Act of 1982 (NWPA). The NWPA and related statutes established the framework for addressing the issues of radioactive waste disposal and designated the roles and responsibilities of the federal government and the owners and generators of the waste

  7. Nevada Test Site Waste Acceptance Criteria (NTSWAC)

    Energy Technology Data Exchange (ETDEWEB)

    NNSA/NSO Waste Management Project

    2008-06-01

    This document establishes the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office, Nevada Test Site Waste Acceptance Criteria (NTSWAC). The NTSWAC provides the requirements, terms, and conditions under which the Nevada Test Site will accept low-level radioactive (LLW) and LLW Mixed Waste (MW) for disposal.

  8. Nevada Test Site Waste Acceptance Criteria (NTSWAC)

    International Nuclear Information System (INIS)

    NNSA/NSO Waste Management Project

    2008-01-01

    This document establishes the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office, Nevada Test Site Waste Acceptance Criteria (NTSWAC). The NTSWAC provides the requirements, terms, and conditions under which the Nevada Test Site will accept low-level radioactive (LLW) and LLW Mixed Waste (MW) for disposal

  9. APPLICATION OF SUSTAINABILITY CRITERIA TO STELLA, MISSOURI-ECONOMIC PLANNING-PRELIMINARY SITE INFORMATION AND ELEMENTS OF THE MASTER PLAN-16NOV2006 (1130)

    Science.gov (United States)

    Economic systems constraints and performance requirements that are essential to providing goods and services, jobs, and a functioning economic system form a list of criteria for planning a sustainable economy. This presentation places these economic criteria in the context of Ste...

  10. Hanford Site Solid Waste Acceptance Criteria

    Energy Technology Data Exchange (ETDEWEB)

    1993-11-17

    This manual defines the Hanford Site radioactive, hazardous, and sanitary solid waste acceptance criteria. Criteria in the manual represent a guide for meeting state and federal regulations; DOE Orders; Hanford Site requirements; and other rules, regulations, guidelines, and standards as they apply to acceptance of radioactive and hazardous solid waste at the Hanford Site. It is not the intent of this manual to be all inclusive of the regulations; rather, it is intended that the manual provide the waste generator with only the requirements that waste must meet in order to be accepted at Hanford Site TSD facilities.

  11. Hanford Site Solid Waste Acceptance Criteria

    International Nuclear Information System (INIS)

    1993-01-01

    This manual defines the Hanford Site radioactive, hazardous, and sanitary solid waste acceptance criteria. Criteria in the manual represent a guide for meeting state and federal regulations; DOE Orders; Hanford Site requirements; and other rules, regulations, guidelines, and standards as they apply to acceptance of radioactive and hazardous solid waste at the Hanford Site. It is not the intent of this manual to be all inclusive of the regulations; rather, it is intended that the manual provide the waste generator with only the requirements that waste must meet in order to be accepted at Hanford Site TSD facilities

  12. NEVADA TEST SITE WASTE ACCEPTANCE CRITERIA

    International Nuclear Information System (INIS)

    U.S. DEPARTMENT OF ENERGY, NATIONAL NUCLEAR SECURITY ADMINISTRATION, NEVADA SITE OFFICE

    2005-01-01

    This document establishes the U. S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO) waste acceptance criteria (WAC). The WAC provides the requirements, terms, and conditions under which the Nevada Test Site will accept low-level radioactive and mixed waste for disposal. Mixed waste generated within the State of Nevada by NNSA/NSO activities is accepted for disposal. It includes requirements for the generator waste certification program, characterization, traceability, waste form, packaging, and transfer. The criteria apply to radioactive waste received at the Nevada Test Site Area 3 and Area 5 Radioactive Waste Management Site for storage or disposal

  13. Nevada Test Site Waste Acceptance Criteria

    International Nuclear Information System (INIS)

    U. S. Department of Energy, National Nuclear Security Administration Nevada Site Office

    2005-01-01

    This document establishes the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office (NNSA/NSO) waste acceptance criteria (WAC). The WAC provides the requirements, terms, and conditions under which the Nevada Test Site (NTS) will accept low-level radioactive (LLW) and mixed waste (MW) for disposal. It includes requirements for the generator waste certification program, characterization, traceability, waste form, packaging, and transfer. The criteria apply to radioactive waste received at the NTS Area 3 and Area 5 Radioactive Waste Management Complex (RWMC) for storage or disposal

  14. Technical guidance for siting criteria development

    Energy Technology Data Exchange (ETDEWEB)

    Aldrich, D.C.; Sprung, J.L.; Alpert, D.J.; Diegert, K.; Ostmeyer, R.M.; Ritchie, L.T.; Strip, D.R.; Johnson, J.D.; Hansen, K.; Robinson, J.

    1982-12-01

    Technical guidance to support the formulation and comparison of possible siting criteria for nuclear power plants has been developed in four areas: (1) consequences of hypothetical severe nuclear-power-plant accidents, (2) characteristics of population distributions about current reactor sites, (3) site availability within the continental United States, and (4) socioeconomic impacts of reactor siting. The impact on consequences of source-term magnitude, meteorology, population distribution, and emergency response have been analyzed. Population distributions about current sites were analyzed to identify statistical characteristics, time trends, and regional differences. A site-availability data bank was constructed for the continential United States. The data bank contains information about population densities, seismicity, topography, water availability, and land-use restrictions. Finally, the socioeconomic impacts of rural-industrialization projects, energy boomtowns, and nuclear power plants were examined to determine their nature, magnitude, and dependence on site demography and remoteness.

  15. Technical guidance for siting criteria development

    International Nuclear Information System (INIS)

    Aldrich, D.C.; Sprung, J.L.; Alpert, D.J.

    1982-12-01

    Technical guidance to support the formulation and comparison of possible siting criteria for nuclear power plants has been developed in four areas: (1) consequences of hypothetical severe nuclear-power-plant accidents, (2) characteristics of population distributions about current reactor sites, (3) site availability within the continental United States, and (4) socioeconomic impacts of reactor siting. The impact on consequences of source-term magnitude, meteorology, population distribution, and emergency response have been analyzed. Population distributions about current sites were analyzed to identify statistical characteristics, time trends, and regional differences. A site-availability data bank was constructed for the continential United States. The data bank contains information about population densities, seismicity, topography, water availability, and land-use restrictions. Finally, the socioeconomic impacts of rural-industrialization projects, energy boomtowns, and nuclear power plants were examined to determine their nature, magnitude, and dependence on site demography and remoteness

  16. Preliminary site characterization - final report

    Energy Technology Data Exchange (ETDEWEB)

    Clark, D.; Smith, L.B.

    1993-12-01

    This report summarizes the ecological unit reconnaissance conducted at the F-Area Burning/Rubble Pit(s) RCRA/CERCLA Unit (F-Area BRP) on August 30 and 31, 1993 as part of the RFI/RI baseline risk assessment for the waste unit The baseline risk assessment will assess the potential endangerment to human health and the environment associated with the unit and will be used to evaluate remediation criteria, if needed. The information presented in this report will be used in subsequent stages of the ecological risk assessment to refine the conceptual site model, assist in the selection of contaminants of concern, identify potential ecological receptors, and evaluate trophic relationships and other exposure pathways. The unit reconnaissance survey was conducted in accordance with Specification No. E-18272, Rev. 1 dated August 5, 1993, and the Draft {open_quotes}Ecological Risk Assessment Program Plan for Evaluation of Waste Sites on the Savannah River Site{close_quotes}. The objectives of the site reconnaissance were to: Assess the general characteristics of on-unit biological communities including mammals, birds, reptiles, amphibians, and any aquatic communities present. Determine the location, extent, and characteristics of on-unit ecological resources, such as forested areas and wetlands, that could serve as important wildlife habitat or provide other ecological functions. Identify any overt effects of contamination on biological communities. The field investigations included mapping and describing all wetland and terrestrial habitats; recording wildlife observations of birds, mammals, and reptiles; and investigating ecological resources in nearby downgradient and downstream areas which could be affected by mobile contaminants or future remedial actions. In preparation for the field investigation, existing unit information including aerial photographs and reports were reviewed to help identify and describe ecological resources at the waste unit.

  17. Ecological criteria for evaluating candidate sites for marine reserves

    Science.gov (United States)

    Roberts, Callum M.; Andelman, Sandy; Branch, George; Bustamante, Rodrigo H.; Castilla, Juan Carlos; Dugan, Jenifer; Halpern, Benjamin S.; Lafferty, Kevin D.; Leslie, Heather; Lubchenco, Jane; McArdle, Deborah; Possingham, Hugh P.; Ruckelshaus, Mary; Warner, Robert R.

    2003-01-01

    Several schemes have been developed to help select the locations of marine reserves. All of them combine social, economic, and biological criteria, and few offer any guidance as to how to prioritize among the criteria identified. This can imply that the relative weights given to different criteria are unimportant. Where two sites are of equal value ecologically, then socioeconomic criteria should dominate the choice of which should be protected. However, in many cases, socioeconomic criteria are given equal or greater weight than ecological considerations in the choice of sites. This can lead to selection of reserves with little biological value that fail to meet many of the desired objectives. To avoid such a possibility, we develop a series of criteria that allow preliminary evaluation of candidate sites according to their relative biological values in advance of the application of socioeconomic criteria. We include criteria that, while not strictly biological, have a strong influence on the species present or ecological processes. Our scheme enables sites to be assessed according to their biodiversity, the processes which underpin that diversity, and the processes that support fisheries and provide a spectrum of other services important to people. Criteria that capture biodiversity values include biogeographic representation, habitat representation and heterogeneity, and presence of species or populations of special interest (e.g., threatened species). Criteria that capture sustainability of biodiversity and fishery values include the size of reserves necessary to protect viable habitats, presence of exploitable species, vulnerable life stages, connectivity among reserves, links among ecosystems, and provision of ecosystem services to people. Criteria measuring human and natural threats enable candidate sites to be eliminated from consideration if risks are too great, but also help prioritize among sites where threats can be mitigated by protection. While our

  18. Nevada National Security Site Waste Acceptance Criteria

    Energy Technology Data Exchange (ETDEWEB)

    NSTec Environmental Management

    2010-09-03

    This document establishes the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO) Nevada National Security Site Waste Acceptance Criteria (NNSSWAC). The NNSSWAC provides the requirements, terms, and conditions under which the Nevada National Security Site (NNSS) will accept low-level radioactive waste and mixed low-level waste for disposal. The NNSSWAC includes requirements for the generator waste certification program, characterization, traceability, waste form, packaging, and transfer. The criteria apply to radioactive waste received at the NNSS Area 3 and Area 5 Radioactive Waste Management Complex for disposal. The NNSA/NSO and support contractors are available to assist you in understanding or interpreting this document. For assistance, please call the NNSA/NSO Waste Management Project at (702) 295-7063 or fax to (702) 295-1153.

  19. Nevada National Security Site Waste Acceptance Criteria

    International Nuclear Information System (INIS)

    2010-01-01

    This document establishes the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO) Nevada National Security Site Waste Acceptance Criteria (NNSSWAC). The NNSSWAC provides the requirements, terms, and conditions under which the Nevada National Security Site (NNSS) will accept low-level radioactive waste and mixed low-level waste for disposal. The NNSSWAC includes requirements for the generator waste certification program, characterization, traceability, waste form, packaging, and transfer. The criteria apply to radioactive waste received at the NNSS Area 3 and Area 5 Radioactive Waste Management Complex for disposal. The NNSA/NSO and support contractors are available to assist you in understanding or interpreting this document. For assistance, please call the NNSA/NSO Waste Management Project at (702) 295-7063 or fax to (702) 295-1153.

  20. Nevada National Security Site Waste Acceptance Criteria

    International Nuclear Information System (INIS)

    2011-01-01

    This document establishes the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO) Nevada National Security Site Waste Acceptance Criteria (NNSSWAC). The NNSSWAC provides the requirements, terms, and conditions under which the Nevada National Security Site (NNSS) will accept low-level radioactive waste and mixed low-level waste for disposal. The NNSSWAC includes requirements for the generator waste certification program, characterization, traceability, waste form, packaging, and transfer. The criteria apply to radioactive waste received at the NNSS Area 3 and Area 5 Radioactive Waste Management Complex for disposal. The NNSA/NSO and support contractors are available to assist you in understanding or interpreting this document. For assistance, please call the NNSA/NSO Waste Management Project at (702) 295-7063 or fax to (702) 295-1153.

  1. Preliminary site characterization - final report

    International Nuclear Information System (INIS)

    Clark, D.; Smith, L.B.

    1993-12-01

    This report summarizes the ecological unit reconnaissance conducted at the F-Area Burning/Rubble Pit(s) RCRA/CERCLA Unit (F-Area BRP) on August 30 and 31, 1993 as part of the RFI/RI baseline risk assessment for the waste unit The baseline risk assessment will assess the potential endangerment to human health and the environment associated with the unit and will be used to evaluate remediation criteria, if needed. The information presented in this report will be used in subsequent stages of the ecological risk assessment to refine the conceptual site model, assist in the selection of contaminants of concern, identify potential ecological receptors, and evaluate trophic relationships and other exposure pathways. The unit reconnaissance survey was conducted in accordance with Specification No. E-18272, Rev. 1 dated August 5, 1993, and the Draft open-quotes Ecological Risk Assessment Program Plan for Evaluation of Waste Sites on the Savannah River Siteclose quotes. The objectives of the site reconnaissance were to: Assess the general characteristics of on-unit biological communities including mammals, birds, reptiles, amphibians, and any aquatic communities present. Determine the location, extent, and characteristics of on-unit ecological resources, such as forested areas and wetlands, that could serve as important wildlife habitat or provide other ecological functions. Identify any overt effects of contamination on biological communities. The field investigations included mapping and describing all wetland and terrestrial habitats; recording wildlife observations of birds, mammals, and reptiles; and investigating ecological resources in nearby downgradient and downstream areas which could be affected by mobile contaminants or future remedial actions. In preparation for the field investigation, existing unit information including aerial photographs and reports were reviewed to help identify and describe ecological resources at the waste unit

  2. Hanford Site solid waste acceptance criteria

    International Nuclear Information System (INIS)

    Ellefson, M.D.

    1998-01-01

    Order 5820.2A requires that each treatment, storage, and/or disposal facility (referred to in this document as TSD unit) that manages low-level or transuranic waste (including mixed waste and TSCA PCB waste) maintain waste acceptance criteria. These criteria must address the various requirements to operate the TSD unit in compliance with applicable safety and environmental requirements. This document sets forth the baseline criteria for acceptance of radioactive waste at TSD units operated by WMH. The criteria for each TSD unit have been established to ensure that waste accepted can be managed in a manner that is within the operating requirements of the unit, including environmental regulations, DOE Orders, permits, technical safety requirements, waste analysis plans, performance assessments, and other applicable requirements. Acceptance criteria apply to the following TSD units: the Low-Level Burial Grounds (LLBG) including both the nonregulated portions of the LLBG and trenches 31 and 34 of the 218-W-5 Burial Ground for mixed waste disposal; Central Waste Complex (CWC); Waste Receiving and Processing Facility (WRAP); and T Plant Complex. Waste from all generators, both from the Hanford Site and from offsite facilities, must comply with these criteria. Exceptions can be granted as provided in Section 1.6. Specific waste streams could have additional requirements based on the 1901 identified TSD pathway. These requirements are communicated in the Waste Specification Records (WSRds). The Hanford Site manages nonradioactive waste through direct shipments to offsite contractors. The waste acceptance requirements of the offsite TSD facility must be met for these nonradioactive wastes. This document does not address the acceptance requirements of these offsite facilities

  3. Hanford Site solid waste acceptance criteria

    International Nuclear Information System (INIS)

    Willis, N.P.; Triner, G.C.

    1991-09-01

    Westinghouse Hanford Company manages the Hanford Site solid waste treatment, storage, and disposal facilities for the US Department of Energy Field Office, Richland under contract DE-AC06-87RL10930. These facilities include radioactive solid waste disposal sites, radioactive solid waste storage areas and hazardous waste treatment, storage, and/or disposal facilities. This manual defines the criteria that must be met by waste generators for solid waste to be accepted by Westinghouse Hanford Company for treatment, storage and/or disposal facilities. It is to be used by all waste generators preparing radioactive solid waste for storage or disposal at the Hanford Site facilities and for all Hanford Site generators of hazardous waste. This manual is also intended for use by Westinghouse Hanford Company solid waste technical staff involved with approval and acceptance of solid waste. The criteria in this manual represent a compilation of state and federal regulations; US Department of Energy orders; Hanford Site requirements; and other rules, regulations, guidelines, and standards as they apply to management of solid waste. Where appropriate, these requirements are included in the manual by reference. It is the intent of this manual to provide guidance to the waste generator in meeting the applicable requirements

  4. Nevada National Security Site Waste Acceptance Criteria

    Energy Technology Data Exchange (ETDEWEB)

    NSTec Environmental Management

    2012-02-28

    This document establishes the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office (NNSA/NSO), Nevada National Security Site Waste Acceptance Criteria (NNSSWAC). The NNSSWAC provides the requirements, terms, and conditions under which the Nevada National Security Site (NNSS) will accept DOE non-radioactive classified waste, DOE non-radioactive hazardous classified waste, DOE low-level radioactive waste (LLW), DOE mixed low-level waste (MLLW), and U.S. Department of Defense (DOD) classified waste for permanent disposal. Classified waste is the only waste accepted for disposal that may be non-radioactive and will be required to meet the waste acceptance criteria for radioactive waste as specified in this document. The NNSA/NSO and support contractors are available to assist you in understanding or interpreting this document. For assistance, please call the NNSA/NSO Waste Management Project (WMP) at (702) 295-7063, and your call will be directed to the appropriate contact.

  5. Nevada National Security Site Waste Acceptance Criteria

    International Nuclear Information System (INIS)

    2012-01-01

    This document establishes the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office (NNSA/NSO), Nevada National Security Site Waste Acceptance Criteria (NNSSWAC). The NNSSWAC provides the requirements, terms, and conditions under which the Nevada National Security Site (NNSS) will accept DOE non-radioactive classified waste, DOE non-radioactive hazardous classified waste, DOE low-level radioactive waste (LLW), DOE mixed low-level waste (MLLW), and U.S. Department of Defense (DOD) classified waste for permanent disposal. Classified waste is the only waste accepted for disposal that may be non-radioactive and will be required to meet the waste acceptance criteria for radioactive waste as specified in this document. The NNSA/NSO and support contractors are available to assist you in understanding or interpreting this document. For assistance, please call the NNSA/NSO Waste Management Project (WMP) at (702) 295-7063, and your call will be directed to the appropriate contact.

  6. Nevada National Security Site Waste Acceptance Criteria

    Energy Technology Data Exchange (ETDEWEB)

    none,

    2013-06-01

    This document establishes the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Field Office (NNSA/NFO), Nevada National Security Site Waste Acceptance Criteria (NNSSWAC). The NNSSWAC provides the requirements, terms, and conditions under which the Nevada National Security Site (NNSS) will accept the following: • DOE hazardous and non-hazardous non-radioactive classified waste • DOE low-level radioactive waste (LLW) • DOE mixed low-level waste (MLLW) • U.S. Department of Defense (DOD) classified waste The LLW and MLLW listed above may also be classified waste. Classified waste is the only waste accepted for disposal that may be non-radioactive and shall be required to meet the waste acceptance criteria for radioactive waste as specified in this document. Classified waste may be sent to the NNSS as classified matter. Section 3.1.18 provides the requirements that must be met for permanent burial of classified matter. The NNSA/NFO and support contractors are available to assist the generator in understanding or interpreting this document. For assistance, please call the NNSA/NFO Environmental Management Operations (EMO) at (702) 295-7063, and the call will be directed to the appropriate contact.

  7. Nevada National Security Site Waste Acceptance Criteria

    International Nuclear Information System (INIS)

    2013-01-01

    This document establishes the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Field Office (NNSA/NFO), Nevada National Security Site Waste Acceptance Criteria (NNSSWAC). The NNSSWAC provides the requirements, terms, and conditions under which the Nevada National Security Site (NNSS) will accept the following: DOE hazardous and non-hazardous non-radioactive classified waste; DOE low-level radioactive waste (LLW); DOE mixed low-level waste (MLLW); and, U.S. Department of Defense (DOD) classified waste. The LLW and MLLW listed above may also be classified waste. Classified waste is the only waste accepted for disposal that may be non-radioactive and shall be required to meet the waste acceptance criteria for radioactive waste as specified in this document. Classified waste may be sent to the NNSS as classified matter. Section 3.1.18 provides the requirements that must be met for permanent burial of classified matter. The NNSA/NFO and support contractors are available to assist the generator in understanding or interpreting this document. For assistance, please call the NNSA/NFO Environmental Management Operations (EMO) at (702) 295-7063, and the call will be directed to the appropriate contact.

  8. Preliminary Site Characterization Report, Rulsion Site, Colorado

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-08-01

    This report is a summary of environmental information gathered during a review of the documents pertaining to Project Rulison and interviews with personnel who worked on the project. Project Rulison was part of Operation Plowshare (a program designed to explore peaceful uses for nuclear devices). The project consisted of detonating a 43-kiloton nuclear device on September 10, 1969, in western Colorado to stimulate natural gas production. Following the detonation, a reentry well was drilled and several gas production tests were conducted. The reentry well was shut-in after the last gas production test and was held in standby condition until the general cleanup was undertaken in 1972. A final cleanup was conducted after the emplacement and testing wells were plugged in 1976. However, some surface radiologic contamination resulted from decontamination of the drilling equipment and fallout from the gas flaring during drilling operations. With the exception of the drilling effluent pond, all surface contamination at the Rulison Site was removed during the cleanup operations. All mudpits and other excavations were backfilled, and both upper and lower drilling pads were leveled and dressed. This report provides information regarding known or suspected areas of contamination, previous cleanup activities, analytical results, a review of the regulatory status, the site`s physical environment, and future recommendations for Project Ruhson. Based on this research, several potential areas of contamination have been identified. These include the drilling effluent pond and mudpits used during drilling operations. In addition, contamination could migrate in the gas horizon.

  9. NWTS program criteria for mined geologic disposal of nuclear wasite: site performance criteria

    International Nuclear Information System (INIS)

    1981-02-01

    This report states ten criteria governing the suitability of sites for mined geologic disposal of high-level radioactive waste. The Department of Energy will use these criteria in its search for sites and will reevaluate their use when the Nuclear Regulatory Commission issues radioactive waste repository rules. These criteria encompass site geometry, geohydrology, geochemistry, geologic characteristics, tectonic environment, human intrusion, surface characteristics, environment, and potential socioeconomic impacts. The contents of this document include background discussion, site performance criteria, and appendices. The background section describes the waste disposal system, the application of the site criteria, and applicable criteria from NWTS-33(1) - Program Objectives, Functional Requirements and System Performance Criteria. Appendix A, entitled Comparison with Other Siting Criteria compares the NWTS criteria with those recommended by other agencies. Appendix B contains DOE responses to public comments received on the January 1980 draft of this document. Appendix C is a glossary

  10. Nevada Test Site Waste Acceptance Criteria, December 2000

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-12-01

    This document establishes the US Department of Energy, Nevada Operations Office waste acceptance criteria. The waste acceptance criteria provides the requirements, terms, and conditions under which the Nevada Test Site will accept low-level radioactive waste and mixed waste for disposal. It includes requirements for the generator waste certification program, characterization, traceability, waste form, packaging, and transfer. The criteria apply to radioactive waste received at the Nevada Test Site Area 3 and Area 5 Radioactive Waste Management Sites for storage or disposal.

  11. Nevada Test Site Waste Acceptance Criteria, December 2000

    International Nuclear Information System (INIS)

    2000-01-01

    This document establishes the US Department of Energy, Nevada Operations Office waste acceptance criteria. The waste acceptance criteria provides the requirements, terms, and conditions under which the Nevada Test Site will accept low-level radioactive waste and mixed waste for disposal. It includes requirements for the generator waste certification program, characterization, traceability, waste form, packaging, and transfer. The criteria apply to radioactive waste received at the Nevada Test Site Area 3 and Area 5 Radioactive Waste Management Sites for storage or disposal

  12. At-reactor storage concepts criteria for preliminary assessment

    International Nuclear Information System (INIS)

    Boydston, L.A.

    1981-12-01

    The licensing, safety, and environmental considerations of four wet and four dry at-reactor storage concepts are presented. Physical criteria for each concept are examined to determine the minimum site and facility requirements which must be met by a utility which desires to expand its at-reactor spent fuel storage capability

  13. Preliminary criteria for the handling of radioactive tea

    International Nuclear Information System (INIS)

    Oezemre, A.Y.

    1993-01-01

    Two years after the Chernobyl accident, tea plantations in northeastern Turkey, at Rize and its surroundings especially, were affected by radioactive fallout. As a radiological countermeasure, the turkish Atomic energy commission (AEC) was called in before tea packing and set up a maximum permissible limit of 12,500 Bq/kg for dry tea in the market; 58,078 t of radioactive tea (≥ 25,000 Bq/kg) were set apart as radioactive waste. In its concern to determine the best solution about the handling of radioactive tea and considering the national conditions, the AEC developed four preliminary criteria that led to select the burial option. (author)

  14. Nevada Test Site Waste Acceptance Criteria

    International Nuclear Information System (INIS)

    U.S. Department of Energy, Nevada Operations Office, Waste Acceptance Criteria

    1999-01-01

    This document provides the requirements, terms, and conditions under which the Nevada Test Site will accept low-level radioactive and mixed waste for disposal; and transuranic and transuranic mixed waste for interim storage at the Nevada Test Site

  15. Site suitability criteria for solidified high level waste repositories

    International Nuclear Information System (INIS)

    Heckman, R.A.; Holdsworth, T.; Isherwood, D.; Towse, D.F.; Dayem, N.L.

    1979-01-01

    The NRC is developing a framework of regulations, criteria, and standards. Lawrence Livermore Laboratory provides broad technical support to the NRC for developing this regulatory framework, part of which involves site suitability criteria for solidified high-level wastes (SHLW). Both the regulatory framework and the technical base on which it rests have evolved in time. This document is the second report of the technical support project. It was issued as a draft working paper for a programmatic review held at LLL from August 16 to 18, 1977. It was printed and distributed solely as a briefing document on preliminary methodology and initial findings for the purpose of critical review by those in attendance. These briefing documents are being reprinted now in their original formats as UCID-series reports for the sake of the historical record. Analysis results have evolved as both the models and data base have changed. As a result, the methodology, models, and data base in this document are severely outmoded

  16. Geoscientific evaluation factors and criteria for siting and site evaluation. Progress report

    International Nuclear Information System (INIS)

    Stroem, A.; Ericsson, Lars O.; Svemar, C.; Almen, K.E.; Andersson, Johan

    1999-03-01

    thereby involved. Requirements and preferences regarding the deep repository, and thereby the rock, are primarily formulated with respect to function and not directly for individual parameter values. In a similar manner the evaluation factors have been arranged per geoscientific discipline. A geoscientific parameter that can be measured or estimated in site investigations is considered to be a suitable evaluation factor if one of the following conditions is fulfilled: a direct requirement or an essential preference has been formulated for the parameter, or a the parameter is expected to have a great influence on the result of one or more important function analyses. Based on a preliminary list of possible evaluation factors, the level of knowledge that can or should be reached after the feasibility study, site investigation and detailed characterization have been completed is also discussed. It is not reasonable to designate a geoscientific parameter as an evaluation factor if the parameter cannot be measured or estimated with sufficient accuracy. Criteria for site evaluation will also be determined in the future work. When it comes to repository performance, criteria consist of indicative values or value ranges of outcomes of performance assessments. The criteria can be changed during the course of the siting work as the information available on the sites changes. But requirements and preferences remain the same. Even though the overall evaluation of the suitability of the sites is determined within the framework of an integrated safety assessment and an integrated construction analysis, the specified criteria should provide good guidance regarding the results of such an integrated assessment/analysis

  17. Geoscientific evaluation factors and criteria for siting and site evaluation. Progress report

    Energy Technology Data Exchange (ETDEWEB)

    Stroem, A.; Ericsson, Lars O.; Svemar, C. [Swedish Nuclear Fuel and Waste Management Co., Stockholm (Sweden); Almen, K.E. [KEA GEO-konsult AB (Sweden); Andersson, Johan [Golder Grundteknik KB (Sweden)

    1999-03-01

    thereby involved. Requirements and preferences regarding the deep repository, and thereby the rock, are primarily formulated with respect to function and not directly for individual parameter values. In a similar manner the evaluation factors have been arranged per geoscientific discipline. A geoscientific parameter that can be measured or estimated in site investigations is considered to be a suitable evaluation factor if one of the following conditions is fulfilled: a direct requirement or an essential preference has been formulated for the parameter, or a the parameter is expected to have a great influence on the result of one or more important function analyses. Based on a preliminary list of possible evaluation factors, the level of knowledge that can or should be reached after the feasibility study, site investigation and detailed characterization have been completed is also discussed. It is not reasonable to designate a geoscientific parameter as an evaluation factor if the parameter cannot be measured or estimated with sufficient accuracy. Criteria for site evaluation will also be determined in the future work. When it comes to repository performance, criteria consist of indicative values or value ranges of outcomes of performance assessments. The criteria can be changed during the course of the siting work as the information available on the sites changes. But requirements and preferences remain the same. Even though the overall evaluation of the suitability of the sites is determined within the framework of an integrated safety assessment and an integrated construction analysis, the specified criteria should provide good guidance regarding the results of such an integrated assessment/analysis 14 refs, figs, tabs

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

    International Nuclear Information System (INIS)

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

    1982-08-01

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

  19. Preliminary radiation criteria and nuclear analysis for ETF

    International Nuclear Information System (INIS)

    Engholm, B.A.

    1980-09-01

    Preliminary biological and materials radiation dose criteria for the Engineering Test Facility are described and tabulated. In keeping with the ETF Mission Statement, a key biological dose criterion is a 24-hour shutdown dose rate of 2 mrem/hr on the surface of the outboard bulk shield. Materials dose criteria, which primarily govern the inboard shield design, include 10 9 rads exposure limit to epoxy insulation, 3 x 10 -4 dpa damage to the TF coil copper stabilizer, and a total nuclear heating rate of 5 kW in the inboard TF coils. Nuclear analysis performed during FY 80 was directed primarily at the inboard and outboard bulk shielding, and at radiation streaming in the neutral beam drift ducts. Inboard and outboard shield thicknesses to achieve the biological and materials radiation criteria are 75 cm inboard and 125 cm outboard, the configuration consisting of alternating layers of stainless steel and borated water. The outboard shield also includes a 5 cm layer of lead. NBI duct streaming analyses performed by ORNL and LASL will play a key role in the design of the duct and NBI shielding in FY 81. The NBI aluminum cryopanel nuclear heating rate during the heating cycle is about 1 milliwatt/cm 3 , which is far less than the permissible limit

  20. Preliminary selection criteria for the Yucca Mountain Project waste package container material

    International Nuclear Information System (INIS)

    Halsey, W.G.

    1991-01-01

    The Department of Energy's Yucca Mountain Project (YMP) is evaluating a site at Yucca Mountain in Nevada for construction of a geologic repository for the storage of high-level nuclear waste. Lawrence Livermore National Laboratory's (LLNL) Nuclear Waste Management Project (NWMP) has the responsibility for design, testing, and performance analysis of the waste packages. The design is performed in an iterative manner in three sequential phases (conceptual design, advanced conceptual design, and license application design). An important input to the start of the advanced conceptual design is the selection of the material for the waste containers. The container material is referred to as the 'metal barrier' portion of the waste package, and is the responsibility of the Metal Barrier Selection and Testing task at LLNL. The selection will consist of several steps. First, preliminary, material-independent selection criteria will be established based on the performance goals for the container. Second, a variety of engineering materials will be evaluated against these criteria in a screening process to identify candidate materials. Third, information will be obtained on the performance of the candidate materials, and final selection criteria and quantitative weighting factors will be established based on the waste package design requirements. Finally, the candidate materials will be ranked against these criteria to determine whether they meet the mandated performance requirements, and to provide a comparative score to choose the material for advanced conceptual design activities. This document sets forth the preliminary container material selection criteria to be used in screening candidate materials. 5 refs

  1. Accident consequence assessment and siting criteria development

    International Nuclear Information System (INIS)

    Kollas, J.G.

    1988-01-01

    The methodology developed is based on assessing the average over a large spectrum of meteorological conditions whole body collective dose resulting from a severe reference accident. The assessment of this dose is performed by code CRAC.GAEC, the Greek A.E.C. version of code CRAC2. The collective dose, which is chosen as a measure of the social radiation risk, is compared to the dose corresponding to a level of social risk encountered historically in energy production as a whole. The outcome of the comparison can be the determination of one or more sectors of acceptable sites for a set of specific conditions considered, such as the reactor characteristics. The present approach was aimed to deal with the problems stemming from the demographic idiomorphy of Greece, where one third of the country's population is concentrated in Athens, with the rest of the country exhibiting small population densities. One of the applications of the methodology developed concerned the identification of acceptable sites near Athens. For these sites the risk from the reference severe accident of a standard reactor to the over three millions inhabitants of Athens is less tan the risk corresponding to the same population that is due to energy production

  2. Additional media studies for site suitability criteria

    International Nuclear Information System (INIS)

    Donich, T.R.; Kaufman, A.M.; Sauter, G.D.; Steinborn, T.L.; Towse, D.F.

    1978-01-01

    Site suitability studies have been made previously at LLL on bedded salt and shale. In the present study domed salt, basalt, and crystalline rock are compared with bedded salt and shale and with each other as possible repositories. The level of effort required to develop models for these media that are similar in quality to those available for bedded salt and shale is evaluated. The effort necessary to develop data bases on the physical and chemical properties comparable to that available for bedded salt and shale is also estimated. Each medium is evaluated as a suitable repository environment. The funding necessary for model and data base development is estimated

  3. Preliminary safety analysis of the Gorleben site

    International Nuclear Information System (INIS)

    Bracke, G.; Fischer-Appelt, K.

    2014-01-01

    The safety requirements governing the final disposal of heat-generating radioactive waste in Germany were implemented by the Federal Ministry of Environment, Natural Conservation and Nuclear Safety (BMU) in 2010. The Ministry considers as a fundamental objective the protection of man and the environment against the hazards of radioactive waste. Unreasonable burdens and obligation for future generations shall be avoided. The main safety principles are concentration and inclusion of radioactive and other pollutants in a containment-providing rock zone. Any release of radioactive nuclides may increase the risk for men and the environment only negligibly compared to natural radiation exposure. No intervention or maintenance work shall be necessary in the post-closure phase. Retrieval/recovery of the waste shall be possible up to 500 years after closure. The Gorleben salt dome has been discussed since the 1970's as a possible repository site for heat-generating radioactive waste in Germany. The objective of the project preliminary safety analysis of the Gorleben site (VSG) was to assess if repository concepts at the Gorleben site or other sites with a comparable geology could comply with these requirements based on currently available knowledge (Fischer-Appelt, 2013; Bracke, 2013). In addition to this it was assessed if methodological approaches can be used for a future site selection procedure and which technological and conceptual considerations can be transferred to other geological situations. The objective included the compilation and review of the available exploration data of the Gorleben site and on disposal in salt rock, the development of repository designs, and the identification of the needs for future R and D work and further site investigations. (authors)

  4. Nevada test site waste acceptance criteria

    International Nuclear Information System (INIS)

    1996-01-01

    This document provides the requirements, terms, and conditions under which the Nevada Test Site (NTS) will accept low-level radioactive and mixed waste for disposal; and transuranic and transuranic mixed waste for interim storage at the NTS. Review each section of this document. This document is not intended to include all of the requirements; rather, it is meant as a guide toward meeting the regulations. All references in this document should be observed to avoid omission of requirements on which acceptance or rejection of waste will be based. The Department of Energy/Nevada Operations Office (DOE/NV) and support contractors are available to assist you in understanding or interpreting this document

  5. Nevada test site waste acceptance criteria

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-09-01

    This document provides the requirements, terms, and conditions under which the Nevada Test Site (NTS) will accept low-level radioactive and mixed waste for disposal; and transuranic and transuranic mixed waste for interim storage at the NTS. Review each section of this document. This document is not intended to include all of the requirements; rather, it is meant as a guide toward meeting the regulations. All references in this document should be observed to avoid omission of requirements on which acceptance or rejection of waste will be based. The Department of Energy/Nevada Operations Office (DOE/NV) and support contractors are available to assist you in understanding or interpreting this document.

  6. Early Site Permit Demonstration Program: Siting Guide, Site selection and evaluation criteria for an early site permit application

    International Nuclear Information System (INIS)

    1993-01-01

    In August 1991, the Joint Contractors came to agreement with Sandia National Laboratories (SNL) and the Department of Energy (DOE) on a workscope for the cost-shared Early Site Permit Demonstration Program. One task within the scope was the development of a guide for site selection criteria and procedures. A generic Siting Guide his been prepared that is a roadmap and tool for applicants to use developing detailed siting plans for their specific region of the country. The guide presents three fundamental principles that, if used, ensure a high degree of success for an ESP applicant. First, the site selection process should take into consideration environmentally diverse site locations within a given region of interest. Second, the process should contain appropriate opportunities for input from the public. Third, the process should be applied so that it is clearly reasonable to an impartial observer, based on appropriately selected criteria, including criteria which demonstrate that the site can host an advanced light water reactor (ALWR). The Siting Guide provides for a systematic, comprehensive site selection process in which three basic types of criteria (exclusionary, avoidance, and suitability) are presented via a four-step procedure. It provides a check list of the criteria for each one of these steps. Criteria are applied qualitatively, as well as presented numerically, within the guide. The applicant should use the generic guide as an exhaustive checklist, customizing the guide to his individual situation

  7. Early Site Permit Demonstration Program: Siting Guide, Site selection and evaluation criteria for an early site permit application. Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    1993-03-24

    In August 1991, the Joint Contractors came to agreement with Sandia National Laboratories (SNL) and the Department of Energy (DOE) on a workscope for the cost-shared Early Site Permit Demonstration Program. One task within the scope was the development of a guide for site selection criteria and procedures. A generic Siting Guide his been prepared that is a roadmap and tool for applicants to use developing detailed siting plans for their specific region of the country. The guide presents three fundamental principles that, if used, ensure a high degree of success for an ESP applicant. First, the site selection process should take into consideration environmentally diverse site locations within a given region of interest. Second, the process should contain appropriate opportunities for input from the public. Third, the process should be applied so that it is clearly reasonable to an impartial observer, based on appropriately selected criteria, including criteria which demonstrate that the site can host an advanced light water reactor (ALWR). The Siting Guide provides for a systematic, comprehensive site selection process in which three basic types of criteria (exclusionary, avoidance, and suitability) are presented via a four-step procedure. It provides a check list of the criteria for each one of these steps. Criteria are applied qualitatively, as well as presented numerically, within the guide. The applicant should use the generic guide as an exhaustive checklist, customizing the guide to his individual situation.

  8. Workshop material for state review of USNRC site suitability criteria for high-level radioactive waste repositories

    International Nuclear Information System (INIS)

    1977-08-01

    The Nuclear Regulatory Commission (NRC) is developing criteria on which to judge whether a proposed site for a geologic repository is suitable for disposal of high-level nuclear wastes. To aid in its analysis and assessment, NRC is planning three early independent reviews of the site suitability criteria development effort: a peer review by experts outside of NRC; a review by the National Academy of Sciences; and a review by State officials. This document has been prepared to aid workshop participants in understanding the Preliminary Site Suitability Criteria and to prepare them to contribute to an evaluation of those criteria

  9. Set of rules SOR 2 reactor site criteria

    International Nuclear Information System (INIS)

    1976-06-01

    The purpose of this set of rules is to describe criteria which guide the Director in his evaluation of the suitability of proposed sites for stationary power and testing reactors subject to SOR 2. (B.G.)

  10. Inventory of sites used to develop residual radioactivity criteria

    International Nuclear Information System (INIS)

    Ronca-Battista, M.; Hardeman, J.C. Jr.

    1986-01-01

    The US Environmental Protection Agency (EPA), in conjunction with the National Conference of Radiation Control Program Directors (CRCPD), has compiled an inventory of never licensed or otherwise poorly documented sites that may be contaminated with radioactive materials. This effort is in support of the EPA's development of radiation protection criteria for residual radioactivity at decommissioned sites. The inventory will help to establish the range of circumstances for which criteria are needed, as well as the suitability of candidate criteria for actual situations. The information will also be used to develop model sites and facilities for analyzing technical and economic feasibility of residual radioactivity criteria and to assess costs and benefits of alternate criteria. Relevant information about each site, such as radionuclides, waste forms, and quantities present will be included in the inventory when such information is available. The CRCPD has requested that each State radiation control agency furnish the information for the inventory. The inventory supplements the relatively extensive documentation of sites regulated by Federal or State agencies with information on old or unlicensed sites, such as old waste storage sites or radium ore processing facilities

  11. Site selection criteria for shallow land burial of low-level radioactive waste

    International Nuclear Information System (INIS)

    Falconer, K.L.; Hull, L.C.; Mizell, S.A.

    1982-01-01

    Twelve site selection criteria are presented. These are: (1) site shall be of sufficient area and depth to accommodate the projected volume of waste and a three dimensional buffer zone; (2) site should allow waste to be buried either completely above or below the transition zone between the unsaturated and saturated zones; (3) site should be located where flooding will not jeopardize performance; (4) site should be located where erosion will not jeopardize performance; (5) site should be located in areas where hydrogeologic conditions allow reliable performance prediction; (6) site should be located where geologic hazards will not jeopardize performance; (7) site should be selected with considerations given to those characteristics of earth materials and water chemistry that favor increased residence times and/or attenuation of radionuclide concentrations within site boundaries; (8) site should be selected with consideration given to current and projected population distributions; (9) site should be selected with consideration given to current and projected land use and resource development; (10) site should be selected with consideration given to location of waste generation, access to all-weather highway and rail routes, and access utilities; (11) site should be selected consistent with federal laws and regulations; (12) site should not be located within areas that are protected from such use by federal laws and regulations. These criteria are considered preliminary and do not necessarily represent the position of the Department of Energy's Low-Level Waste Management Program

  12. Preliminary siting activities for new waste handling facilities at the Idaho National Engineering Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    Taylor, D.D.; Hoskinson, R.L.; Kingsford, C.O.; Ball, L.W.

    1994-09-01

    The Idaho Waste Processing Facility, the Mixed and Low-Level Waste Treatment Facility, and the Mixed and Low-Level Waste Disposal Facility are new waste treatment, storage, and disposal facilities that have been proposed at the Idaho National Engineering Laboratory (INEL). A prime consideration in planning for such facilities is the selection of a site. Since spring of 1992, waste management personnel at the INEL have been involved in activities directed to this end. These activities have resulted in the (a) identification of generic siting criteria, considered applicable to either treatment or disposal facilities for the purpose of preliminary site evaluations and comparisons, (b) selection of six candidate locations for siting,and (c) site-specific characterization of candidate sites relative to selected siting criteria. This report describes the information gathered in the above three categories for the six candidate sites. However, a single, preferred site has not yet been identified. Such a determination requires an overall, composite ranking of the candidate sites, which accounts for the fact that the sites under consideration have different advantages and disadvantages, that no single site is superior to all the others in all the siting criteria, and that the criteria should be assigned different weighing factors depending on whether a site is to host a treatment or a disposal facility. Stakeholder input should now be solicited to help guide the final selection. This input will include (a) siting issues not already identified in the siting, work to date, and (b) relative importances of the individual siting criteria. Final site selection will not be completed until stakeholder input (from the State of Idaho, regulatory agencies, the public, etc.) in the above areas has been obtained and a strategy has been developed to make a composite ranking of all candidate sites that accounts for all the siting criteria.

  13. Preliminary siting activities for new waste handling facilities at the Idaho National Engineering Laboratory

    International Nuclear Information System (INIS)

    Taylor, D.D.; Hoskinson, R.L.; Kingsford, C.O.; Ball, L.W.

    1994-09-01

    The Idaho Waste Processing Facility, the Mixed and Low-Level Waste Treatment Facility, and the Mixed and Low-Level Waste Disposal Facility are new waste treatment, storage, and disposal facilities that have been proposed at the Idaho National Engineering Laboratory (INEL). A prime consideration in planning for such facilities is the selection of a site. Since spring of 1992, waste management personnel at the INEL have been involved in activities directed to this end. These activities have resulted in the (a) identification of generic siting criteria, considered applicable to either treatment or disposal facilities for the purpose of preliminary site evaluations and comparisons, (b) selection of six candidate locations for siting,and (c) site-specific characterization of candidate sites relative to selected siting criteria. This report describes the information gathered in the above three categories for the six candidate sites. However, a single, preferred site has not yet been identified. Such a determination requires an overall, composite ranking of the candidate sites, which accounts for the fact that the sites under consideration have different advantages and disadvantages, that no single site is superior to all the others in all the siting criteria, and that the criteria should be assigned different weighing factors depending on whether a site is to host a treatment or a disposal facility. Stakeholder input should now be solicited to help guide the final selection. This input will include (a) siting issues not already identified in the siting, work to date, and (b) relative importances of the individual siting criteria. Final site selection will not be completed until stakeholder input (from the State of Idaho, regulatory agencies, the public, etc.) in the above areas has been obtained and a strategy has been developed to make a composite ranking of all candidate sites that accounts for all the siting criteria

  14. Site characterization criteria (DOE-STD-1022-94) for natural phenomena hazards at DOE sites

    International Nuclear Information System (INIS)

    Chen, J.C.; Ueng, T.S.; Boissonnade, A.C.

    1995-12-01

    This paper briefly summarizes requirements of site characterization for Natural Phenomena Hazards (NPH) at DOE sites. In order to comply with DOE Order 5480.28, site characterization criteria has been developed to provide site-specific information needed for development of NPH assessment criteria. Appropriate approaches are outlined to ensure that the current state-of-the-art methodologies and procedures are used in the site characterization. General and detailed site characterization requirements are provided in the areas of meteorology, hydrology, geology, seismology and geotechnical studies

  15. Site suitability criteria for solidified high level waste repositories

    International Nuclear Information System (INIS)

    Heckman, R.A.; Holdsworth, T.; Towse, D.F.

    1979-01-01

    Activities devoted to development of regulations, criteria, and standards for storage of solidified high-level radioactive wastes are reported. The work is summarized in sections on site suitability regulations, risk calculations, geological models, aquifer models, human usage model, climatology model, and repository characteristics. Proposed additional analytical work is also summarized

  16. Early Site Permit Demonstration Program: Regulatory criteria evaluation report

    International Nuclear Information System (INIS)

    1993-03-01

    The primary objective of the Early Site Plan Demonstration Program (ESPDP) is to demonstrate successfully the use of 10CFR52 to obtain ESPs for one or more US sites for one (or more) ALWR nuclear power plants. It is anticipated that preparation of the ESP application and interaction with NRC during the application review process will result not only in an ESP for the applicant(s) but also in the development of criteria and definition of processes, setting the precedent that facilitates ESPs for subsequent ESP applications. Because siting regulatory processes and acceptance criteria are contained in over 100 separate documents, comprehensive licensing and technical reviews were performed to establish whether the requirements and documentation are self-consistent, whether the acceptance criteria are sufficiently well-defined and clear, and whether the licensing process leading to the issuance of an ESP is unambiguously specified. This document provides appendices A and B of this report. Appendix A contains a list of regulations, regulatory guidance, and acceptance criteria; Appendix B contains a cross-reference index of siting-related documentation

  17. 40 CFR 228.6 - Specific criteria for site selection.

    Science.gov (United States)

    2010-07-01

    ... 40 Protection of Environment 24 2010-07-01 2010-07-01 false Specific criteria for site selection. 228.6 Section 228.6 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) OCEAN..., nursery, feeding, or passage areas of living resources in adult or -juvenile phases; (3) Location in...

  18. Sediment quality criteria: A review with recommendations for developing criteria for the Hanford Site

    Energy Technology Data Exchange (ETDEWEB)

    Driver, C.J.

    1994-05-01

    Criteria for determining the quality of liver sediment are necessary to ensure that concentrations of contaminants in aquatic systems are within acceptable limits for the protection of aquatic and human life. Such criteria should facilitate decision-making about remediation, handling, and disposal of contaminants. Several approaches to the development of sediment quality criteria (SQC) have been described and include both descriptive and numerical methods. However, no single method measures all impacts at all times to all organisms (U.S. EPA 1992b). The U.S. EPA`s interest is primarily in establishing chemically based, numerical SQC that are applicable nation-wide (Shea 1988). Of the approaches proposed for SQC development, only three are being considered for numerical SQC on a national level. These approaches include an Equilibrium Partitioning Approach, a site-specific method using bioassays (the Apparent Effects Threshold Approach), and an approach similar to EPA`s water quality criteria (Pavlou and Weston 1984). Although national (or even regional) criteria address a number of political, litigative, and engineering needs, some researchers feel that protection of benthic communities require site-specific, biologically based criteria (Baudo et al. 1990). This is particularly true for areas where complex mixtures of contaminants are present in sediments. Other scientifically valid and accepted procedures for freshwater SQC include a background concentration approach, methods using field or spiked bioassays, a screening level concentration approach, the Apparent Effects Threshold Approach, the Sediment Quality Triad, the International Joint Commission Sediment Assessment Strategy, and the National Status and Trends Program Approach. The various sediment assessment approaches are evaluated for application to the Hanford Reach and recommendations for Hanford Site sediment quality criteria are discussed.

  19. General siting regulation and population distribution criteria for Greece

    International Nuclear Information System (INIS)

    Kollas, J.; Yadigaroglu, G.

    1983-01-01

    A new national regulation for nuclear power plant siting is described. The main body of the regulation is similar in contents to the IAEA Code of Practice in siting, but exceeds its scope in certain areas and covers all aspects of the impact of the plant on the population and the environment of the region, including non-radiological effects. The regulation is accompanied by appendices which refer to site suitability criteria with respect to the radiological consequences from the operational states of the plant and with respect to accidents, including core-melt accidents; these reflect the particular geographic and demographic situation of Greece

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

    International Nuclear Information System (INIS)

    Shord, A.L.

    1979-09-01

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

  1. Early Site Permit Demonstration Program: Regulatory criteria evaluation report

    International Nuclear Information System (INIS)

    1993-03-01

    The primary objective of the ESPDP is to demonstrate successfully the use of 10CFR52 to obtain ESPs for one or more US sites for one (or more) ALWR nuclear power plants. It is anticipated that preparation of the ESP application and interaction with NRC during the application review process will result not only in an ESP for the applicant(s) but also in the development of criteria and definition of processes, setting the precedent that facilitates ESPs for subsequent ESP applications. Because siting regulatory processes and acceptance criteria are contained in over 100 separate documents, comprehensive licensing and technical reviews were performed to establish whether the requirements and documentation are self-consistent, whether the acceptance criteria are sufficiently well-defined and clear, and whether the licensing process leading to the issuance of an ESP is unambiguously specified. The results of the technical and licensing evaluations are presented in this report. The purpose, background, and organization of the ESPDP is delineated in Section 1. Section 11 contains flowcharts defining siting application requirements, environmental report requirements, and emergency planning/preparedness requirements for ALWRS. The licensing and technical review results are presented in Section III

  2. Early Site Permit Demonstration Program: Regulatory criteria evaluation report

    International Nuclear Information System (INIS)

    1993-03-01

    The primary objective of the Early Site Plan Demonstration Program (ESPDP) is to demonstrate successfully the use of 10CFR52 to obtain ESPs for one or more US sites for one (or more) ALWR nuclear power plants. It is anticipated that preparation of the ESP application and interaction with NRC during the application review process will result not only in an ESP for the applicant(s) but also in the development of criteria and definition of processes, setting the precedent that facilitates ESPs for subsequent ESP applications. Because siting regulatory processes and acceptance criteria are contained in over 100 separate documents, comprehensive licensing and technical reviews were performed to establish whether the requirements and documentation are self-consistent, whether the acceptance criteria are sufficiently well-defined and clear, and whether the licensing process leading to the issuance of an ESP is unambiguously specified. This document provides appendices C and D of this report. Appendix C contains data from the licensing and technical reviews; Appendix D contains technology toolkit data sheets

  3. Early Site Permit Demonstration Program: Regulatory criteria evaluation report

    Energy Technology Data Exchange (ETDEWEB)

    1993-03-01

    The primary objective of the ESPDP is to demonstrate successfully the use of 10CFR52 to obtain ESPs for one or more US sites for one (or more) ALWR nuclear power plants. It is anticipated that preparation of the ESP application and interaction with NRC during the application review process will result not only in an ESP for the applicant(s) but also in the development of criteria and definition of processes, setting the precedent that facilitates ESPs for subsequent ESP applications. Because siting regulatory processes and acceptance criteria are contained in over 100 separate documents, comprehensive licensing and technical reviews were performed to establish whether the requirements and documentation are self-consistent, whether the acceptance criteria are sufficiently well-defined and clear, and whether the licensing process leading to the issuance of an ESP is unambiguously specified. The results of the technical and licensing evaluations are presented in this report. The purpose, background, and organization of the ESPDP is delineated in Section 1. Section 11 contains flowcharts defining siting application requirements, environmental report requirements, and emergency planning/preparedness requirements for ALWRS. The licensing and technical review results are presented in Section III.

  4. Use of DOE site selection criteria for screening low-level waste disposal sites on the Oak Ridge Reservation

    International Nuclear Information System (INIS)

    Lee, D.W.; Ketelle, R.H.; Stinton, L.H.

    1983-09-01

    The proposed Department of Energy (DOE) site selection criteria were applied to the Oak Ridge Reservation, and the application was evaluated to determine the criteria's usefulness in the selection of a low-level waste disposal site. The application of the criteria required the development of a methodology to provide a framework for evaluation. The methodology is composed of site screening and site characterization stages. The site screening stage relies on reconnaissance data to identify a preferred site capable of satisfying the site selection criteria. The site characterization stage relies on a detailed site investigation to determine site acceptability. The site selection criteria were applied to the DOE Oak Ridge Reservation through the site screening stage. Results of this application were similar to those of a previous siting study on the Oak Ridge Reservation. The DOE site selection criteria when coupled with the methodology that was developed were easily applied and would be adaptable to any region of interest

  5. Criteria and evaluation of shallow land burial sites

    International Nuclear Information System (INIS)

    Chandra, U.

    1986-01-01

    The criteria for shallow ground disposal of radioactive wastes as developed by Nuclear Regulatory Commission-US and International Atomic Energy Agency are discussed. Emphasis has been given to: elaboration of various basic components of a national Strategy for radioactive waste disposal; development of technical requirements; environmental standards, consensus among scientific community and public confidence. Aspects of site selection, evaluation/characterization and site suitability are dealt with. Some results of characterization of a site for tempory storage of low level solid radioactive wastes in Instituto de Pesquisas Energeticas e Nucleares-IPEN-CNEN/Sao Paulo are described. The methods used for hydrological characterization include use of artificial tritium for unsaturated zone and radioactive tracers like I-131, Cr 51 Cl 3 , Cr 51 EDTA, Br 82 for the saturated zone. (Author) [pt

  6. Criteria and evaluation of shallow land burial sites

    International Nuclear Information System (INIS)

    Chandra, U.

    1987-01-01

    The criteria for shallow ground disposal of radioactive wastes as developed by Nuclear Regulatory Comission-US and International Atomic Energy Agency are discussed. Emphasis has been given to: elaboration of various basic components of a national strategy for radioactive waste disposal; development of technical requirements; environmental standards, consensus among scientific community and public confidence. Aspects of site selection, evaluation/characterization and site suitability are dealt with. Some results of characterization of a site for temporary storage of low level solid radioactive wastes in Instituto de Pesquisas Energeticas e Nucleares - IPEN - CNEN/Sao Paulo are described. The methods used for hydrological characterization include use of artificial tritium for unsaturated zone and radioactive tracers like I - 131, Cr 51 Cl 3 , Cr 51 EDTA, Br 82 for the saturated zone. (Author) [pt

  7. Screening criteria for siting waste management facilities: Regional Management Plan

    International Nuclear Information System (INIS)

    1986-01-01

    The Midwest Interstate Low-Level Radioactive Waste Commission (Midwest Compact) seeks to define and place into operation a system for low-level waste management that will protect the public health and safety and the environment from the time the waste leaves its point of origin. Once the system is defined it will be necessary to find suitable sites for the components of that waste management system. The procedure for siting waste management facilities that have been chosen by the compact is one in which a host state is chosen for each facility. The host state is then given the freedom to select the site. Sites will be needed of low-level waste disposal facilities. Depending on the nature of the waste management system chosen by the host state, sites may also be needed for regional waste treatment facilities, such as compactors or incinerators. This report provides example criteria for use in selecting sites for low-level radioactive waste treatment and disposal facilities. 14 refs

  8. Preliminary siting characterization Salt Disposition Facility - Site B

    International Nuclear Information System (INIS)

    Wyatt, D.

    2000-01-01

    A siting and reconnaissance geotechnical program has been completed in S-Area at the Savannah River Site in South Carolina. This program investigated the subsurface conditions for the area known as ''Salt Disposition Facility (SDF), Site B'' located northeast of H-Area and within the S-Area. Data acquired from the Site B investigation includes both field exploration and laboratory test data

  9. Managing Hanford Site solid waste through strict acceptance criteria

    International Nuclear Information System (INIS)

    Jasen, W.G.; Pierce, R.D.; Willis, N.P.

    1993-02-01

    Various types of waste have been generated during the 50-year history of the Hanford Site. Regulatory changes in the last 20 years have provided the emphasis for better management of these wastes. Interpretations of the Atomic Energy Act of 1954 (AEA) and the Resource Conservation and Recovery Act of 1976 (RCRA) have led to the definition of a group of wastes called radioactive mixed wastes (RMW). As a result of the radioactive and hazardous properties of these wastes, strict management programs have been implemented for the management of these wastes. Solid waste management is accomplished through a systems performance approach to waste management that used best-demonstrated available technology (BDAT) and best management practices. The solid waste program at the Hanford Site strives to integrate all aspects of management relative to the treatment, storage and disposal (TSD) of solid waste. Often there are many competing and important needs. It is a difficult task to balance these needs in a manner that is both equitable and productive. Management science is used to help the process of making decisions. Tools used to support the decision making process include five-year planning, cost estimating, resource allocation, performance assessment, waste volume forecasts, input/output models, and waste acceptance criteria. The purpose of this document is to describe how one of these tools, waste acceptance criteria, has helped the Hanford Site manage solid wastes

  10. OSU TOMF Program Site Selection and Preliminary Concept Design Report

    Energy Technology Data Exchange (ETDEWEB)

    Spadling, Steve [Oklahoma State Univ., Stillwater, OK (United States)

    2012-05-10

    The purpose of this report is to confirm the programmatic requirements for the new facilities, identify the most appropriate project site, and develop preliminary site and building concepts that successfully address the overall project goals and site issues. These new facilities will be designed to accommodate the staff, drivers and maintenance requirements for the future mixed fleet of passenger vehicles, Transit Style Buses and School Buses.

  11. Preliminary environmental site assessments in New York City

    International Nuclear Information System (INIS)

    Lundy, P.; Gasson, D.R.; Longendyke, S.T.

    1991-01-01

    Preliminary Environmental Site Assessments are often performed prior to real estate transactions or refinancing. These assessments are typically performed for real estate buyers, sellers and lending institutions. Undertaking a Preliminary Environmental Site Assessment in New York City can often be quite complex and time-consuming. This is due, in part, to the age and density of buildings in the city as well as the myriad of regulatory agencies with jurisdiction over environmental issues. This paper will discuss how environmental assessments are performed with a special emphasis on building in New York City. In includes hazardous wastes management for Radon, PCB's and asbestos

  12. Geological Storage of CO2. Site Selection Criteria

    International Nuclear Information System (INIS)

    Ruiz, C.; Martinez, R.; Recreo, F.; Prado, P.; Campos, R.; Pelayo, M.; Losa, A. de la; Hurtado, A.; Lomba, L.; Perez del Villar, L.; Ortiz, G.; Sastre, J.; Zapatero, M. A.; Suarez, I.; Arenillas, A.

    2007-01-01

    In year 2002 the Spanish Parliament unanimously passed the ratification of the Kyoto Protocol, signed December 1997, compromising to limiting the greenhouse gas emissions increase. Later on, the Environment Ministry submitted the Spanish National Assignment Emissions Plan to the European Union and in year 2005 the Spanish Greenhouse Gas market started working, establishing taxes to pay in case of exceeding the assigned emissions limits. So, the avoided emissions of CO2 have now an economic value that is promoting new anthropogenic CO2 emissions reduction technologies. Carbon Capture and Storage (CCS) are among these new technological developments for mitigating or eliminate climate change. CO2 can be stored in geological formations such as depleted oil or gas fields, deep permeable saline water saturated formations and unmailable coal seams, among others. This report seeks to establish the selection criteria for suitable geological formations for CO2 storage in the Spanish national territory, paying attention to both the operational and performance requirements of these storage systems. The report presents the physical and chemical properties and performance of CO2 under storage conditions, the transport and reaction processes of both supercritical and gaseous CO2, and CO2 trapping mechanisms in geological formations. The main part of the report is devoted to geological criteria at watershed, site and formation scales. (Author) 100 refs

  13. Geological Storage of CO2. Site Selection Criteria

    International Nuclear Information System (INIS)

    Ruiz, C.; Martinez, R.; Recreo, F.; Prado, P.; Campos, R.; Pelayo, M.; Losa, A. de la; Hurtado, A.; Lomba, L.; Perez del Villar, L.; Ortiz, G.; Sastre, J.

    2006-01-01

    In year 2002 the Spanish Parliament unanimously passed the ratification of the Kyoto Protocol, signed December 1997, compromising to limiting the greenhouse gas emissions increase. Later on, the Environment Ministry submitted the Spanish National Assignment Emissions Plan to the European Union and in year 2005 the Spanish Greenhouse Gas market started working, establishing taxes to pay in case of exceeding the assigned emissions limits. So, the avoided emissions of CO2 have now an economic value that is promoting new anthropogenic CO2 emissions reduction technologies. Carbon Capture and Storage (CCS) are among these new technological developments for mitigating or eliminate climate change. CO2 can be stored in geological formations such as depleted oil or gas fields, deep permeable saline water saturated formations and unmineable coal seams, among others. This report seeks to establish the selection criteria for suitable geological formations for CO2 storage in the Spanish national territory, paying attention to both the operational and performance requirements of these storage systems. The report presents the physical and chemical properties and performance of CO2 under storage conditions, the transport and reaction processes of both supercritical and gaseous CO2, and CO2 trapping mechanisms in geological formations. The main part of the report is devoted to geological criteria at watershed, site and formation scales. (Author) 100 ref

  14. Development of site-specific soil cleanup criteria: New Brunswick Laboratory, New Jersey site

    Energy Technology Data Exchange (ETDEWEB)

    Veluri, V.R.; Moe, H.J.; Robinet, M.J.; Wynveen, R.A.

    1983-03-01

    The potential human exposure which results from the residual soil radioactivity at a decommissioned site is a prime concern during D and D projects. To estimate this exposure, a pathway analysis approach is often used to arrive at the residual soil radioactivity criteria. The development of such a criteria for the decommissioning of the New Brunswick Laboratory, New Jersey site is discussed. Contamination on this site was spotty and located in small soil pockets spread throughout the site area. Less than 1% of the relevant site area was contaminated. The major contaminants encountered at the site were /sup 239/Pu, /sup 241/Am, normal and natural uranium, and natural thorium. During the development of the pathway analysis to determine the site cleanup criteria, corrections for the inhomogeneity of the contamination were made. These correction factors and their effect upon the relevant pathway parameters are presented. Major pathways by which radioactive material may reach an individual are identified and patterns of use are specified (scenario). Each pathway is modeled to estimate the transfer parameters along the given pathway, such as soil to air to man, etc. The transfer parameters are then combined with dose rate conversion factors (ICRP 30 methodology) to obtain soil concentration to dose rate conversion factors (pCi/g/mrem/yr). For an appropriate choice of annual dose equivalent rate, one can then arrive at a value for the residual soil concentration. Pathway modeling, transfer parameters, and dose rate factors for the three major pathways; inhalation, ingestion and external exposure, which are important for the NBL site, are discussed.

  15. Preliminary long-term stability criteria for compressed air energy storage caverns in salt domes

    Energy Technology Data Exchange (ETDEWEB)

    Thoms, R.L.; Martinez, J.D.

    1978-08-01

    Air storage caverns, which are an essential and integral component of a CAES plant, should be designed and operated so as to perform satisfactorily over the intended life of the overall facility. It follows that the long-term ''stability'' of air storage caverns must be considered as a primary concern in projecting the satisfactory operation of CAES facilities. As used in the report, ''stability'' of a storage cavern implies the extent to which an acceptable amount of cavern storage volume can be utilized with routine maintenance for a specified time interval, e.g., 35 years. In this context, cavern stability is relative to both planned utilization and time interval of operation. The objective of the study was to review the existing literature and consult knowledgeable workers in the storage industry, and then report state-of-the-art findings relative to long-term stability of compressed air energy storage caverns in salt domes. Further, preliminary cavern stability criteria were to be presented in a form consistent with the amount of information available on cavern performance in salt domes. Another objective of the study was to outline a methodology for determining the long-term stability of site-specific CAES cavern systems in salt domes.

  16. Preliminary Evaluation of Removing Used Nuclear Fuel from Shutdown Sites

    Energy Technology Data Exchange (ETDEWEB)

    Maheras, Steven J.; Best, Ralph E.; Ross, Steven B.; Buxton, Kenneth A.; England, Jeffery L.; McConnell, Paul E.

    2013-09-30

    This report fulfills the M2 milestone M2FT-13PN0912022, “Stranded Sites De-Inventorying Report.” In January 2013, the U.S. Department of Energy (DOE) issued the Strategy for the Management and Disposal of Used Nuclear Fuel and High-Level Radioactive Waste (DOE 2013). Among the elements contained in this strategy is an initial focus on accepting used nuclear fuel from shutdown reactor sites. This focus is consistent with the recommendations of the Blue Ribbon Commission on America’s Nuclear Future, which identified removal of stranded used nuclear fuel at shutdown sites as a priority so that these sites may be completely decommissioned and put to other beneficial uses (BRC 2012). Shutdown sites are defined as those commercial nuclear power reactor sites where the nuclear power reactors have been shut down and the site has been decommissioned or is undergoing decommissioning. In this report, a preliminary evaluation of removing used nuclear fuel from 12 shutdown sites was conducted. The shutdown sites were Maine Yankee, Yankee Rowe, Connecticut Yankee, Humboldt Bay, Big Rock Point, Rancho Seco, Trojan, La Crosse, Zion, Crystal River, Kewaunee, and San Onofre. These sites have no other operating nuclear power reactors at their sites and have also notified the U.S. Nuclear Regulatory Commission that their reactors have permanently ceased power operations and that nuclear fuel has been permanently removed from their reactor vessels. Shutdown reactors at sites having other operating reactors are not included in this evaluation.

  17. Ranking criteria for assessment of municipal solid waste dumping sites

    Directory of Open Access Journals (Sweden)

    Mahmood Khalid

    2017-03-01

    Full Text Available Priority wise channelization of resources is the key to successful environmental management, especially when funds are limited. The study in hand has successfully developed an algorithmic criterion to compare hazardous effects of Municipal Solid Waste (MSW dumping sites quantitatively. It is a Multi Criteria Analysis (MCA that has made use of the scaling function to normalize the data values, Analytical Hierarchy Process (AHP for assigning weights to input parameters showing their relevant importance, and Weighted Linear Combination (WLC for aggregating the normalized scores. Input parameters have been divided into three classes namely Resident’s Concerns, Groundwater Vulnerability and Surface Facilities. Remote Sensing data and GIS analysis were used to prepare most of the input data. To elaborate the idea, four dumpsites have been chosen as case study, namely Old-FSD, New-FSD, Saggian and Mahmood Booti. The comparison has been made first at class levels and then class scores have been aggregated into environmental normalized index for environmental impact ranking. The hierarchy of goodness found for the selected sites is New-FSD > Old-FSD > Mahmood Booti > Saggian with comparative scores of goodness to environment as 36.67, 28.43, 21.26 and 13.63 respectively. Flexibility of proposed model to adjust any number of classes and parameters in one class will be very helpful for developing world where availability of data is the biggest hurdle in research based environmental sustainability planning. The model can be run even without purchasing satellite data and GIS software, with little inaccuracy, using imagery and measurement tools provided by Google Earth.

  18. Preliminary safety evaluation for the Laxemar subarea. Based on data and site descriptions after the initial site investigation stage

    Energy Technology Data Exchange (ETDEWEB)

    Andersson, Johan [JA Streamflow AB, Aelvsjoe (Sweden)

    2006-03-15

    The main objectives of this Preliminary Safety Evaluation (PSE) of the Laxemar subarea have been to determine, with limited efforts, whether the feasibility study's judgement of the suitability of the candidate area with respect to long-term safety holds up in the light of the actual site investigation data; to provide feedback to continued site investigations and site-specific repository design and to identify site-specific scenarios and geoscientific issues for further analyses. The PSE focuses on comparing the attained knowledge of the sites with the suitability criteria as set out by SKB in 2000. These criteria both concern properties of the site judged to be necessary for safety and engineering (requirements) and properties judged to be beneficial (preferences). The findings are then evaluated in order to provide feedback to continued investigations and design work. The PSE does not aim at comparing sites and does not assess compliance with safety and radiation protection criteria. The latter is eventually done in coming Safety Assessments. This preliminary safety evaluation shows that, according to existing data, the Laxemar subarea meets all safety requirements. The evaluation also shows that the Laxemar subarea meets most of the safety preferences, but for some aspects of the site description further reduction of the uncertainties would enhance the safety case. Despite the stated concerns, there is no reason, from a safety point of view, not to continue the Site Investigations at the Laxemar subarea. There are uncertainties to resolve and the safety would eventually need to be verified through a proper safety assessment. Only some of the uncertainties noted in the Site Descriptive Model have safety implications and need further resolution for this reason. Furthermore, uncertainties may need resolving for other reasons, such as giving an adequate assurance of site understanding or assisting in optimising design. Notably, there are questions about the

  19. Preliminary safety evaluation for the Laxemar subarea. Based on data and site descriptions after the initial site investigation stage

    International Nuclear Information System (INIS)

    Andersson, Johan

    2006-03-01

    The main objectives of this Preliminary Safety Evaluation (PSE) of the Laxemar subarea have been to determine, with limited efforts, whether the feasibility study's judgement of the suitability of the candidate area with respect to long-term safety holds up in the light of the actual site investigation data; to provide feedback to continued site investigations and site-specific repository design and to identify site-specific scenarios and geoscientific issues for further analyses. The PSE focuses on comparing the attained knowledge of the sites with the suitability criteria as set out by SKB in 2000. These criteria both concern properties of the site judged to be necessary for safety and engineering (requirements) and properties judged to be beneficial (preferences). The findings are then evaluated in order to provide feedback to continued investigations and design work. The PSE does not aim at comparing sites and does not assess compliance with safety and radiation protection criteria. The latter is eventually done in coming Safety Assessments. This preliminary safety evaluation shows that, according to existing data, the Laxemar subarea meets all safety requirements. The evaluation also shows that the Laxemar subarea meets most of the safety preferences, but for some aspects of the site description further reduction of the uncertainties would enhance the safety case. Despite the stated concerns, there is no reason, from a safety point of view, not to continue the Site Investigations at the Laxemar subarea. There are uncertainties to resolve and the safety would eventually need to be verified through a proper safety assessment. Only some of the uncertainties noted in the Site Descriptive Model have safety implications and need further resolution for this reason. Furthermore, uncertainties may need resolving for other reasons, such as giving an adequate assurance of site understanding or assisting in optimising design. Notably, there are questions about the

  20. Criteria and results from the analysis of the problem of site selection for the construction of high level RAW repository

    International Nuclear Information System (INIS)

    Evstatiev, D.; Kozhoukharova, D.; Iliev, I.; Karagyuleva, J.

    1993-02-01

    The criteria for preliminary assessment of the Bulgarian territory and the results of the selection of prospective sites for future investigation concerning the choice of the suitable places for RAW repositories are presented. The selection of the prospective terrains has been performed in two stages: 1) Categorization of the country according to the prospective conditions for suitable sites and 2) Distinguishing and preliminary assessment of the suitable sites. The number of these sites was reduced to 20 by the method of successive screening. They are located in Northwest and Southeast Bulgaria and are built of marls, clays, granite, gneiss, serpentine and and volcanic rocks. The selected 20 sites has been subjected to preliminary investigation according to a programme specially worked out for the purpose. The investigation covers the analysis and summing up of the available geographical, geomorphological, geological, seismotectonic, hydrological, climatic, hydrogeological and geotechnical data, as well as a minimum of additional field research and laboratory tests. The results of the investigation of each site are presented and discussed. 1 ref

  1. Preliminary Evaluation of Removing Used Nuclear Fuel from Shutdown Sites

    Energy Technology Data Exchange (ETDEWEB)

    Maheras, Steven J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Best, Ralph E. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Ross, Steven B. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Buxton, Kenneth A. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); England, Jeffery L. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); McConnell, Paul E. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Massaro, Lawrence M. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Jensen, Philip J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

    2015-09-30

    A preliminary evaluation of removing spent nuclear fuel (SNF) from 13 shutdown nuclear power reactor sites was conducted. At these shutdown sites the nuclear power reactors have been permanently shut down and the sites have been decommissioned or are undergoing decommissioning. The shutdown sites were Maine Yankee, Yankee Rowe, Connecticut Yankee, Humboldt Bay, Big Rock Point, Rancho Seco, Trojan, La Crosse, Zion, Crystal River, Kewaunee, San Onofre, and Vermont Yankee. The evaluation was divided into four components: (1) characterization of the SNF and greater-than-Class C low-level radioactive waste (GTCC waste) inventory, (2) a description of the on-site infrastructure and conditions relevant to transportation of SNF and GTCC waste, (3) an evaluation of the near-site transportation infrastructure and experience relevant to shipping transportation casks containing SNF and GTCC waste, including identification of gaps in information, and (4) an evaluation of the actions necessary to prepare for and remove SNF and GTCC waste. Every site was found to have at least one off-site transportation mode option for removing its SNF and GTCC waste; some have multiple options. Experience removing large components during reactor decommissioning provided an important source of information used to identify the transportation mode options for the sites. Especially important in conducting the evaluation were site visits, through which information was obtained that would not have been available otherwise. Extensive photographs taken during the site visits proved to be particularly useful in documenting the current conditions at or near the sites. It is expected that additional site visits will be conducted to add to the information presented in the evaluation.

  2. Environmental Survey preliminary report, Hanford Site, Richland, Washington

    Energy Technology Data Exchange (ETDEWEB)

    1987-08-01

    This report presents the preliminary findings from the first phase of the Environmental Survey of the United States Department of Energy (DOE) Hanford Site, conducted August 18 through September 5, 1986. The Survey is being conducted by an interdisciplinary team of environmental specialists, led and managed by the Office of Environment, Safety and Health's Office of Environmental Audit. Individual team components are being supplied by a private contractor. The objective of the Survey is to identify environmental problems and areas of environmental risk associated with the Hanford Site. The Survey covers all environmental media and all areas of environmental regulation. It is being performed in accordance with the DOE Environmental Survey Manual. This phase of the Survey involves the review of existing site environmental data, observations of the operations carried on at the Hanford Site, and interviews with site personnel. The Survey team developed a Sampling and Analysis Plan to assist in further assessing certain of the environmental problems identified during its on-site activities. The Sampling and Analysis Plan will be executed by a DOE National Laboratory or a support contractor. When completed, the results will be incorporated into the Environmental Survey Interim Report for the Hanford Site. The Interim Report will reflect the final determinations of the Hanford Site Survey. 44 refs., 88 figs., 74 tabs.

  3. Environmental Survey preliminary report, Hanford Site, Richland, Washington

    International Nuclear Information System (INIS)

    1987-08-01

    This report presents the preliminary findings from the first phase of the Environmental Survey of the United States Department of Energy (DOE) Hanford Site, conducted August 18 through September 5, 1986. The Survey is being conducted by an interdisciplinary team of environmental specialists, led and managed by the Office of Environment, Safety and Health's Office of Environmental Audit. Individual team components are being supplied by a private contractor. The objective of the Survey is to identify environmental problems and areas of environmental risk associated with the Hanford Site. The Survey covers all environmental media and all areas of environmental regulation. It is being performed in accordance with the DOE Environmental Survey Manual. This phase of the Survey involves the review of existing site environmental data, observations of the operations carried on at the Hanford Site, and interviews with site personnel. The Survey team developed a Sampling and Analysis Plan to assist in further assessing certain of the environmental problems identified during its on-site activities. The Sampling and Analysis Plan will be executed by a DOE National Laboratory or a support contractor. When completed, the results will be incorporated into the Environmental Survey Interim Report for the Hanford Site. The Interim Report will reflect the final determinations of the Hanford Site Survey. 44 refs., 88 figs., 74 tabs

  4. HWVP compliance with the Hanford site solid waste acceptance criteria

    International Nuclear Information System (INIS)

    Bromm, R.; Ornelas, J.; Fundingsland, S.; Shah, K.

    1993-01-01

    In order to ensure that the Hanford Waste Vitrification Project (HWVP) will meet solid waste acceptance criteria, a review of the criteria was performed. The primary purpose of the study was to evaluate the modifications that will be required to bring the HWVP into compliance for secondary waste which will be generated during normal operations of the facility. To accomplish this objective, the current HWVP design was evaluated based on the criteria established. Once the non-compliance areas and potentially non-compliance areas were identified, alternative plant design modifications were proposed. This paper summarizes the results and recommendations of that study

  5. Workshops for state review of site suitability criteria for high-level radioactive waste repositories: analysis and recommendations

    International Nuclear Information System (INIS)

    1978-02-01

    The purpose of this report is to present the views and recommendations of invited State officials and legislators participating in a workshop concerned with preliminary site suitability criteria for high level radioactive waste repositories. The workshops were open to the public and were conducted by the U. S. Nuclear Regulatory Commission (NRC) during September 1977 in three regional locations across the United States. This contractor report is the second of two reports and consolidates the discussion by State officials on the role of a State in siting a repository, NRC's waste management program, the transportation of high level wastes, the number and location of repositories and concerns with the socio-economic impacts of siting a repository in a community. The recommendations to the NRC can be categorized into four areas. These were: (1) general recommendations, (2) procedural recommendations, (3) recommendations for improving communications, and (4) specific recommendations on the preliminary siting criteria. The recommendations emphasized the need for early State involvement in the siting process, the need for an impacted State to assess repository operations, the need for early solution of waste transportation concerns, and the requirement that any repository developed insure the protection of the public health and safety as its most important characteristic. Other participant recommendations are included in the body of the report

  6. Technical advisory on SSC site criteria and catalog of site information needs

    Energy Technology Data Exchange (ETDEWEB)

    1985-06-15

    The Superconducting Super Collider, or SSC, is a proposed scientific instrument of the study of the fundamental nature of matter. In the SSC two 20-TeV beams of protons will be accelerated and counter circulate on an approximately circular path. The protons will be made to collide at six locations where detectors can be placed to count and measure the products of the collisions. These collisions, twenty times more energetic than in any existing facility, will enable scientists to probe deeper into the heart of matter in the quest for a deeper understanding of the universal forces of nature. The goal of the SSC project is to create a scientific laboratory in high energy physics whose facilities are unique. Ultimately the success of that laboratory will be measured by its scientific discoveries, measurements, interpretations, and innovations. Toward that end the accelerator-collider must be constructed to high standards at minimum cost and maximum effectiveness. Preparations must be made for future operations and a scientific-technical staff attracted and maintained. The chosen site must accommodate all of these factors. This document summarizes siting criteria for the SSC and enumerates site-specific information important to the evaluation of potential sites. This document is not a call for site proposals but a technical report prepared for the information and use of the Department of Energy (DOE).

  7. Recommended criteria for the evaluation of on-site nuclear power plant emergency plans, volume II: criteria

    International Nuclear Information System (INIS)

    1997-01-01

    A critical review of existing Canadian and international nuclear power plant (NPP) emergency plans, evaluation criteria, and approaches has been conducted to provide AECB staff with information which can be used to assess the adequacy of NPP on-site emergency response plans. The results of this work are published in two volumes. Volume I, Basis Document, provides the reasons why certain requirements are in place. It also gives comprehensive references to various standards.Volume II, Criteria, contains the criteria which relate to on-site actions and their integration with control room activities and the roles of off-site responsible organizations. The recommended criteria provide information on what is required, and not on how to accomplish the requirements. The licensees are given the latitude to decide on the methods and processes needed to meet the requirements. The documents do not address NPP off-site plans and response capability, or the control room emergency operating procedures and response capability. This report contains only Volume II: Criteria. 55 refs., 2 tabs., 1 fig

  8. Site characterization criteria (DOE-STD-1022-94) for natural phenomena hazards at DOE sites. Revision 1

    International Nuclear Information System (INIS)

    Chen, J.C.; Ueng, Tzou-Shin; Boissonnade, A.C.

    1995-01-01

    This paper briefly summarizes requirements of site characterization for Natural Phenomena Hazards (NPH) at DOE sites. In order to comply with DOE Order 5480.28, site characterization criteria has been developed to provide site-specific information needed for development of NPH assessment criteria. Appropriate approaches are outlined to ensure that the current state-of-the-art methodologies and procedures are used in the site characterization. General and detailed site characterization requirements are provided in the areas of meteorology, hydrology, geology, seismology and geotechnical studies

  9. Preliminary Evaluation of Removing Used Nuclear Fuel from Shutdown Sites

    Energy Technology Data Exchange (ETDEWEB)

    Maheras, Steven J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Best, Ralph E. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Ross, Steven B. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Buxton, Kenneth A. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); England, Jeffery L. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); McConnell, Paul E. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Massaro, Lawrence M. [Fermi Research Alliance (FRA), Batavia, IL (United States); Jensen, Philip J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

    2016-09-30

    A preliminary evaluation of removing spent nuclear fuel (SNF) from 13 shutdown nuclear power plant sites was performed. At these shutdown sites the nuclear power reactors have been permanently shut down and the sites have been decommissioned or are undergoing decommissioning. The shutdown sites were Maine Yankee, Yankee Rowe, Connecticut Yankee, Humboldt Bay, Big Rock Point, Rancho Seco, Trojan, La Crosse, Zion, Crystal River, Kewaunee, San Onofre, and Vermont Yankee. The evaluation was divided into four components: Characterization of the SNF and greater-than-Class C low-level radioactive waste (GTCC waste) inventory A description of the on-site infrastructure at the shutdown sites An evaluation of the near-site transportation infrastructure and transportation experience at the shutdown sites An evaluation of the actions necessary to prepare for and remove SNF and GTCC waste. The primary sources for the inventory of SNF and GTCC waste were the U.S. Department of Energy (DOE) spent nuclear fuel inventory database, industry publications such as StoreFUEL, and government sources such as the U.S. Nuclear Regulatory Commission. The primary sources for information on the conditions of on-site infrastructure and near-site transportation infrastructure and experience included information collected during site visits, information provided by managers at the shutdown sites, Facility Interface Data Sheets compiled for DOE in 2005, Services Planning Documents prepared for DOE in 1993 and 1994, industry publications such as Radwaste Solutions, and Google Earth. State staff, State Regional Group representatives, a Tribal representative, and a Federal Railroad Administration representative have participated in nine of the shutdown site visits. Every shutdown site was found to have at least one off-site transportation mode option for removing its SNF and GTCC waste; some have multiple options. Experience removing large components during reactor decommissioning provided an

  10. Description of the Northwest hazardous waste site data base and preliminary analysis of site characteristics

    International Nuclear Information System (INIS)

    Woodruff, D.L.; Hartz, K.E.; Triplett, M.B.

    1988-08-01

    The Northwest Hazardous Waste RD and D Center (the Center) conducts research, development, and demonstration (RD and D) activities for hazardous and radioactive mixed-waste technologies applicable to remediating sites in the states of Idaho, Montana, Oregon, and Washington. To properly set priorities for these RD and D activities and to target development efforts it is necessary to understand the nature of the sites requiring remediation. A data base of hazardous waste site characteristics has been constructed to facilitate this analysis. The data base used data from EPA's Region X Comprehensive Environmental Response, Compensation, and Liability Information System (CERCLIS) and from Preliminary Assessment/Site Investigation (PA/SI) forms for sites in Montana. The Center's data base focuses on two sets of sites--those on the National Priorities List (NPL) and other sites that are denoted as ''active'' CERCLIS sites. Active CERCLIS sites are those sites that are undergoing active investigation and analysis. The data base contains information for each site covering site identification and location, type of industry associated with the site, waste categories present (e.g., heavy metals, pesticides, etc.), methods of disposal (e.g., tanks, drums, land, etc.), waste forms (e.g., liquid, solid, etc.), and hazard targets (e.g., surface water, groundwater, etc.). As part of this analysis, the Northwest region was divided into three geographic subregions to identify differences in disposal site characteristics within the Northwest. 2 refs., 18 figs., 5 tabs

  11. Preliminary Evaluation of Removing Used Nuclear Fuel from Shutdown Sites

    Energy Technology Data Exchange (ETDEWEB)

    Maheras, Steven J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Best, Ralph E. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Ross, Steven B. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Buxton, Kenneth A. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); England, Jeffery L. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); McConnell, Paul E. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Massaro, Lawrence M. [Federal Railroad Administration (FRA) (United States); Jensen, Philip J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

    2014-10-01

    This report presents a preliminary evaluation of removing used nuclear fuel (UNF) from 12 shutdown nuclear power plant sites. At these shutdown sites the nuclear power reactors have been permanently shut down and the sites have been decommissioned or are undergoing decommissioning. The shutdown sites are Maine Yankee, Yankee Rowe, Connecticut Yankee, Humboldt Bay, Big Rock Point, Rancho Seco, Trojan, La Crosse, Zion, Crystal River, Kewaunee, and San Onofre. The evaluation was divided into four components: characterization of the UNF and greater-than-Class C low-level radioactive waste (GTCC waste) inventory; a description of the on-site infrastructure and conditions relevant to transportation of UNF and GTCC waste; an evaluation of the near-site transportation infrastructure and experience relevant to shipping transportation casks containing UNF and GTCC waste, including identification of gaps in information; and, an evaluation of the actions necessary to prepare for and remove UNF and GTCC waste. The primary sources for the inventory of UNF and GTCC waste are the U.S. Department of Energy (DOE) RW-859 used nuclear fuel inventory database, industry sources such as StoreFUEL and SpentFUEL, and government sources such as the U.S. Nuclear Regulatory Commission. The primary sources for information on the conditions of site and near-site transportation infrastructure and experience included observations and information collected during visits to the Maine Yankee, Yankee Rowe, Connecticut Yankee, Humboldt Bay, Big Rock Point, Rancho Seco, Trojan, La Crosse, and Zion sites; information provided by managers at the shutdown sites; Facility Interface Data Sheets compiled for DOE in 2005; Services Planning Documents prepared for DOE in 1993 and 1994; industry publications such as Radwaste Solutions; and Google Earth. State and Regional Group representatives, a Tribal representative, and a Federal Railroad Administration representative participated in six of the shutdown site

  12. New Reactor Siting in Finland, Hanhikivi Site in Pyhaejoki - STUK preliminary safety assessment

    International Nuclear Information System (INIS)

    Nevalainen, Janne

    2013-01-01

    STUK has performed a preliminary assessment of the Decision-in-Principle on the Fennovoima application. A variety of factors must be considered in the selection of a site, including effects of the site on the plant design and the effects of the plant on the site environment. These include external hazards, both natural and human-induced. Since this is a new site, an extensive siting process is followed, that can include an EIA. A site survey is performed to identify candidate sites, after investigating a large region and rejecting unsuitable sites. The remaining sites are then screened and compared on the basis of safety and other considerations to select one or more preferred sites. Natural hazards include geology, seismology, hydrology and meteorology. Offshore ice will be a particular hazard for this plant, since the site is on average only 1.5 m above sea level. The design basis earthquake corresponds to a return frequency of 100,000 years, with 50 % confidence. The existing sites in southern Finland used a design peak ground acceleration of 0.1 g with the ground response spectrum maximum at 10 Hz. The candidate sites in northern Finland will require a peak ground acceleration of 0.2 g with the ground response spectrum maximum at 25 Hz

  13. Construction of Basic Evaluation Criteria for Candidate HLW Repository Sites (1)

    International Nuclear Information System (INIS)

    Koh, Yong Kwon; Bae, Dae Seok; Kim, Kyung Su; Kim, Geon Young; Park, Kyung Woo; Ji, Sung Hoon; Ryu, Ji Hun

    2009-08-01

    We constructed the preliminary site assessment system for selection of proper site as high level radioactive disposal repository with consideration of Korean geological characteristics and underground environments. And, site assessment factor and standard as a point of geologic aspect were suggested for decision of candidate radioactive disposal site in Korea. The results can be used to develop the geological information system for assessment of candidate disposal site

  14. Criteria and measurement techniques applicable to residual radioactivity on a decommissioned reactor site

    International Nuclear Information System (INIS)

    Woollam, P.B.

    1988-12-01

    This document summarises the radiological criteria which might be developed to cover the release of a partly decommissioned nuclear reactor site, then looks at the techniques available by which the site could be monitored to assure compliance with these criteria. In particular, the implications of existing levels of radioactive contamination resulting from airburst nuclear weapons tests and the Chernobyl accident are discussed. (author)

  15. Site Characterization and Preliminary Performance Assessment Calculation Applied To JAEA-Horonobe URL Site of Japan

    International Nuclear Information System (INIS)

    Lim, Doo Hyun; Hatanaka, Koichiro; Ishii, Eiichi

    2010-01-01

    JAEA-Horonobe Underground Research Laboratory (URL) is designed for research and development on high-level radioactive waste (HLW) repository in sedimentary rock. For a potential HLW repository, understanding and implementing fracturing and faulting system, with data from the site characterization, into the performance assessment is essential because fracture and fault will be the major conductors or barriers for the groundwater flow and radionuclide release. The objectives are i) quantitative derivation of characteristics and correlation of fracturing/faulting system with geologic and geophysics data obtained from the site characterization, and ii) preliminary performance assessment calculation with characterized site information

  16. Site Characterization and Preliminary Performance Assessment Calculation Applied To JAEA-Horonobe URL Site of Japan

    Energy Technology Data Exchange (ETDEWEB)

    Lim, Doo Hyun [NE Union Hill Road, Suite 200, WA 98052 (United States); Hatanaka, Koichiro; Ishii, Eiichi [Japan Atomic Energy Agency, Hokkaido (Japan)

    2010-10-15

    JAEA-Horonobe Underground Research Laboratory (URL) is designed for research and development on high-level radioactive waste (HLW) repository in sedimentary rock. For a potential HLW repository, understanding and implementing fracturing and faulting system, with data from the site characterization, into the performance assessment is essential because fracture and fault will be the major conductors or barriers for the groundwater flow and radionuclide release. The objectives are i) quantitative derivation of characteristics and correlation of fracturing/faulting system with geologic and geophysics data obtained from the site characterization, and ii) preliminary performance assessment calculation with characterized site information

  17. Site selection criteria for the shallow land burial of low-level radioactive waste

    International Nuclear Information System (INIS)

    Falconer, K.L.; Hull, L.C.; Mizell, S.A.

    The shallow land burial of low-level waste must be accomplished in a manner that ensures the public and biosphere are protected from harmful amounts of radiation. This can be attained by selecting, designing, operating and closing sites such that contaminants never leave the site boundary in levels above regulatory limits. Site design, operation and closure are all functions of the characteristics of the site selected. As a result, the site selection process offers the most effective means for optimizing safe, efficient and economical low-level waste burial practices. The purpose of this document is to set forth criteria for the selection of shallow land burial sites. Criteria are standard rules, by which the ability of a site to meet waste management goals can be judged. They are comprehensive, universal, and qualitative and are applicable in any geologic environment. Site selection criteria provide the framework for the siting process

  18. Preliminary evaluation of 30 potential granitic rock sites for a radioactive waste storage facility in southern Nevada

    Energy Technology Data Exchange (ETDEWEB)

    Boardman, C.R.; Knutson, C.F.

    1978-02-15

    Results of preliminary study are presented which was performed under subtask 2.7 of the NTS Terminal Waste Storage Program Plan for 1978. Subtask 2.7 examines the feasibility of locating a nuclear waste repository in a granitic stock or pluton in southern Nevada near the Nevada Test Site (NTS). It is assumed for the purposes of this study that such a repository cannot be located at NTS. This assumption may or may not be correct. This preliminary report does not identify a particular site as being a suitable location for a repository. Nor does it absolutely eliminate a particular site from further consideration. It does, however, answer the basic question of probable suitability of some of the sites and present a systematic method for site evaluation. Since the findings of this initial study have been favorable, it will be followed by more exhaustive and detailed studies of the original 30 sites and perhaps others. In future studies some of the evaluation criteria used in the preliminary study may be modified or eliminated, and new criteria may be introduced.

  19. Preliminary evaluation of 30 potential granitic rock sites for a radioactive waste storage facility in southern Nevada

    International Nuclear Information System (INIS)

    Boardman, C.R.; Knutson, C.F.

    1978-01-01

    Results of preliminary study are presented which was performed under subtask 2.7 of the NTS Terminal Waste Storage Program Plan for 1978. Subtask 2.7 examines the feasibility of locating a nuclear waste repository in a granitic stock or pluton in southern Nevada near the Nevada Test Site (NTS). It is assumed for the purposes of this study that such a repository cannot be located at NTS. This assumption may or may not be correct. This preliminary report does not identify a particular site as being a suitable location for a repository. Nor does it absolutely eliminate a particular site from further consideration. It does, however, answer the basic question of probable suitability of some of the sites and present a systematic method for site evaluation. Since the findings of this initial study have been favorable, it will be followed by more exhaustive and detailed studies of the original 30 sites and perhaps others. In future studies some of the evaluation criteria used in the preliminary study may be modified or eliminated, and new criteria may be introduced

  20. Preliminary evaluation of the seismic hazard at Cernavoda NPP site

    International Nuclear Information System (INIS)

    Mingiuc, C.; Serban, V.; Androne, M.

    2001-01-01

    The probabilistic seismic hazard analysis (PSHA) is a methodology by which one evaluates the probability of exceeding different parameters of the ground motions (the maximum ground acceleration - PGA and the ground response spectrum - SA) as effect of the seismic action, on a given site at a future time moment. Due to the large uncertainties in the geological, geophysical, seismological input data, as well as, in the models utilised, various interpretation schemes are applied in the PSHA analyses. This interpretation schemes lead to opinion discrepancies among specialists which finally lead to disagreements in estimating the values of the seismic design for a given site. In order to re-evaluate the methodology and to improve the PSHA result stability, U.S. Nuclear Regulatory Commission (NRC), U.S. Department of Energy (DOE) and Electric Power Research Institute (EPRI) sponsored a project for defining methodological guides of performing PSHA analyses. The project was implemented by a panel of 7 experts, the Senior Seismic Hazard Analysis Committee - SSHAC. This paper presents a preliminary evaluation of the seismic hazard for the Cernavoda NPP site by application of the methodology mentioned, by taking into account the possible sources which could affect the site (the Vrancea focus, Galati - Tulcea fault, Sabla - Dulovo fault and local earthquakes)

  1. Environmental Survey preliminary report, Nevada Test Site, Mercury, Nevada

    International Nuclear Information System (INIS)

    1988-04-01

    This report presents the preliminary findings from the first phase of the Environmental Survey of the United States Department of Energy (DOE) Nevada Test Site (NTS), conducted June 22 through July 10, 1987. The Survey is being conducted by a multidisciplinary team of environmental specialists led and managed by the Office of Environment, Safety and Health's Office of Environmental Audit. Individual team members are outside experts being supplied by a private contractor. The objective of the Survey is to identify environmental problems and areas of environmental risk associated with the NTS. The Survey covers all environment media and all areas of environmental regulation. It is being performed in accordance with the DOE Environmental Survey Manual. This phase of the Survey involves the review of existing site environmental data, observations of the operations and activities performed at the NTS, and interviews with site personnel. The Survey team developed a Sampling and Analysis Plan to assist in further assessing certain environmental problems identified during its on-site activities. The Sampling and Analysis Plan is being executed by the Battelle Columbus Division under contract with DOE. When completed, the results will be incorporated into the NTS Environmental Survey Interim Report. The Interim Report will reflect the final determinations of the NTS Survey. 165 refs., 42 figs., 52 tabs

  2. Environmental Survey preliminary report, Nevada Test Site, Mercury, Nevada

    Energy Technology Data Exchange (ETDEWEB)

    1988-04-01

    This report presents the preliminary findings from the first phase of the Environmental Survey of the United States Department of Energy (DOE) Nevada Test Site (NTS), conducted June 22 through July 10, 1987. The Survey is being conducted by a multidisciplinary team of environmental specialists led and managed by the Office of Environment, Safety and Health's Office of Environmental Audit. Individual team members are outside experts being supplied by a private contractor. The objective of the Survey is to identify environmental problems and areas of environmental risk associated with the NTS. The Survey covers all environment media and all areas of environmental regulation. It is being performed in accordance with the DOE Environmental Survey Manual. This phase of the Survey involves the review of existing site environmental data, observations of the operations and activities performed at the NTS, and interviews with site personnel. The Survey team developed a Sampling and Analysis Plan to assist in further assessing certain environmental problems identified during its on-site activities. The Sampling and Analysis Plan is being executed by the Battelle Columbus Division under contract with DOE. When completed, the results will be incorporated into the NTS Environmental Survey Interim Report. The Interim Report will reflect the final determinations of the NTS Survey. 165 refs., 42 figs., 52 tabs.

  3. Preliminary site design for the SP-100 ground engineering test

    International Nuclear Information System (INIS)

    Cox, C.M.; Miller, W.C.; Mahaffey, M.K.

    1986-04-01

    In November, 1985, Hanford was selected by the Department of Energy (DOE) as the preferred site for a full-scale test of the integrated nuclear subsystem for SP-100. The Hanford Engineering Development Laboratory, operated by Westinghouse Hanford Company, was assigned as the lead contractor for the Test Site. The nuclear subsystem, which includes the reactor and its primary heat transport system, will be provided by the System Developer, another contractor to be selected by DOE in late FY-1986. In addition to reactor operations, test site responsibilities include preparation of the facility plus design, procurement and installation of a vacuum chamber to house the reactor, a secondary heat transport system to dispose of the reactor heat, a facility control system, and postirradiation examination. At the conclusion of the test program, waste disposal and facility decommissioning are required. The test site must also prepare appropriate environmental and safety evaluations. This paper summarizes the preliminary design requirements, the status of design, and plans to achieve full power operation of the test reactor in September, 1990

  4. Preliminary Mark-18A (Mk-18A) Target Material Recovery Program Product Acceptance Criteria

    Energy Technology Data Exchange (ETDEWEB)

    Robinson, Sharon M. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Patton, Bradley D. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

    2016-09-01

    The Mk-18A Target Material Recovery Program (MTMRP) was established in 2015 to preserve the unique materials, e.g. 244Pu, in 65 previously irradiated Mk-18A targets for future use. This program utilizes existing capabilities at SRS and Savannah River National Laboratory (SRNL) to process targets, recover materials from them, and to package the recovered materials for shipping to ORNL. It also utilizes existing capabilities at ORNL to receive and store the recovered materials, and to provide any additional processing of the recovered materials or residuals required to prepare them for future beneficial use. The MTMRP is presently preparing for the processing of these valuable targets which is expected to begin in ~2019. As part of the preparations for operations, this report documents the preliminary acceptance criteria for the plutonium and heavy curium materials to be recovered from the Mk-18A targets at SRNL for transport and storage at ORNL. These acceptance criteria were developed based on preliminary concepts developed for processing, transporting, and storing the recovered Mk-18A materials. They will need to be refined as these concepts are developed in more detail.

  5. Preliminary Mark-18A (Mk-18A) Target Material Recovery Program Product Acceptance Criteria

    International Nuclear Information System (INIS)

    Robinson, Sharon M.; Patton, Bradley D.

    2016-01-01

    The Mk-18A Target Material Recovery Program (MTMRP) was established in 2015 to preserve the unique materials, e.g. 244 Pu, in 65 previously irradiated Mk-18A targets for future use. This program utilizes existing capabilities at SRS and Savannah River National Laboratory (SRNL) to process targets, recover materials from them, and to package the recovered materials for shipping to ORNL. It also utilizes existing capabilities at ORNL to receive and store the recovered materials, and to provide any additional processing of the recovered materials or residuals required to prepare them for future beneficial use. The MTMRP is presently preparing for the processing of these valuable targets which is expected to begin in ~2019. As part of the preparations for operations, this report documents the preliminary acceptance criteria for the plutonium and heavy curium materials to be recovered from the Mk-18A targets at SRNL for transport and storage at ORNL. These acceptance criteria were developed based on preliminary concepts developed for processing, transporting, and storing the recovered Mk-18A materials. They will need to be refined as these concepts are developed in more detail.

  6. Performance allocation traceable to regulatory criteria as applied to site characterization work at the Basalt Waste Isolation Project

    International Nuclear Information System (INIS)

    Deju, R.A.; Babad, H.; Bensky, M.S.; Jacobs, G.K.

    1983-01-01

    The Basalt Waste Isolation Project has developed a method for defining in detail the work required to demonstrate the feasibility of emplacing and providing for the safe isolation of nuclear wastes in a repository in the deep basalts at the Hanford Site near Richland, Washington. Criteria analysis allows the identification of areas of significant technical uncertainty or controversy that can be highlighted as issues. A preliminary analysis has been conducted, which, by identifying key radionuclides and allocating performance among the multiple barriers in a repository constructed in a basalt, allows the design and development testing activities at the Basalt Waste Isolation Project to be put into perspective. Application of sophisticated uncertainty analysis techniques will allow refinements in the analysis to be made and to further guide characterization and testing activities. Preliminary results suggest that a repository constructed in basalt will provide for the safe isolation of nuclear wastes in a cost-effective and reliable manner with a high degree of confidence

  7. Basic principles and criteria on radioactive waste disposal sites

    International Nuclear Information System (INIS)

    Dlouhy, Z.; Kropikova, S.

    1980-01-01

    The basic principles are stated of radiation protection of the workers at radioactive waste disposal facilities, which must be observed in the choice of radioactive waste disposal sites. The emergency programme, the operating regulations and the safety report are specified. Workplace safety regulations are cited. (author)

  8. Appropriate User Acceptance Criteria For New Social Media Sites

    OpenAIRE

    Mirsat Yeşiltepe

    2016-01-01

    Nowadays social media sites have attracted many of users and they have become the mostly commonly used websites for public. These websites are used by individuals, small and even big organizations for various purposes, such as meeting your old friends, sharing your own experiences, sharing pictures and videos, promoting businesses, sharing knowledge etc. Their popularity is increasing at an increasing rate. User’s needs are endless so there will be some new area for creating...

  9. Safety criteria for siting a nuclear power plant

    International Nuclear Information System (INIS)

    2001-01-01

    The guide sets forth requirements for safety of the population and the environment in nuclear power plant siting. It also sets out the general basis for procedures employed by other competent authorities when they issue regulations or grant licences. On request STUK (Radiation and Nuclear Safety Authority of Finland) issues case-specific statements about matters relating to planning and about other matters relating to land use in the environment of nuclear power plants

  10. Engineering study of generic site criteria for selected DOE plutonium facilities

    International Nuclear Information System (INIS)

    Kingsbury, R.J.; Greenwood, J.M.; Sandoval, M.D.

    1980-09-01

    The objectives of this study were to identify criteria that would be applied to selection of a site for plutonium facilities such as those at the Rocky Flats Plant, to establish the relative importance of these criteria, and to identify suitable areas within the United States for location of plutonium facilities with respect to these criteria. Sources of the site criteria identified include federal laws, federal agency regulations, state laws and regulations, and requirements associated with operations to be performed at the site. The criteria identified during the study were organized into 14 major categories. The relative importnace of each category and each criterion within the categories were established using group decision-making techniques. The major criteria categories, their assigned weight on a scale of 1 to 10, and their relative priority ranks are as follows: geology/seismicity; public safety; environmental impact; meteorology; hydrology; topography; transportation; utilities; personnel; safeguards/security; land area and availability; land use compatibility; and, public acceptance. A suitability analysis of the continental United States was performed using only those criteria that could be mapped at a national scale. Suitability was assessed with respect to each of these criteria, and individual suitability maps were prepared. A composite suitability map was generated using computerized overlay techniques. This map provides a starting point for identifying specific candidate sites if an actual site selection were to be conducted

  11. Criteria for prioritization of sites and determining upgrades

    International Nuclear Information System (INIS)

    Ek, David

    2001-01-01

    Full text: Several factors influence the decision to provide physical protection assistance. These factors include the relative attractiveness of the material with respect to nuclear proliferation, the state of the current physical protection system, and the financial resources available to the member state to support the physical protection system. However, identifying, collecting, and evaluating this information from which to make decisions is not a straightforward task. It requires that a relationship and forum be established through which physical protection system information can be shared. Once there is agreement on the need to share PPS information, a more formal evaluation of the effectiveness of the existing system can be performed. The evaluation should be conducted using performance-based criteria as well as INFCIRC/225/Rev. 4 recommendations. The evaluation should take into consideration the material to be protected, the state's design basis threat, and the ability of the existing security system to detect, assess, delay, and respond to an attack by adversaries. A limited review of the internal threat to material should also be performed to ensure appropriate measures are in place to protect material. Analysis tools for this evaluation would include limited computer models, tabletop timeline assessments, and subject matter expert review of specific elements of the protection system. Once the effectiveness of an security system is understood, recommendations for specific upgrades can be discussed with the member state to determine the most viable improvements to the system considering issues such as operational needs, cost, potential reduction in risk to material, and sustainability of the system in future years. To date, the primary mechanism in place for establishing a relationship and forum of information exchange has been the IAEA IPPAS program and other US Bilateral agreements with respect to US origin material. The experience gained through these

  12. Nevada Test Site waste acceptance criteria [Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    None

    1997-08-01

    Revision one updates the requirements, terms, and conditions under which the Nevada Test Site (NTS) will accept low-level radioactive and mixed waste for disposal; and transuranic and transuranic mixed waste for interim storage at the NTS. Review each section of this document. This document is not intended to include all of the requirements; rather, it is meant as a guide toward meeting the regulations. All references in this document should be observed to avoid omission of requirements on which acceptance or rejection of waste will be based. The Department of Energy/Nevada Operations Office (DOE/NV) and support contractors are available to assist you in understanding or interpreting this document.

  13. Nevada Test Site waste acceptance criteria [Revision 1

    International Nuclear Information System (INIS)

    None

    1997-01-01

    Revision one updates the requirements, terms, and conditions under which the Nevada Test Site (NTS) will accept low-level radioactive and mixed waste for disposal; and transuranic and transuranic mixed waste for interim storage at the NTS. Review each section of this document. This document is not intended to include all of the requirements; rather, it is meant as a guide toward meeting the regulations. All references in this document should be observed to avoid omission of requirements on which acceptance or rejection of waste will be based. The Department of Energy/Nevada Operations Office (DOE/NV) and support contractors are available to assist you in understanding or interpreting this document

  14. Nevada test site defense waste acceptance criteria, certification, and transfer requirements

    International Nuclear Information System (INIS)

    1988-10-01

    The Nevada Test Site (NTS) Defense Waste Acceptance Criteria, Certification and Transfer Requirements establishes procedures and criteria for safe transfer, disposal, and storage of defense transuranic, low-level, and mixed waste at the NTS. Included are an overview of the NTS defense waste management program; the NTS waste acceptance criteria for transuranic, low-level, and mixed wastes; waste certification requirements and guidance; application to submit waste; and requirements for waste transfer and receipt. 5 figs., 16 tabs

  15. Minutes of the workshop on off-site release criteria for contaminated materials

    International Nuclear Information System (INIS)

    Singh, S.P.N.

    1989-11-01

    A one and one-half-day workshop was held May 2-3, 1989, at the Pollard Auditorium in Oak Ridge, Tennessee, with the objective of formulating a strategy for developing reasonable and uniform criteria for releasing radioactively contaminated materials from the US Department of Energy (DOE) sites. This report contains the minutes of the workshop. At the conclusion of the workshop, a plan was formulated to facilitate the development of the above-mentioned off-site release criteria

  16. Workshops for state review of site suitability criteria for high-level radioactive waste repositories. Discussion Group reports

    International Nuclear Information System (INIS)

    1977-10-01

    The NRC Waste Management Program and the Office of State Programs held three regional workshops to solicit ideas from State executives and legislators on the siting and licensing procedures for high level waste repositories and to solicit comments on the NRC preliminary site suitability criteria. The workshops were held in Denver, Colorado; New Orleans, Louisiana; and Philadelphia, Pennsylvania during the period 19-30 September 1977. The reports from these workshops are contained herein. The workshops were attended by 170 invited State executives and legislators from 46 states. In addition, there were over 80 observers from diverse backgrounds including the general public, government, industry, professional consultants and university faculty. The workshops were announced in the Federal Register on September 1, 1977

  17. Preliminary safety evaluation, based on initial site investigation data. Planning document

    International Nuclear Information System (INIS)

    Hedin, Allan

    2002-12-01

    This report is a planning document for the preliminary safety evaluations (PSE) to be carried out at the end of the initial stage of SKBs ongoing site investigations for a deep repository for spent nuclear fuel. The main purposes of the evaluations are to determine whether earlier judgements of the suitability of the candidate area for a deep repository with respect to long-term safety holds up in the light of borehole data and to provide feed-back to continued site investigations and site specific repository design. The preliminary safety evaluations will be carried out by a safety assessment group, based on a site model, being part of a site description, provided by a site modelling group and a repository layout within that model suggested by a repository engineering group. The site model contains the geometric features of the site as well as properties of the host rock. Several alternative interpretations of the site data will likely be suggested. Also the biosphere is included in the site model. A first task for the PSE will be to compare the rock properties described in the site model to previously established criteria for a suitable host rock. This report gives an example of such a comparison. In order to provide more detailed feedback, a number of thermal, hydrological, mechanical and chemical analyses of the site will also be included in the evaluation. The selection of analyses is derived from the set of geosphere and biosphere analyses preliminarily planned for the comprehensive safety assessment named SR-SITE, which will be based on a complete site investigation. The selection is dictated primarily by the expected feedback to continued site investigations and by the availability of data after the PSE. The repository engineering group will consider several safety related factors in suggesting a repository layout: Thermal calculations will be made to determine a minimum distance between canisters avoiding canister surface temperatures above 100 deg C

  18. Preliminary Hydrogeochemical Site Description SFR (version 0.2)

    Energy Technology Data Exchange (ETDEWEB)

    Nilsson, Ann-Chatrin (Geosigma AB, Uppaala (Sweden)); Tullborg, Eva-Lena (Terralogica AB, Graabo (Sweden)); Smellie, John (Conterra AB, Partille (Sweden))

    2010-05-15

    The final repository for low and intermediate level radioactive operational waste, SFR, located about 150 km north of Stockholm, is to undergo a future extension. The present on-going project, scheduled from 2007 to 2011, is to define and characterise a suitable bedrock volume for the extended repository. This will include the drilling and geoscientific evaluation of seven core-drilled and four percussion boreholes as well as subsequent interpretation and modelling based on the obtained results in order to provide the necessary information for safety assessment and repository design. This report presents a preliminary hydrogeochemical site description for the SFR site and should be considered as an early progress report rather than a complete hydrochemical site descriptive model. The completed hydrogeochemical field investigations have yielded chemical data from a total of 12 borehole sections in five boreholes and additional data from the entire length of two open boreholes in connection with hydraulic tests. These data, together with data from a total of 18 early boreholes in the present SFR tunnel system, were used in the interpretation work. The main part of the data consisted of basic groundwater analyses including major ions and isotopes. Some sporadic gas, microbe and measured redox data are available, but these are either not treated in this report, or are only briefly discussed. This was due to time constraints since special care is needed when interpreting few data of varying quality. The groundwaters in the SFR dataset cover a maximum depth down to about .400 masl and represent a relatively limited salinity range (1,500 to 5,500 mg/L chloride). However, the delta18O values show a wide variation (-1.55 to -0.75% V-SMOW) similar to that reported from the Forsmark site investigations. At the SFR, marine indicators such as Mg/Cl, K/Cl and Br/Cl also show relatively large variations considering the limited salinity range. From very few measured Eh values, and

  19. Preliminary Hydrogeochemical Site Description SFR (version 0.2)

    International Nuclear Information System (INIS)

    Nilsson, Ann-Chatrin; Tullborg, Eva-Lena; Smellie, John

    2010-05-01

    The final repository for low and intermediate level radioactive operational waste, SFR, located about 150 km north of Stockholm, is to undergo a future extension. The present on-going project, scheduled from 2007 to 2011, is to define and characterise a suitable bedrock volume for the extended repository. This will include the drilling and geoscientific evaluation of seven core-drilled and four percussion boreholes as well as subsequent interpretation and modelling based on the obtained results in order to provide the necessary information for safety assessment and repository design. This report presents a preliminary hydrogeochemical site description for the SFR site and should be considered as an early progress report rather than a complete hydrochemical site descriptive model. The completed hydrogeochemical field investigations have yielded chemical data from a total of 12 borehole sections in five boreholes and additional data from the entire length of two open boreholes in connection with hydraulic tests. These data, together with data from a total of 18 early boreholes in the present SFR tunnel system, were used in the interpretation work. The main part of the data consisted of basic groundwater analyses including major ions and isotopes. Some sporadic gas, microbe and measured redox data are available, but these are either not treated in this report, or are only briefly discussed. This was due to time constraints since special care is needed when interpreting few data of varying quality. The groundwaters in the SFR dataset cover a maximum depth down to about .400 masl and represent a relatively limited salinity range (1,500 to 5,500 mg/L chloride). However, the δ 18 O values show a wide variation (-1.55 to -0.75% V-SMOW) similar to that reported from the Forsmark site investigations. At the SFR, marine indicators such as Mg/Cl, K/Cl and Br/Cl also show relatively large variations considering the limited salinity range. From very few measured Eh values, and

  20. Site study plan for cultural resources, Deaf Smith County site, Texas: Environmental Field Program: Preliminary draft

    International Nuclear Information System (INIS)

    1987-06-01

    The Cultural Resources Site Study Plan describes a field program to identify and evaluate the archaeological, historical, and Native American Indian resources of the site on local and regional perspectives; monitor and manage discovered cultural resources; and establish a worker education program. The archaeological field program consists of three pedestrian surveys: Survey 1 includes two EDBH seismic survey lines and the area within the exploratory shaft facility (ESF); Survey 2 includes the remainder of the site plus a 1/4 to 3/4-mi border area; and Survey 3 includes an assortment of offsite areas. The historical studies will identify and evaluate known and discovered historical sites and structures and the Native American Indian will identify and evaluate cultural and religious concerns expressed by Indian tribal groups. Prehistoric and historic sites will be evaluated to determine if they meet eligibility criteria for listing on the National Register of Historic Places. This site study plan describes the need for each study; its design and design rationale; analysis, management, and use of data; schedule of field activities; organization of field personnel and sample management; and quality assurance requirements. The cultural resource studies will provide data for satisfying the Programmatic Agreement, engineering design needs, and SRP requirements for permits and approvals, and for minimizing effects to any cultural properties discovered during site characterization. 75 refs., 10 figs., 2 tabs

  1. Preliminary site description Forsmark area - version 1.1

    International Nuclear Information System (INIS)

    2004-03-01

    This report presents the interim version (model version 1.1) of the preliminary Site Descriptive Model for Forsmark. The basis for this interim version is quality-assured, geoscientific and ecological field data from Forsmark that were available in the SKB databases SICADA and GIS at April 30, 2003 as well as version 0 of the Site Descriptive Model. The new data acquired during the initial site investigation phase to the date of data freeze 1.1 constitute the basis for the updating of version 0 to version 1.1. These data originate from surface investigations on the candidate area with its regional environment and from drilling and investigations in boreholes. The surface-based data sets were rather extensive whereas the data sets from boreholes were limited to information from one 1,000 m deep cored borehole (KFM01A) and eight 150 to 200 m deep percussion-drilled boreholes in the Forsmark candidate area. Discipline specific models are developed for a selected regional and local model volume and these are then integrated into a site description. The current methodologies for developing the discipline specific models and the integration of these are documented in methodology reports or strategy reports. In the present work, the guidelines given in those reports were followed to the extent possible with the data and information available at the time for data freeze for model version 1.1. Compared with version 0 there are considerable additional features in the version 1.1, especially in the geological description and in the description of the near surface. The geological models of lithology and deformation zones are based on borehole information and much higher resolution surface data. The existence of highly fractured sub-horizontal zones has been verified and these are now part of the model of the deformation zones. A discrete fracture network (DFN) model has also been developed. The rock mechanics model is based on strength information from SFR and an empirical

  2. Nevada Test Site Waste Acceptance Criteria (NTSWAC), Rev. 7-01

    Energy Technology Data Exchange (ETDEWEB)

    NSTec Environmental Management

    2009-05-01

    This document establishes the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office, Nevada Test Site Waste Acceptance Criteria (NTSWAC). The NTSWAC provides the requirements, terms, and conditions under which the Nevada Test Site (NTS) will accept low-level radioactive waste and mixed low-level waste for disposal. The NTSWAC includes requirements for the generator waste certification program, characterization, traceability, waste form, packaging, and transfer. The criteria apply to radioactive waste received at the NTS Area 3 and Area 5 Radioactive Waste Management Complex for disposal.

  3. Nevada Test Site Waste Acceptance Criteria (NTSWAC), Rev. 7-01

    International Nuclear Information System (INIS)

    2009-01-01

    This document establishes the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office, Nevada Test Site Waste Acceptance Criteria (NTSWAC). The NTSWAC provides the requirements, terms, and conditions under which the Nevada Test Site (NTS) will accept low-level radioactive waste and mixed low-level waste for disposal. The NTSWAC includes requirements for the generator waste certification program, characterization, traceability, waste form, packaging, and transfer. The criteria apply to radioactive waste received at the NTS Area 3 and Area 5 Radioactive Waste Management Complex for disposal.

  4. Preliminary site characterization at Beishan northwest China-A potential site for China's high-level radioactive waste repository

    International Nuclear Information System (INIS)

    Wang Ju; Su Rui; Xue Weiming; Zheng Hualing

    2004-01-01

    Chinese nuclear power plants,radioactive waste and radioactive waste disposal are introduced. Beishan region (Gansu province,Northwest China)for high-level radioactive waste repository and preliminary site characterization are also introduced. (Zhang chao)

  5. Preliminary site description. Simpevarp area - version 1.1

    International Nuclear Information System (INIS)

    Winberg, Anders

    2004-08-01

    Site characterisation in the Oskarshamn area is currently conducted at two adjoining localities, the Simpevarp and Laxemar subareas. This report presents the interim version (model version Simpevarp 1.1 of S1.1 for short) of the preliminary Site Descriptive Model for the Simpevarp subarea. The basis for this interim version is quality-assured, geoscientific and ecological field data from the Simpevarp subarea (and in part from the Laxemar area) available in the SKB SICADA and GIS data bases as of July 1, 2003 as well as version 0 of the Site Descriptive Model. The new data collected during the initial site investigation phase up till the date of data freeze S1.1 constitute the basis for the update of version 0 to version S1.1. These data include results from surface investigations in the subarea with its regional environment and from drillings and investigations in boreholes. The surface-based data sets were, in a relative sense, extensive compared with data sets from boreholes, were the information largely was limited to information from one c. 1,000 m deep cored borehole (KSH01A), two existing cored boreholes and three c. 200 m deep percussion-drilled boreholes. Discipline-specific models are developed for the selected regional and local model volumes and these models are subsequently integrated into a unified site description. The current methodologies for developing discipline-specific models and their integration are documented in methodology/ strategy reports. In the present work, the procedures and guidelines given in those reports were followed to the extent possible given the data and information available at the time of data freeze for model version S1.1. Compared with version 0 there are considerable additional features in the version S1.1, especially in the geological description and in the description of the near surface. The geological models of lithology and deformation zones are based on borehole information and surface data of much higher

  6. Criteria for the siting, construction, management and evaluation of low and intermediate activity radioactive waste stores

    International Nuclear Information System (INIS)

    Granero, J.J.

    1986-01-01

    The experience acquired by Spain for the storage of low and intermediate level radioactive wastes, is presented. General considerations related to the technology, financing, administrative measures and risk determination are done. The criteria of site selection for construction and management of the waste storage facility are described, evaluating the specific criteria for the licensing procedure, and taking in account the safety and the radiation protection during periods of the system operation. (M.C.K.) [pt

  7. Siting criteria based on the prevention of deterministic effects from plutonium inhalation exposures

    International Nuclear Information System (INIS)

    Sorensen, S.A.; Low, J.O.

    1998-01-01

    Siting criteria are established by regulatory authorities to evaluate potential accident scenarios associated with proposed nuclear facilities. The 0.25 Sv (25 rem) siting criteria adopted in the United States has been historically based on the prevention of deterministic effects from acute, whole-body exposures. The Department of Energy has extended the applicability of this criterion to radionuclides that deliver chronic, organ-specific irradiation through the specification of a 0.25 Sv (25 rem) committed effective dose equivalent siting criterion. A methodology is developed to determine siting criteria based on the prevention of deterministic effects from inhalation intakes of radionuclides which deliver chronic, organ-specific irradiation. Revised siting criteria, expressed in terms of committed effective dose equivalent, are proposed for nuclear facilities that handle primarily plutonium compounds. The analysis determined that a siting criterion of 1.2 Sv (120 rem) committed effective dose equivalent for inhalation exposures to weapons-grade plutonium meets the historical goal of preventing deterministic effects during a facility accident scenario. The criterion also meets the Nuclear Regulatory Commission and Department of Energy Nuclear Safety Goals provided that the frequency of the accident is sufficiently low

  8. Preliminary safety evaluation for the Simpevarp subarea. Based on data and site descriptions after the initial site investigation stage

    International Nuclear Information System (INIS)

    2005-04-01

    The main objectives of this Preliminary safety evaluation (PSE) of the Simpevarp subarea are: to determine, whether the feasibility study's judgement of the suitability of the candidate area with respect to long-term safety holds up in the light of the site investigation data; to provide feedback to continued site investigations and site-specific repository design and to identify site specific scenarios and geoscientific issues for further analyses. The PSE focuses on comparing the attained knowledge of the sites with the suitability criteria as set out by SKB in the report SKB-TR--00-12. These criteria both concern properties of the site judged to be necessary for safety and engineering (requirements) and properties judged to be beneficial (preferences). The findings are then evaluated in order to provide feedback to continued investigations and design work. The PSE does not aim at comparing sites and does not assess compliance with safety and radiation protection criteria. The evaluation shows that even considering remaining uncertainties, the Simpevarp subarea meets all safety requirements and most of the safety preferences. Consequently, from a safety point of view, there is no reason not to continue the Site Investigations of the Simpevarp subarea. There are still uncertainties to resolve and the safety would eventually need to be verified through a full safety assessment. Still, this Preliminary Safety Evaluation demonstrates that it is likely that a safe repository for spent nuclear fuel of the KBS-3 type could be constructed at the site. The following feedback is provided to the site investigations and the associated site modelling: Reducing the uncertainty on the deformation zone geometry within the Simpevarp subarea would allow for a more specified layout, although the sensitivity analysis shows that the space needed is rather robust with respect to uncertainties in the zones. There is substantial uncertainty in the discrete fracture network (DFN) model

  9. Preliminary site description Forsmark area - version 1.1

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2004-03-01

    This report presents the interim version (model version 1.1) of the preliminary Site Descriptive Model for Forsmark. The basis for this interim version is quality-assured, geoscientific and ecological field data from Forsmark that were available in the SKB databases SICADA and GIS at April 30, 2003 as well as version 0 of the Site Descriptive Model. The new data acquired during the initial site investigation phase to the date of data freeze 1.1 constitute the basis for the updating of version 0 to version 1.1. These data originate from surface investigations on the candidate area with its regional environment and from drilling and investigations in boreholes. The surface-based data sets were rather extensive whereas the data sets from boreholes were limited to information from one 1,000 m deep cored borehole (KFM01A) and eight 150 to 200 m deep percussion-drilled boreholes in the Forsmark candidate area. Discipline specific models are developed for a selected regional and local model volume and these are then integrated into a site description. The current methodologies for developing the discipline specific models and the integration of these are documented in methodology reports or strategy reports. In the present work, the guidelines given in those reports were followed to the extent possible with the data and information available at the time for data freeze for model version 1.1. Compared with version 0 there are considerable additional features in the version 1.1, especially in the geological description and in the description of the near surface. The geological models of lithology and deformation zones are based on borehole information and much higher resolution surface data. The existence of highly fractured sub-horizontal zones has been verified and these are now part of the model of the deformation zones. A discrete fracture network (DFN) model has also been developed. The rock mechanics model is based on strength information from SFR and an empirical

  10. Recommended criteria for the evaluation of on-site nuclear power plant emergency exercises

    International Nuclear Information System (INIS)

    Lafortune, J.F.

    1997-01-01

    A review of existing Canadian and International emergency exercise evaluation criteria and approaches has been conducted. Based on the results of the review, criteria are proposed for the evaluation of on-site emergency exercises for Canadian nuclear power stations. The proposed criteria are performance-based. They are comprehensive, yet remain adaptable to all stations and accident scenarios. They are primarily aimed at radiological emergency exercises, but are entirely applicable to fire or other conventional exercises. This report also addresses evaluation preparation and methodology. (author). 21 refs., 6 tabs

  11. Preliminary site description. Simpevarp area - version 1.1

    Energy Technology Data Exchange (ETDEWEB)

    Winberg, Anders [ed.

    2004-08-01

    Site characterisation in the Oskarshamn area is currently conducted at two adjoining localities, the Simpevarp and Laxemar subareas. This report presents the interim version (model version Simpevarp 1.1 of S1.1 for short) of the preliminary Site Descriptive Model for the Simpevarp subarea. The basis for this interim version is quality-assured, geoscientific and ecological field data from the Simpevarp subarea (and in part from the Laxemar area) available in the SKB SICADA and GIS data bases as of July 1, 2003 as well as version 0 of the Site Descriptive Model. The new data collected during the initial site investigation phase up till the date of data freeze S1.1 constitute the basis for the update of version 0 to version S1.1. These data include results from surface investigations in the subarea with its regional environment and from drillings and investigations in boreholes. The surface-based data sets were, in a relative sense, extensive compared with data sets from boreholes, were the information largely was limited to information from one c. 1,000 m deep cored borehole (KSH01A), two existing cored boreholes and three c. 200 m deep percussion-drilled boreholes. Discipline-specific models are developed for the selected regional and local model volumes and these models are subsequently integrated into a unified site description. The current methodologies for developing discipline-specific models and their integration are documented in methodology/ strategy reports. In the present work, the procedures and guidelines given in those reports were followed to the extent possible given the data and information available at the time of data freeze for model version S1.1. Compared with version 0 there are considerable additional features in the version S1.1, especially in the geological description and in the description of the near surface. The geological models of lithology and deformation zones are based on borehole information and surface data of much higher

  12. HOSPITAL SITE SELECTION USING TWO-STAGE FUZZY MULTI-CRITERIA DECISION MAKING PROCESS

    Directory of Open Access Journals (Sweden)

    Ali Soltani

    2011-06-01

    Full Text Available Site selection for sitting of urban activities/facilities is one of the crucial policy-related decisions taken by urban planners and policy makers. The process of site selection is inherently complicated. A careless site imposes exorbitant costs on city budget and damages the environment inevitably. Nowadays, multi-attributes decision making approaches are suggested to use to improve precision of decision making and reduce surplus side effects. Two well-known techniques, analytical hierarchal process and analytical network process are among multi-criteria decision making systems which can easily be consistent with both quantitative and qualitative criteria. These are also developed to be fuzzy analytical hierarchal process and fuzzy analytical network process systems which are capable of accommodating inherent uncertainty and vagueness in multi-criteria decision-making. This paper reports the process and results of a hospital site selection within the Region 5 of Shiraz metropolitan area, Iran using integrated fuzzy analytical network process systems with Geographic Information System (GIS. The weights of the alternatives were calculated using fuzzy analytical network process. Then a sensitivity analysis was conducted to measure the elasticity of a decision in regards to different criteria. This study contributes to planning practice by suggesting a more comprehensive decision making tool for site selection.

  13. HOSPITAL SITE SELECTION USING TWO-STAGE FUZZY MULTI-CRITERIA DECISION MAKING PROCESS

    Directory of Open Access Journals (Sweden)

    Ali Soltani

    2011-01-01

    Full Text Available Site selection for sitting of urban activities/facilities is one of the crucial policy-related decisions taken by urban planners and policy makers. The process of site selection is inherently complicated. A careless site imposes exorbitant costs on city budget and damages the environment inevitably. Nowadays, multi-attributes decision making approaches are suggested to use to improve precision of decision making and reduce surplus side effects. Two well-known techniques, analytical hierarchal process and analytical network process are among multi-criteria decision making systems which can easily be consistent with both quantitative and qualitative criteria. These are also developed to be fuzzy analytical hierarchal process and fuzzy analytical network process systems which are capable of accommodating inherent uncertainty and vagueness in multi-criteria decision-making. This paper reports the process and results of a hospital site selection within the Region 5 of Shiraz metropolitan area, Iran using integrated fuzzy analytical network process systems with Geographic Information System (GIS. The weights of the alternatives were calculated using fuzzy analytical network process. Then a sensitivity analysis was conducted to measure the elasticity of a decision in regards to different criteria. This study contributes to planning practice by suggesting a more comprehensive decision making tool for site selection.

  14. Development of site suitability criteria for the high level waste repository for Lawrence Livermore Laboratories

    International Nuclear Information System (INIS)

    1977-06-01

    Results of our mining, geological and geotechnical studies provided in support of the development of site suitability criteria for the high level waste repository are presented. The primary purpose of the work was the identification and development of appropriate geotechnical descriptors and coefficients required for the Site Suitability Repository Model. This model was developed by The Analytic Sciences Corporation (TASC) of Reading, Massachusetts and is not described in this report

  15. Development of site suitability criteria for the high level waste repository for Lawrence Livermore Laboratories

    Energy Technology Data Exchange (ETDEWEB)

    1977-06-01

    Results of our mining, geological and geotechnical studies provided in support of the development of site suitability criteria for the high level waste repository are presented. The primary purpose of the work was the identification and development of appropriate geotechnical descriptors and coefficients required for the Site Suitability Repository Model. This model was developed by The Analytic Sciences Corporation (TASC) of Reading, Massachusetts and is not described in this report.

  16. Preliminary site description Simpevarp subarea - version 1.2

    Energy Technology Data Exchange (ETDEWEB)

    Winberg, Anders [ed.

    2005-04-01

    The objectives of the version 1.2 site descriptive modelling (SDM) of the Simpevarp subarea are to produce and document an integrated description of the site and its regional environments based on the site-specific data available from the initial site investigations and to give recommendations on continued investigations on a continuous basis. The modelling work is based on primary data available at the time of the data freeze for Simpevarp 1.2, April 1, 2004. The local scale model area (24 km{sup 2}) for the Simpevarp 1.2 modelling encompasses both the Simpevarp and Laxemar subareas. The local model area is located in the centre of a regional scale model area (273 km{sup 2}). Surface ecosystem models in terms of pools and fluxes of carbon have been developed for the terrestrial (e.g. plants and animals) and limnic (e.g. algae and fish) systems using the Lake Frisksjoen drainage area. Furthermore, a first marine ecosystem model has been developed for the Basin Borholmsfjaerden. Three principal lithological domains have been defined in the subarea, an A domain that is dominated by the Aevroe granite, a domain B that is dominated by the fine-grained dioritoid, a C domain that is characterised by a mixture of of Aevroe granite and quartz monzodiorite. A fourth domain is made up a few scattered domains of diorite to gabbro. In total, 22 deformation zones with high confidence of occurrence have been interpreted in the local scale model area. The understanding of the interpreted deformation zones of the Simpevarp subarea is considered adequate to make a preliminary assessment of available storage volumes for a deep repository. High rock stresses do not appear to be a major concern for the Simpevarp subarea. The magnitude of the maximum principal stress at 500 m in the Simpevarp subarea is estimated at 10-22 MPa. The analysis of the thermal conductivity has developed considerably since Simpevarp 1.1. In terms of interpreted mean values for the identified lithological

  17. Preliminary site description Simpevarp subarea - version 1.2

    International Nuclear Information System (INIS)

    Winberg, Anders

    2005-04-01

    The objectives of the version 1.2 site descriptive modelling (SDM) of the Simpevarp subarea are to produce and document an integrated description of the site and its regional environments based on the site-specific data available from the initial site investigations and to give recommendations on continued investigations on a continuous basis. The modelling work is based on primary data available at the time of the data freeze for Simpevarp 1.2, April 1, 2004. The local scale model area (24 km 2 ) for the Simpevarp 1.2 modelling encompasses both the Simpevarp and Laxemar subareas. The local model area is located in the centre of a regional scale model area (273 km 2 ). Surface ecosystem models in terms of pools and fluxes of carbon have been developed for the terrestrial (e.g. plants and animals) and limnic (e.g. algae and fish) systems using the Lake Frisksjoen drainage area. Furthermore, a first marine ecosystem model has been developed for the Basin Borholmsfjaerden. Three principal lithological domains have been defined in the subarea, an A domain that is dominated by the Aevroe granite, a domain B that is dominated by the fine-grained dioritoid, a C domain that is characterised by a mixture of of Aevroe granite and quartz monzodiorite. A fourth domain is made up a few scattered domains of diorite to gabbro. In total, 22 deformation zones with high confidence of occurrence have been interpreted in the local scale model area. The understanding of the interpreted deformation zones of the Simpevarp subarea is considered adequate to make a preliminary assessment of available storage volumes for a deep repository. High rock stresses do not appear to be a major concern for the Simpevarp subarea. The magnitude of the maximum principal stress at 500 m in the Simpevarp subarea is estimated at 10-22 MPa. The analysis of the thermal conductivity has developed considerably since Simpevarp 1.1. In terms of interpreted mean values for the identified lithological domains, the

  18. Multi-criteria assessment tool for sustainability appraisal of remediation alternatives for a contaminated site

    DEFF Research Database (Denmark)

    Søndergaard, Gitte Lemming; Binning, Philip John; Bondgård, Morten

    2017-01-01

    Purpose: In order to improve and support decision-making for the selection of remedial techniques for contaminated sites, a multi-criteria assessment (MCA) method has been developed. The MCA framework is structured in a decision process actively involving stakeholders, and compares...

  19. Site study plan for Deep Hydronest Test Wells, Deaf Smith County Site, Texas: Preliminary draft

    International Nuclear Information System (INIS)

    1987-05-01

    Wells called Deep Hydronest Wells will be installed at six locations at the Deaf Smith County Site to characterize hydraulic parameters in the geologic column between the top of the San Andres Formation and the base of Pennsylvanian System. Three hydronests will be drilled during early stages of site characterization to provide data for performance assessment modeling. Four wells are proposed for each of these 3 nests. Results of drilling, testing, and preliminary modeling will direct drilling and testing activities at the last 3 nests. Two wells are proposed at each of the last 3 nests for a total of 18 wells. The Salt Repository Project (SRP) Networks specify the schedule under which this program will operate. Drilling and hydrologic testing of the first Deep Hydronest will begin early in the Surface Investigation Program. Drilling and testing of the first three Deep Hydronests will require about 18 months. After 12 months of evaluating and analyzing data from the first three hydronests, the remaining three hydronests will be drilled during a 12-month period. The Technical Field Services Contractor is responsible for conducting the field program. Samples and data will be handled and reported in accordance with established SRP procedures. A quality assurance program will be used to assure that activities affecting quality are performed correctly and that the appropriate documentation is maintained. 36 refs., 20 figs., 6 tabs

  20. The Spanish version of the 2010 American College of Rheumatology Preliminary Diagnostic Criteria for fibromyalgia: reliability and validity assessment.

    Science.gov (United States)

    Casanueva, Benigno; García-Fructuoso, Ferrán; Belenguer, Rafael; Alegre, Cayetano; Moreno-Muelas, José V; Hernández, José L; Pina, Tinitario; González-Gay, Miguel Á

    2016-01-01

    To investigate the reliability and validity of the Spanish version of the 2010 American College of Rheumatology (ACR) Preliminary Diagnostic Criteria for Fibromyalgia (FM) in patients with chronic pain. The 2010 ACR Preliminary Diagnostic Criteria for FM were adapted to a Spanish version following the guidelines of the Rheumatology Spanish Society Study Group of FM. Based on the 1990 ACR classi cation criteria for FM, patients with chronic pain were initially divided into two groups: a FM group and another group of non-FM individuals. Patients from the FM group were evaluated by tender points (TP) examination, Fibromyalgia Impact Questionnaire (FIQ), Widespread Pain Index (WPI), and Symptom Severity Scale (SSS). The non-FM (control) group included patients with rheumatoid arthritis (RA) and osteoarthritis (OA). They were evaluated by WPI and SSS. We included 1,169 patients divided into two groups: FM group (n=803; 777 women and 26 men) and non-FM group (n= 366; 147 patients with RA, and 219 with OA). The median value of TP and FIQ in the FM group was 16 and 74 respectively. The preliminary 2010 ACR criteria were met by 665 (82.8%) FM patients and by 112 (30.6%) patients from the non-FM group (pFIQ (p<0.0001), WPI (p<0.0001) and SSS (p<0.0001) were observed when FM patients fulfilling the 2010 ACR criteria were compared with the remaining FM patients who did not fulfill these criteria. Sensitivity of the Spanish version of the 2010 ACR criteria was 85.6% (95%CI: 83.1-88.1), speci city 73.2% (95%CI: 68.4-78), positive predictive value 87.7% (95%CI: 85.3-90.1) and negative predictive value 69.4% (95%CI: 64.5-74.2). Our results indicate that the 2010 ACR Preliminary Diagnostic Criteria for FM may be useful to establish a diagnosis of FM in Spanish individuals with chronic pain.

  1. Siting Criteria for Low and Intermediate Level Radioactive Waste Disposal in Egypt (Proposal approach)

    International Nuclear Information System (INIS)

    Abdellatif, M.M.

    2012-01-01

    The objective of radioactive waste disposal is to isolate waste from the surrounding media so that it does not result in undue radiation exposure to humans and the environment. The required degree of isolation can be obtained by implementing various disposal methods and suitable criteria. Near surface disposal method has been practiced for some decades, with a wide variation in sites, types and amounts of wastes, and facility designs employed. Experience has shown that the effective and safe isolation of waste depends on the performance of the overall disposal system, which is formed by three major components or barriers: the site, the disposal facility and the waste form. The site selection process for low-level and intermediate level radioactive waste disposal facility addressed a wide range of public health, safety, environmental, social and economic factors. Establishing site criteria is the first step in the sitting process to identify a site that is capable of protecting public health, safety and the environment. This paper is concerning a proposal approach for the primary criteria for near surface disposal facility that could be applicable in Egypt.

  2. Development of criteria for release of Idaho National Engineering Laboratory sites following decontamination and decommissioning

    International Nuclear Information System (INIS)

    Kirol, L.

    1986-08-01

    Criteria have been developed for release of Idaho National Engineering Laboratory (INEL) facilities and land areas following decontamination and decommissioning (D and D). Although these facilities and land areas are not currently being returned to the public domain, and no plans exist for doing so, criteria suitable for unrestricted release to the public were desired. Midway through this study, the implementation of Department of Energy (DOE) Order 5820.2, Radioactive Waste Management, required development of site specific release criteria for use on D and D projects. These criteria will help prevent remedial actions from being required if INEL reuse considerations change in the future. Development of criteria for release of INEL facilities following D and D comprised four study areas: pathways analysis, dose and concentration guidelines, sampling and instrumentation, and implementation procedures. Because of the complex and sensitive nature of the first three categories, a thorough review by experts in those respective fields was desired. Input and support in preparing or reviewing each part of the criteria development task was solicited from several DOE field offices. Experts were identified and contracted to assist in preparing portions of the release criteria, or to serve on a peer-review committee. Thus, the entire release criteria development task was thoroughly reviewed by recognized experts from contractors at several DOE field offices, to validate technical content of the document. Each of the above four study areas was developed originally as an individual task, and a report was generated from each. These reports are combined here to form this document. This release criteria document includes INEL-specific pathways analysis, instrumentation requirements, sampling procedures, the basis for selection of dose and concentration guidelines, and cost-risk-benefit procedures

  3. Preliminary safety evaluation for the Forsmark area. Based on data and site descriptions after the initial site investigation stage

    International Nuclear Information System (INIS)

    Andersson, Johan

    2005-08-01

    The main objectives of this Preliminary Safety Evaluation (PSE) of the Forsmark area have been to determine, with limited efforts, whether the feasibility study's judgement of the suitability of the candidate area with respect to long-term safety holds up in the light of the actual site investigation data; to provide feedback to continued site investigations and site-specific repository design and to identify site-specific scenarios and geoscientific issues for further analyses. The PSE focuses on comparing the attained knowledge of the sites with the suitability criteria as set out by SKB. The PSE does not aim at comparing sites and does not assess compliance with safety and radiation protection criteria. The evaluation shows that, even considering remaining uncertainties, the Forsmark area meets all stated safety requirements and preferences. Consequently, from a safety point of view, there is no reason not to continue the Site Investigations of the Forsmark area. There are still uncertainties to resolve and the safety would eventually need to be verified through a full safety assessment. Nevertheless, this Preliminary Safety Evaluation demonstrates that it is likely that a safe repository for spent nuclear fuel of the KBS-3 type could be constructed at the site. The following feedback is provided to the site investigations and the associated site modelling: Reducing the uncertainty on the deformation zone geometry inside the target area would be needed to more firmly define locations of the suitable deposition volumes. There is substantial uncertainty in the Discrete Fracture Network model. Further reduction of the uncertainties, if needed, would probably only be possible from the underground, detailed investigation phase. Efforts need also be spent on improving the DFN-modelling. There are assumptions made in current models that could be challenged and there seems to be room for better use of the borehole information. It is particularly important to provide

  4. Preliminary safety evaluation for the Forsmark area. Based on data and site descriptions after the initial site investigation stage

    Energy Technology Data Exchange (ETDEWEB)

    Andersson, Johan [JA Streamflow AB, Aelvsjoe (Sweden)

    2005-08-01

    The main objectives of this Preliminary Safety Evaluation (PSE) of the Forsmark area have been to determine, with limited efforts, whether the feasibility study's judgement of the suitability of the candidate area with respect to long-term safety holds up in the light of the actual site investigation data; to provide feedback to continued site investigations and site-specific repository design and to identify site-specific scenarios and geoscientific issues for further analyses. The PSE focuses on comparing the attained knowledge of the sites with the suitability criteria as set out by SKB. The PSE does not aim at comparing sites and does not assess compliance with safety and radiation protection criteria. The evaluation shows that, even considering remaining uncertainties, the Forsmark area meets all stated safety requirements and preferences. Consequently, from a safety point of view, there is no reason not to continue the Site Investigations of the Forsmark area. There are still uncertainties to resolve and the safety would eventually need to be verified through a full safety assessment. Nevertheless, this Preliminary Safety Evaluation demonstrates that it is likely that a safe repository for spent nuclear fuel of the KBS-3 type could be constructed at the site. The following feedback is provided to the site investigations and the associated site modelling: Reducing the uncertainty on the deformation zone geometry inside the target area would be needed to more firmly define locations of the suitable deposition volumes. There is substantial uncertainty in the Discrete Fracture Network model. Further reduction of the uncertainties, if needed, would probably only be possible from the underground, detailed investigation phase. Efforts need also be spent on improving the DFN-modelling. There are assumptions made in current models that could be challenged and there seems to be room for better use of the borehole information. It is particularly important to

  5. Development of policies for Natura 2000 sites: a multi-criteria approach to support decision makers.

    Science.gov (United States)

    Cortina, Carla; Boggia, Antonio

    2014-08-01

    The aim of this study is to present a methodology to support decision makers in the choice of Natura 2000 sites needing an appropriate management plan to ensure a sustainable socio-economic development. In order to promote sustainable development in the Natura 2000 sites compatible with nature preservation, conservation measures or management plans are necessary. The main issue is to decide when only conservation measures can be applied and when the sites need an appropriate management plan. We present a case study for the Italian Region of Umbria. The methodology is based on a multi-criteria approach to identify the biodiversity index (BI), and on the development of a human activities index (HAI). By crossing the two indexes for each site on a Cartesian plane, four groups of sites were identified. Each group corresponds to a specific need for an appropriate management plan. Sites in the first group with a high level both of biodiversity and human activities have the most urgent need of an appropriate management plan to ensure sustainable development. The proposed methodology and analysis is replicable in other regions or countries by using the data available for each site in the Natura 2000 standard data form. A multi-criteria analysis is especially suitable for supporting decision makers when they deal with a multidimensional decision process. We found the multi-criteria approach particularly sound in this case, due to the concept of biodiversity itself, which is complex and multidimensional, and to the high number of alternatives (Natura 2000 sites) to be assessed. Copyright © 2014 Elsevier Ltd. All rights reserved.

  6. A Preliminary Case Study for Rectenna Sites in Indonesia

    Science.gov (United States)

    Purwanto, Y.; Collins, P.

    2004-12-01

    Electricity power generation using alternative energy sources in Indonesia has become an important policy. Until now, the contribution from alternative energy sources (especially from renewable energy sources) is very small, only about 1% of the total energy supply. It is expected that in the next 10 years this contribution will be raised to 20%. The development of renewable energy sources is primarily performed in remote areas, that are poor in infrastructure facilities. This is considered to be a good policy since there are many such remote areas in Indonesia that need development programs. The existence of Solar Power Satellite system will open a new horizon in alternative energy supply, including Indonesia, because of its higher efficiency compared to conventional terrestrial solar cells, with almost no influence from either climate or solar position. Like other countries in the world, Indonesia, although one of the largest mineral energy producers in the world (i.e. oil, coal, and natural gas), still gives attention to energy diversification programs, including solar energy utilization. SPS, being based on solar energy, could be a good choice. The Indonesian archipelago consists of thousands of islands (more than 13,000) and is the equatorial country with the longest equatorial extent (more than 5000 km). This condition is very good for energy reception from the SPS 2000 pilot plant since the energy transmitting system (spacetenna) will orbit above the equator. Along the equator there could be placed more than four receiving stations (rectenna), especially in remote areas. Thus, it is very important to consider the involvement of Indonesia in SPS energy reception research. This paper describes a preliminary study of the development possibilities in SPS energy reception in Indonesia. To define the rectenna sites and physical development aspect, this study considers some major aspects: environmental, technical, social, and economic aspects. Environmental aspects

  7. Criteria and technical concept for demonstrating greater confinement disposal of radioactive wastes at Arid Western Sites

    International Nuclear Information System (INIS)

    Hunter, P.H.

    1981-01-01

    This report summarizes the work of two documents; the Criteria for Greater Confinement of Radioactive Wastes at Arid Western Sites, NVO-234, March 1981, (within this report, referred to as the GCDF Criteria Document); and the Draft Technical Concept for a Test of Greater Confinement Disposal of Radioactive Waste in Unsaturated Media at the Nevada Test Site, FBDU-343-004, June 1981, (referred within this report as the Technical Concept for the GCDF). For the past two years, Ford, Bacon and Davis has been performing technical services for the Department of Energy at the Nevada Test Site in development of defense low-level waste management concepts, including the greater confinement disposal concept with particular application to arid sites. The investigations have included the development of Criteria for Greater Confinement Disposal, NVO-234, which we published in May of this year; then the draft for the technical concept for greater confinement disposal, published in June; leading up to the point where we are now. The final technical concept and design specifications should be published imminently. The document is prerequisite to the actual construction and implementation of the demonstration facility this fiscal year

  8. Geoscientific long-term prognosis. Preliminary safety analysis for the site Gorleben

    International Nuclear Information System (INIS)

    Mrugalla, Sabine

    2011-07-01

    The preliminary safety analysis of the site Gorleben includes the following chapters: (1) Introduction; (2) Aim and content of the geoscientific long-term prognosis for the site Gorleben; (3) Boundary conditions at the site Gorleben: climate; geomorphology; overlying rocks and adjoining rocks; hydrogeology; salt deposit Gorleben. (4) Probable future geological developments at the site Gorleben: supraregional developments with effects on the site Gorleben; glacial period developments; developments of the geomorphology, overlying and adjoining rocks; future developments of the hydrological systems at the site Gorleben; future saliniferous specific developments of the salt deposit Gorleben. (5) Commentary on the unlikely or excludable developments of the site Gorleben.

  9. Analysis of Multi-Criteria Evaluation Method of Landfill Site Selection for Municipal Solid Waste Management

    Science.gov (United States)

    Mohammed, Habiba Ibrahim; Majid, Zulkepli; Yusof, Norhakim Bin; Bello Yamusa, Yamusa

    2018-03-01

    Landfilling remains the most common systematic technique of solid waste disposal in most of the developed and developing countries. Finding a suitable site for landfill is a very challenging task. Landfill site selection process aims to provide suitable areas that will protect the environment and public health from pollution and hazards. Therefore, various factors such as environmental, physical, socio-economic, and geological criteria must be considered before siting any landfill. This makes the site selection process vigorous and tedious because it involves the processing of large amount of spatial data, rules and regulations from different agencies and also policy from decision makers. This allows the incorporation of conflicting objectives and decision maker preferences into spatial decision models. This paper particularly analyzes the multi-criteria evaluation (MCE) method of landfill site selection for solid waste management by means of literature reviews and surveys. The study will help the decision makers and waste management authorities to choose the most effective method when considering landfill site selection.

  10. Analysis of Multi-Criteria Evaluation Method of Landfill Site Selection for Municipal Solid Waste Management

    Directory of Open Access Journals (Sweden)

    Ibrahim Mohammed Habiba

    2018-01-01

    Full Text Available Landfilling remains the most common systematic technique of solid waste disposal in most of the developed and developing countries. Finding a suitable site for landfill is a very challenging task. Landfill site selection process aims to provide suitable areas that will protect the environment and public health from pollution and hazards. Therefore, various factors such as environmental, physical, socio-economic, and geological criteria must be considered before siting any landfill. This makes the site selection process vigorous and tedious because it involves the processing of large amount of spatial data, rules and regulations from different agencies and also policy from decision makers. This allows the incorporation of conflicting objectives and decision maker preferences into spatial decision models. This paper particularly analyzes the multi-criteria evaluation (MCE method of landfill site selection for solid waste management by means of literature reviews and surveys. The study will help the decision makers and waste management authorities to choose the most effective method when considering landfill site selection.

  11. Derivation of site-specific selenium criteria for a Kentucky stream receiving fly ash effluent

    International Nuclear Information System (INIS)

    Reash, R.J.; Van Hassel, J.H.

    1993-01-01

    Blaine Creek, a fifth-order tributary to the Big Sandy River in eastern Kentucky, receives fly ash effluent from Kentucky Power Company's Big Sandy Plant fly ash pond near the creek's mouth. Long-term biosurvey/physicochemical data and speciation studies were used to derive proposed site-specific selenium water quality criteria. Biosurvey results from 1982--1990 were consistent in showing no adverse effects of fly ash discharge, even during low flow conditions when the effluent comprised 75% of creek flow. Five macroinvertebrate parameters (taxa richness, total abundance, EPT taxa, number caddisflies and chironomids) were significantly correlated with % effluent, indicating enhanced communities at high instream waste concentrations. Several fish metrics similarly showed greater enhancement at high % effluent conditions. Selenium speciation studies indicated that selenite (Se 4+ ) represented 100% of total selenium in the effluent. Total selenium concentrations were low at fully mixed downstream reaches. US EPA's Recalculation Procedure was used to calculate site-specific selenium criteria based on Se 4+ toxicity data for resident species. These criteria are higher than statewide criteria which are based on selenium, effects at waterbodies having low turnover rates

  12. Suggested state requirements and criteria for a low-level radioactive waste disposal site regulatory program

    International Nuclear Information System (INIS)

    Ratliff, R.A.; Dornsife, B.; Autry, V.; Gronemyer, L.; Vaden, J.; Cashman, T.

    1985-08-01

    Description of criteria and procedure is presented for a state to follow in the development of a program to regulate a LLW disposal site. This would include identifying those portions of the NRC regulations that should be matters of compatibility, identifying the various expertise and disciplines that will be necessary to effectively regulate a disposal site, identifying the resources necessary for conducting a confirmatory monitoring program, and providing suggestions in other areas which, based on experiences, would result in a more effective regulatory program

  13. Development of on-site accident criteria for waste transfer casks

    International Nuclear Information System (INIS)

    Uldrich, E.D.

    1989-01-01

    Removal of radioactive waste must withstand the scrutiny of the public and various regulatory offices. Currently, there is no standard accident criteria or methodology for intra-site shipments at the Idaho National Engineering Laboratory (INEL). Since the radioactive waste transfer casks only carry material within the INEL site boundaries and are not used for normal over-the-road transport, the requirements of 10 CFR 71 Packaging and Transportation of Radioactive Material, do not provide suitable requirements for cask design or safety analyses. The objective is to develop realistically conservative accident scenarios consistent with the limited uses at the INEL for which the cask is approved

  14. Development of closure criteria for inactive radioactive waste-disposal sites at Oak Ridge National Laboratory

    International Nuclear Information System (INIS)

    Kocher, D.C.

    1990-01-01

    The Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) specifies that the U.S. Department of Energy shall comply with the procedural and substantive requirements of CERCLA regarding cleanup of inactive waste-disposal sites. Remedial actions require a level of control for hazardous substances that at least attains legally applicable or relevant and appropriate requirements (ARAR). This requirement may be waived if compliance with ARAR results in greater risk to human health and the environment than alternatives or is technically impractical. It will review potential ARAR for cleanup of inactive radioactive waste-disposal sites and propose a set of closure criteria for such sites at Oak Ridge National Laboratory. Important potential ARAR include federal standards for radiation protection of the public, radioactivity in drinking water, and near-surface land disposal of radioactive wastes. Proposed criteria for cleanup of inactive radioactive waste-disposal sites are: (1) a limit of 0.25 mSv on annual effective dose equivalent for offsite individuals; (2) limits of 1 mSv for continuous exposures and 5 mSv for occasional exposures on annual effective dose equivalent for inadvertent intruders, following loss of institutional controls over disposal sites; and (3) limits on concentrations of radionuclides in potable ground and surface waters in accordance with federal drinking-water standards, to the extent reasonably achievable

  15. Multi-criteria analysis for site selection for the reuse of reclaimed water and biosolids

    Directory of Open Access Journals (Sweden)

    António Albuquerque

    2015-01-01

    Full Text Available Low pH soils with insufficient organic matter can benefit from the application of reclaimed water (RW and biosolids. The presence of nutrients also aids plant growth. This paper presents the results of two integrated research studies, both carried out in the Beira Interior Region (Covilhã, Portugal; one used RW for irrigation, the other applied paper mill sludge to agricultural land. In both cases, multiple criteria based on GIS tools were used for site selection. In the first study, the characteristics of RW analyzed over 2 years were found suitable for crop irrigation. The RW had moderate organic content, low electrical conductivity (CE, high nutrient content (N, P, and low concentrations of nitrate, metals and phytotoxic elements (Al, B, Cl and Na. The multi-criteria analysis was carried out taking into account environmental, technical and economic criteria and a suitable area of 30.5 ha was found for RW irrigation. In the second work, the paper mill sludge was considered suitable for application to agricultural land. Its concentrations of N, P and heavy metals did not a present risk for soil contamination and were suitable for soil improvement and crop production. A multi-criteria analysis based on similar criteria was conducted and a suitable area of 253 ha was found for sludge application.

  16. Preliminary site description Forsmark area - version 1.2

    Energy Technology Data Exchange (ETDEWEB)

    Skagius, Kristina [ed.

    2005-06-01

    The Swedish Nuclear Fuel and Waste Management Company (SKB) is undertaking site characterisation at two different locations, the Forsmark and Simpevarp areas, with the objective of siting a geological repository for spent nuclear fuel. An integrated component in the characterisation work is the development of a site descriptive model that constitutes a description of the site and its regional setting, covering the current state of the geosphere and the biosphere as well as those ongoing natural processes that affect their long-term evolution. The present report documents the site descriptive modelling activities (version 1.2) for the Forsmark area. The overall objectives of the version 1.2 site descriptive modelling are to produce and document an integrated description of the site and its regional environments based on the site-specific data available from the initial site investigations and to give recommendations on continued investigations. The modelling work is based on primary data, i.e. quality-assured, geoscientific and ecological field data available in the SKB databases SICADA and GIS, available July 31, 2004. The work has been conducted by a project group and associated discipline-specific working groups. The members of the project group represent the disciplines of geology, rock mechanics, thermal properties, hydrogeology, hydrogeochemistry, transport properties and surface ecosystems (including overburden, surface hydrogeochemistry and hydrology). In addition, some group members have specific qualifications of importance in this type of project e.g. expertise in RVS (Rock Visualisation System) modelling, GIS-modelling and in statistical data analysis. The overall strategy to achieve a site description is to develop discipline-specific models by interpretation and analyses of the primary data. The different discipline-specific models are then integrated into a site description. Methodologies for developing the discipline-specific models are documented in

  17. Preliminary site description Forsmark area - version 1.2

    International Nuclear Information System (INIS)

    Skagius, Kristina

    2005-06-01

    The Swedish Nuclear Fuel and Waste Management Company (SKB) is undertaking site characterisation at two different locations, the Forsmark and Simpevarp areas, with the objective of siting a geological repository for spent nuclear fuel. An integrated component in the characterisation work is the development of a site descriptive model that constitutes a description of the site and its regional setting, covering the current state of the geosphere and the biosphere as well as those ongoing natural processes that affect their long-term evolution. The present report documents the site descriptive modelling activities (version 1.2) for the Forsmark area. The overall objectives of the version 1.2 site descriptive modelling are to produce and document an integrated description of the site and its regional environments based on the site-specific data available from the initial site investigations and to give recommendations on continued investigations. The modelling work is based on primary data, i.e. quality-assured, geoscientific and ecological field data available in the SKB databases SICADA and GIS, available July 31, 2004. The work has been conducted by a project group and associated discipline-specific working groups. The members of the project group represent the disciplines of geology, rock mechanics, thermal properties, hydrogeology, hydrogeochemistry, transport properties and surface ecosystems (including overburden, surface hydrogeochemistry and hydrology). In addition, some group members have specific qualifications of importance in this type of project e.g. expertise in RVS (Rock Visualisation System) modelling, GIS-modelling and in statistical data analysis. The overall strategy to achieve a site description is to develop discipline-specific models by interpretation and analyses of the primary data. The different discipline-specific models are then integrated into a site description. Methodologies for developing the discipline-specific models are documented in

  18. American College of Radiology Accreditation Program for mammographic screening sites: Physical evaluation criteria

    International Nuclear Information System (INIS)

    Hendrick, R.E.; Haus, A.G.; Hubbard, L.B.; Lasky, H.J.; McCrohan, J.; McLelland, R.; Rothenberg, L.N.; Tanner, R.L.; Zinninger, M.D.

    1987-01-01

    The American College of Radiology has initiated a program for the accreditation of mammographic screening sites, which includes evaluation by mail of image quality and average glandular breast dose. Image quality is evaluated by use of a specially designed phantom (a modified RMI 152D Mammographic Phantom) containing simulated microcalcifications, fibrils and masses. Average glandular dose to a simulated 4.5-cm-thick (50% glandular, 50% fat) compressed breast is evaluated by thermoluminescent dosimeter measurements of entrance exposure and half value layer. Standards for acceptable image quality and patient doses are presented and preliminary results of the accreditation program are discussed

  19. Development of cleanup criteria for historic low-level radioactive waste sites in Canada

    International Nuclear Information System (INIS)

    Pollock, R.W.; Chambers, D.B.; Lowe, L.M.

    1995-01-01

    This paper will describe recent work performed to develop cleanup criteria, and their current status, for historic low-level radioactive waste sites in Canada. These historic wastes date back to 1933, when a radium refinery began operation in Port Hope, Ontario. The problem of residual wastes and contaminated buildings and soils in Port Hope, resulting from the practices in the early years of radium and uranium production, was discovered in the mid-1970s, and a large scale cleanup program carried out. This work was concentrated on developed properties. As a result, substantial quantities of contaminated materials remained in a number of large undeveloped areas. A number of additional historic waste sites have subsequently been discovered at other locations in Canada, where buildings and/or soils were contaminated with uranium ores or concentrates spilled during transport, or with processing residues, or as a result of the use of radium containing materials. There has been substantial evolution of the criteria for cleanup of these sites over the almost 20 year period since work started at the first sites

  20. High level waste repository site suitability criteria. Environmental impact statement methodology

    International Nuclear Information System (INIS)

    1977-06-01

    The approach (methodology) which has been developed for the preparation of the environmental impact statement (EIS) is described. A suggested outline is presented for the High Level Waste Repository Site Suitability Criteria EIS together with a detailed description of the approach to be used in preparing the EIS. In addition, a methodology is presented by which the necessary cost/benefit/risk comparisons of alternative sets of site suitability criteria can be made. The TERA environmental research data bank, a computerized data bank which contained information on current and historical licensing activities for power plants was modified to include information on generic or programmatic EIS related issues. The content of the modified data bank was utilized to develop the EIS outline presented in this report. The report recommends that a modified matrix evaluation approach be used to make the cost/benefit/risk comparisons. The suggested matrix is designed to facilitate between criteria comparative analyses of economic, environmental, sociological and radiological risk factors. The quantitative compositing of dollar cost and benefits, environmental and sociological impacts, and radiological risks is to be performed using a semi-analytical, semi-visual procedure based on the concept of ''decision surfaces.''

  1. Site characterization and validation. Stage 2 - Preliminary predictions

    International Nuclear Information System (INIS)

    Olsson, O.; Black, J.H.; Gale, J.E.; Holmes, D.C.

    1989-05-01

    The Site Characterization and Validation (SCV) project is designed to assess how well we can characterize a volume of rock prior to using it as a repository. The programme of work focuses on the validation of the techniques used in site characterization. The SCV project contains 5 stages of work arranged in two 'cycles' of data-gathering, prediction, and validation. The first stage of work has included drilling of 6 boreholes (N2, N3, N4, W1, W2 and V3) and measurements of geology, fracture characteristics, stess, single borehole geophysical logging, radar, seismics and hydrogeology. The rock at the SCV site is granite with small lithological variations. Based essentially on radar and seismic results 5 'fracture zones' have been identified, named GA, GB, GC, GH and GI. They all extend acroos the entire SCV site. They aer basically in in two groups (GA, GB, GC and GH, GI). The first group are aligned N40 degree E with a dip of 35 degree to the south. The second group are aligned approximately N10 degree W dipping 60 degree E. From the stochastic analysis of the joint data it was possible to identify three main fracture orientation clusters. The orientation of two of these clusters agree roughly with orientation of the main features. Cluster B has roughly the same orientation as GH and GI, while features GA, GB and GC have an orientation similar to the more loosely defined cluster C. The orientation of the third cluster (A) is northwest with a dip to northeast. It is found that 94% of all measured hydraulic transmissivity is accounted for by 4% of the tested rock, not all of this 'concentrated' transmissivity is with the major features defined by geophysics. When the hydraulic connections across the site are examied they show that there are several welldefined zones which permit rapid transmission of hydraulic signals. These are essentially from the northeast to the southwest. (66 figs., 21 tabs., 33 refs.)

  2. Preliminary proposed seismic design and evaluation criteria for new and existing underground hazardous materials storage tanks

    International Nuclear Information System (INIS)

    Kennedy, R.P.

    1991-01-01

    The document provides a recommended set of deterministic seismic design and evaluation criteria for either new or existing underground hazardous materials storage tanks placed in either the high hazard or moderate hazard usage catagories of UCRL-15910. The criteria given herein are consistent with and follow the same philosophy as those given in UCRL-15910 for the US Department of Energy facilities. This document is intended to supplement and amplify upon Reference 1 for underground hazardous materials storage tanks

  3. Early response to sibutramine in patients not meeting current label criteria: preliminary analysis of SCOUT lead-in period

    DEFF Research Database (Denmark)

    Caterson, Ian; Coutinho, Walmir; Finer, Nick

    2010-01-01

    The Sibutramine Cardiovascular Outcomes (SCOUT) trial protocol defines a patient population predominantly outside current European Union label criteria. This article explores responses to sibutramine during the 6-week, single-blind, lead-in period between patients who conformed to the label...... requirements ("conformers") and those who did not ("nonconformers"). SCOUT is an ongoing, randomized, double-blind, placebo-controlled outcome trial in overweight/obese patients at high risk of a cardiovascular event. In total, 10,742 patients received sibutramine and weight management during the lead...... with sibutramine confirms its good tolerability and efficacy in patients who meet current label criteria. Preliminary data from high-risk patients for whom sibutramine is currently contraindicated suggest a low discontinuation rate and few serious adverse events but confirmation from the SCOUT outcome data...

  4. Multi-criteria analysis for the detection of the most critical European UNESCO Heritage sites

    Science.gov (United States)

    Valagussa, Andrea; Frattini, Paolo; Berta, Nadia; Spizzichino, Daniele; Leoni, Gabriele; Margottini, Claudio; Battista Crosta, Giovanni

    2017-04-01

    A GIS-based multi-criteria analysis has been implemented to identify and to rank the most critical UNESCO Heritage sites at the European scale in the context of PROTHEGO JPI-Project. Two multi-criteria methods have been tested and applied to more than 300 European UNESCO Sites. First, the Analytic Hierarchy Procedure (AHP) was applied to the data of the UNESCO Periodic Report, in relation to 13 natural hazards that have affected or can potentially affect the Heritage sites. According to these reports, 22% of sites are without any documented hazard and 70% of the sites have at least one hazard affecting the site. The most important hazards on the European country are: fire (wildfire), storm, flooding, earthquake and erosion. For each UNESCO site, the potential risk was calculated as a weighed sum of the hazards that affect the site. The weighs of the 13 hazards were obtained by AHP procedure, which is a technique for multi-attribute decision making that enables the decomposition of a problem into hierarchy, based on the opinion of different experts about the dominance of risks. The weights are obtained by rescaling between 0 and 1 the eigenvectors relative to the maximum eigenvalue for the matrix of the coefficients. The internal coherence of the expert's attributions is defined through the calculation of the consistency ratio (Saaty, 1990). The result of the AHP method consists in a map of the UNESCO sites ranked according to the potential risk, where the site most at risk results to be the Geirangerfjord and Nærøyfjord in Norway. However, the quality of these results lies in the reliability of the Period Reports, which are produced by different experts with unknown level of scientific background. To test the reliability of these results, a comparison of the information of the periodic reports with available high-quality datasets (earthquake, volcano and landslide) at the Italian scale has been performed. Sites properly classified by the Period Reports range from

  5. Cost of implementing AECB interim criteria for the closeout of uranium tailings sites

    International Nuclear Information System (INIS)

    1981-04-01

    The main purpose of this study was to arrive at a gross approximation of the costs to the Canadian uranium mining industry of meeting the proposed closeout criteria established by the Atomic Energy Control Board for tailings deposits. Two options have been investigated: on-land disposal and underlake disposal. Given the budget allocated to the study, the estimates must be understood as approximations. Overall cost figures for the Canadian uranium mining industry are linear extensions from a hypothetical base case. The results of a conference held in Ottawa on February 25 and 26 to discuss the proposed AECB interim criteria for the closeout of uranium tailings sites are also included. Representatives from mining firms, provincial regulatory authorities, universities and the Atomic Energy Control board attended the conference

  6. Screening criteria of volcanic hazards aspect in the NPP site evaluation

    International Nuclear Information System (INIS)

    Nur Siwhan

    2013-01-01

    Studies have been conducted on the completeness of regulation in Indonesia particularly on volcanic hazards aspects in the evaluation of nuclear power plant site. Volcanic hazard aspect needed to identify potential external hazards that may endanger the safety of the operation of nuclear power plants. There are four stages for evaluating volcanic hazards, which are initial assessment, characterization sources of volcanic activity in the future, screening volcanic hazards and assessment of capable volcanic hazards. This paper discuss the third stage of the general evaluation which is the screening procedure of volcanic hazards. BAPETEN Chairman Regulation No. 2 Year of 2008 has only one screening criteria for missile volcanic phenomena, so it required screening criteria for other hazard phenomena that are pyroclastic flow density; lava flows; avalanche debris materials; lava; opening hole new eruptions, volcano missile; tsunamis; ground deformation; and hydrothermal system and ground water anomaly. (author)

  7. Preliminary interpretation of thermal data from the Nevada Test Site

    International Nuclear Information System (INIS)

    Sass, J.H.; Lachenbruch, A.H.

    1982-01-01

    Analysis of data from 60 wells in and around the Nevada Test Site, including 16 in the Yucca Mountain area, indicates a thermal regime characterized by large vertical and lateral gradients in heat flow. Estimates of heat flow indicate considerable variation on both regional and local scales. The variations are attributable primarily to hydrologic processes involving interbasin flow with a vertical component of (seepage) velocity (volume flux) of a few mm/yr. Apart from indicating a general downward movement of water at a few mm/yr, the reults from Yucca Mountain are as yet inconclusive. The purpose of the study was to determine the suitability of the area for proposed repository sites

  8. Multi-criteria GIS-based siting of an incineration plant for municipal solid waste.

    Science.gov (United States)

    Tavares, Gilberto; Zsigraiová, Zdena; Semiao, Viriato

    2011-01-01

    Siting a municipal solid waste (MSW) incineration plant requires a comprehensive evaluation to identify the best available location(s) that can simultaneously meet the requirements of regulations and minimise economic, environmental, health, and social costs. A spatial multi-criteria evaluation methodology is presented to assess land suitability for a plant siting and applied to Santiago Island of Cape Verde. It combines the analytical hierarchy process (AHP) to estimate the selected evaluation criteria weights with Geographic Information Systems (GIS) for spatial data analysis that avoids the subjectivity of the judgements of decision makers in establishing the influences between some criteria or clusters of criteria. An innovative feature of the method lies in incorporating the environmental impact assessment of the plant operation as a criterion in the decision-making process itself rather than as an a posteriori assessment. Moreover, a two-scale approach is considered. At a global scale an initial screening identifies inter-municipal zones satisfying the decisive requirements (socio-economic, technical and environmental issues, with weights respectively, of 48%, 41% and 11%). A detailed suitability ranking inside the previously identified zones is then performed at a local scale in two phases and includes environmental assessment of the plant operation. Those zones are ranked by combining the non-environmental feasibility of Phase 1 (with a weight of 75%) with the environmental assessment of the plant operation impact of Phase 2 (with a weight of 25%). The reliability and robustness of the presented methodology as a decision supporting tool is assessed through a sensitivity analysis. The results proved the system effectiveness in the ranking process. Copyright © 2011 Elsevier Ltd. All rights reserved.

  9. Coastal flooding as a parameter in multi-criteria analysis for industrial site selection

    Science.gov (United States)

    Christina, C.; Memos, C.; Diakoulaki, D.

    2014-12-01

    Natural hazards can trigger major industrial accidents, which apart from affecting industrial installations may cause a series of accidents with serious impacts on human health and the environment far beyond the site boundary. Such accidents, also called Na-Tech (natural - technical) accidents, deserve particular attention since they can cause release of hazardous substances possibly resulting in severe environmental pollution, explosions and/or fires. There are different kinds of natural events or, in general terms, of natural causes of industrial accidents, such as landslides, hurricanes, high winds, tsunamis, lightning, cold/hot temperature, floods, heavy rains etc that have caused accidents. The scope of this paper is to examine the coastal flooding as a parameter in causing an industrial accident, such as the nuclear disaster in Fukushima, Japan, and the critical role of this parameter in industrial site selection. Land use planning is a complex procedure that requires multi-criteria decision analysis involving economic, environmental and social parameters. In this context the parameter of a natural hazard occurrence, such as coastal flooding, for industrial site selection should be set by the decision makers. In this paper it is evaluated the influence that has in the outcome of a multi-criteria decision analysis for industrial spatial planning the parameter of an accident risk triggered by coastal flooding. The latter is analyzed in the context of both sea-and-inland induced flooding.

  10. Standards and guidelines pertinent to the development of decommissioning criteria for sites contaminated with radioactive material

    International Nuclear Information System (INIS)

    Dickson, H.W.

    1978-08-01

    A review of existing health and safety standards and guidelines has been undertaken to assist in the development of criteria for the decontamination and decommissioning of property contaminated with radioactive material. During the early years of development of the nuclear program in the United States, a number of sites were used which became contaminated with radioactive material. Many of these sites are no longer useful for nuclear activities, and the U.S. DOE desires to develop criteria for the management of these sites for future uses. Radiation protection standards promulgated by ICRP, NCRP, and ANSI have been considered. Government regulations, from the Code of Federal Regulations and the legal codes of various states, as well as regulatory guidelines with specific application to decommissioning of nuclear facilities also have been reviewed. In addition, recommendations of other scientific organizations such as the National Academy of Sciences/National Research Council Advisory Committee on the Biological Effects of Ionizing Radiations and the United Nations Scientific Committee on the Effects of Atomic Radiation were considered. Finally, a few specific recommendations and discussions from current literature were included. 28 references

  11. Program criteria for subseabed disposal of radioactive waste: site qualification plan

    International Nuclear Information System (INIS)

    Laine, E.P.; Anderson, D.R.; Hollister, C.D.

    1982-05-01

    This document describes the evolving methodology which is being used to identify, and study sites in subseabed geological formations which may be candidates for use as repositories for high-level nuclear waste. Two primary criteria guide all phases of this work: the stability and barrier criteria. The stability criterion defines areas of the seabed that are unlikely to be disturbed by tectonic forces and oceanographic changes durig the lifetime of a waste repository. The barrier criterion defines those subseabed geological formations most likely to form an effective barrier to the release of radionuclides. Because of the large area of the oceans, a phased approach has been adopted through which successively smaller areas of the sea floor are studied in ever greater detail. The first phase, which is complete, has identified abyssal clay deposits that are remote from tectonic boundaries and continental margins as being the regions (>10 5 km 2 ) on the sea floor within which acceptable sites might be most readily identified. The second phase involves downgrading less desirable areas (>10 4 km 2 ) within these regions, using archived seismic reflection profiling, sediment cores, and oceanographic data. This winnowing process identifies locations about one degree square (greater than or equal to 10 4 km 2 ) for more detailed field studies during the first part of the third phase. From these locations candidate sites (less than or equal to 10 4 km 2 ) will be chosen based on detailed geological and geophysical surveying. In the second part of the third phase, detailed monitoring of the candidate sites will begin to determine long-term baseline conditions. After monitoring is underway, a pilot repository will be established using waste canisters. Based on this work, a site selection/rejection report will be written. The fourth and last phase will involve extended monitoring of oceanographic conditions at each repository

  12. Nuclear safety criteria applied in site selection - the practice in France

    International Nuclear Information System (INIS)

    Candes, P.; Aussourd, Ph.

    1975-01-01

    In France, the safety of nuclear facilities is the responsibility of the Ministry for Industry and Research (Central Department for the Safety of Nuclear Facilities). The first part of the paper deals with the conception and contents of the site studies which are included in a safety report with the object of obtaining authorization to go ahead with work on the establishment of a facility. The conception is governed by the following two considerations: (a) the site is a place where the natural elements and living organisms occur and which is characterized by the permanent presence of the human factor, while the proposed nuclear facility will - like any industrial facility - present risks and have an impact on the site, particularly through the discharge of radioactive effluent and potentially in consequence of a nuclear accident; (b) the site exercises an influence - in fact, it even imposes constraints - on the nuclear facility. The site study as submitted by the operators to the authorities responsible for the safety evaluation traditionally consists of six sections, covering: (I) description and history of the site; (II) meteorological conditions; (III) hydrology of the area; (IV) geological and seismological conditions; (V) ecological factors; (VI) natural and/or previous radioactivity at the site. These six sections contain the data which serve as a basis for applying the two considerations spelled out above. However, the two corresponding directions of study and analysis do not settle the fundamental problem of the distribution of the population around the site. Methods for dealing with this problem are suggested in the second part of the paper; they take into account the efforts made so far at the international level. The authors consider that limiting criteria should not be based solely on the radioactive effluent discharges associated with normal operation but on the radioactivity releases associated with accidents. The methods proposed by them constitute

  13. Preliminary Safety Analysis of the Gorleben Site: Geological Database - 13300

    International Nuclear Information System (INIS)

    Weber, Jan Richard; Mrugalla, Sabine; Dresbach, Christian; Hammer, Joerg

    2013-01-01

    The Gorleben salt dome is 4 km wide and nearly 15 km long. It is composed of different salt rock types of the Zechstein (Upper Permian) series and extends to the Zechstein basis in a depth of more than 3 km. In the course of the salt dome formation the salt was moved several kilometers. During the uplift of the salt the initially plane-bedded strata of the Zechstein series were extensively folded. In this process anhydrite as a competent layer was broken to isolated blocks. In the core of the salt dome the Hauptsalz, which is characterized by a particularly high creeping capacity, forms a homogeneous halite body with a volume of several cubic kilometres. The Hauptsalz contains gaseous and liquid hydrocarbons in separated zones of decimeter to meter dimensions. The overall hydrocarbon content is far below 0.01 %. At the flanks the salt dome consists of salt rocks with lower creeping capacities. Brine reservoirs with fluid volumes in the range of liters to hundreds of cubic meters exist in certain regions of this part of the salt dome. The water content of the Hauptsalz is below 0.02 %. Interconnected pores do not exist in the salt rock outside of fluid bearing or fractured areas, i.e. the salt rock is impermeable. The exploration of the Gorleben site as a potential site for a HLW-repository started in 1979 and is still in progress. To date no scientific findings contest the suitability of the site for a safe HLW-repository. (authors)

  14. Acceptance criteria for the physical protection upgrade rule requirements for fixed sites. Information guide

    International Nuclear Information System (INIS)

    Dwyer, P.

    1980-09-01

    This document has been developed as a tool to assist in providing consistent evaluation of upgraded physical security plans submitted in response to the Physical Protection Upgrade Rule, effective March 25, 1980. It presents a means for assuring licensee compliance with every regulatory requirement of particular significance to the protection of the public health and safety. Acceptance criteria are included to determine the extent to which each licensee meets the regulatory requirements. The format parallels Regulatory Guide 5.52, Standard Format and Content of a Licensee Physical Protection Plan for Strategic Special Nuclear Material at Fixed Sites

  15. Development of a design basis tornado and structural design criteria for Lawrence Livermore Laboratory's Site 300

    International Nuclear Information System (INIS)

    McDonald, J.R.; Minor, J.E.; Mehta, K.C.

    1975-11-01

    Criteria are prescribed and guidance is provided for professional personnel who are involved with the evaluation of existing buildings and facilities at Site 300 near Livermore, California to resist the possible effects of extreme winds and tornadoes. The development of parameters for the effects of tornadoes and extreme winds and guidelines for evaluation and design of structures are presented. The investigations conducted are summarized and the techniques used for arriving at the combined tornado and extreme wind risk model are discussed. The guidelines for structural design methods for calculating pressure distributions on walls and roofs of structures and methods for accommodating impact loads from missiles are also presented

  16. Defining waste acceptance criteria for the Hanford Replacement Cross-Site Transfer System

    International Nuclear Information System (INIS)

    Hudson, J.D.

    1996-04-01

    This document provides a methodology for defining waste acceptance criteria for the Hanford Replacement Cross-Site Transfer System (RCSTS). This methodology includes characterization, transport analysis, and control. A framework is described for each of these functions. A tool was developed for performing the calculations associated with the transport analysis. This tool, a worksheet that is available in formats acceptable for a variety of PC spreadsheet programs, enables a comparison of the pressure required to transport a given slurry at a rate that particulate suspension is maintained to the pressure drop available from the RCSTS

  17. Status policy and criteria for the remediation of sites with radioactive residues in China

    International Nuclear Information System (INIS)

    Yamin, Z.

    1999-01-01

    This paper introduces the status policy and criteria for remediation of sites with radioactive residues in China. We deal with the sites in difference patterns according to their circumstances. For the sites related with the decommissioning of the nuclear fuel cycle facilities, the programs for environmental restoration must be reviewed and approved by the State Environmental Protection Administration (SEPA). And the radioactive waste resulting from these facilities should be collected and eventually disposed of at the regional disposal repositories built by the country. For the sites related with use of radionuclides in medicine, research and industry, as well as the small scale extraction and processing of materials containing natural radionuclides, the provincial environmental authority is responsible for approving the restoration projects. These radioactive wastes should finally be sent to the special radioactive waste repositories built by the provincial environmental authorities. So far 21 waste repositories have been built in some provinces. More then 10 sites with radioactive residues have been restored. The standards for general public dose limit and soil residual radionuclides content have been established. (author)

  18. Development of closure criteria for inactive radioactive waste disposal sites at Oak Ridge National Laboratory

    International Nuclear Information System (INIS)

    Kocher, D.C.

    1989-01-01

    The Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA), as amended, specifies that cleanup of inactive waste disposal sites at Department of Energy (DOE) facilities shall at least attain legally applicable or relevant and appropriate requirements (ARARs) for cleanup or control of environmental contamination. This paper discusses potential ARARs for cleanup of inactive radioactive waste disposal sites and proposes a set of closure criteria for such sites at Oak Ridge National Laboratory (ORNL). The most important potential ARARs include Federal standards for radiation protection of the public, radioactivity in drinking water, and near-surface land disposal of radioactive wastes. On the basis of these standards, we propose that cleanup and closure of inactive radioactive waste disposal sites at ORNL shall achieve (1) limits on annual effective dose equivalent for off-site individuals and inadvertent intruders that conform to the DOE's performance objectives for new low-level waste disposal facilities and (2) to the extent reasonably achievable, limits on radionuclide concentrations in ground water and surface waters in accordance with Federal drinking water standards and ground-water protection requirements

  19. Criteria for safety-related nuclear plant operator actions: a preliminary assessment of available data

    International Nuclear Information System (INIS)

    Haas, P.M.; Bott, T.F.

    1980-01-01

    In the US, an effort has been underway for a number of years to develop a design standard to define when required manual operator action can be accepted as part of a nuclear plant design basis. Insufficient data are available to provide quantitative guidelines for the standard. To provide the necessary data base to support such standards and the necessary quantitative assessment of operator reliability, the US Nuclear Regulatory Commission is sponsoring a study at Oak National Laboratory to develop the data base. A preliminary assessment completed in April, 1979 concluded that sufficient data from US operating experience did not exist to provide an adequate data base. A program of research using full-scope nuclear plant simulators and results that are correlated to field data was suggested. That program was recently initiated. The approach, results and conclusions of the preliminary assessment are reviewed and the planned research program of simulator studies is summarised. (author)

  20. Development of Preliminary Remission Criteria for Gout Using Delphi and 1000Minds® Consensus Exercises

    DEFF Research Database (Denmark)

    de Lautour, Hugh; Taylor, William J; Adebajo, Ade

    2016-01-01

    OBJECTIVES: The aim of this study was to establish consensus for potential remission criteria for use in clinical trials of gout. METHODS: Experts (n=88) in gout from multiple countries were invited to participate in a web-based questionnaire study. Three rounds of Delphi consensus exercises were...... months (51%) and one year (49%). In the discrete choice experiment, there was a preference towards 12 months as a timeframe for remission. CONCLUSION: These consensus exercises have identified domains and provisional definitions for gout remission criteria. Based on the results of these exercises...

  1. Interim criteria for Organic Watch List tanks at the Hanford Site

    International Nuclear Information System (INIS)

    Babad, S.; Turner, D.A.

    1993-09-01

    This document establishes interim criteria for identifying single-shell radioactive waste storage tanks at the Hanford Site that contain organic chemicals mixed with nitrate/nitrite salts in potentially hazardous concentrations. These tanks are designated as ''organic Watch List tanks.'' Watch List tanks are radioactive waste storage tanks that have the potential for release of high-level waste as a result of uncontrolled increases in temperature or pressure. Organic Watch List tanks are those Watch List tanks that contain relatively high concentrations of organic chemicals. Because of the potential for release of high-level waste resulting from uncontrolled increases in temperature or pressure, the organic Watch List tanks (collectively) constitute a Hanford Site radioactive waste storage tank ''safety issue.''

  2. Requirements and criteria for choosing sites suitable for the construction of nuclear installations and power stations

    International Nuclear Information System (INIS)

    1978-05-01

    The present document explains the selection criteria for areas in Italy suitable for the installation of nuclear power stations to be included in the 'National Site Map' provided for in Section 23 of Act No 393 of 2 August 1975. It represents the results of a thorough investigation into the various aspects of the problem of siting nuclear power stations, at the present stage of technology, taking into account the effect of the installations on the environment and the effect of the environment on the installations. The essential aim is to demonstrate that the requirements derived from these analyses, and on which there was full consultation with the other controlling bodies of European countries (in particular, France, Great Britain and West Germany) ensure the optimum choice of areas from the point of view of safety and public health. (author)

  3. Preliminary post-closure safety assessment of repository concepts for low level radioactive waste at the Bruce Site, Ontario

    International Nuclear Information System (INIS)

    Little, R.H.; Penfold, J.S.S.; Egan, M.J.; Leung, H.

    2005-01-01

    The preliminary post-closure safety assessment of permanent repository concepts for low-level radioactive waste (LLW) at the Ontario Power Generation (OPG) Bruce Site is described. The study considered the disposal of both short and long-lived LLW. Four geotechnically feasible repository concepts were considered (two near-surface and two deep repositories). An approach consistent with best international practice was used to provide a reasoned and comprehensive analysis of post-closure impacts of the repository concepts. The results demonstrated that the deep repository concepts in shale and in limestone, and the surface repository concept on sand should meet radiological protection criteria. For the surface repository concept on glacial till, it appears that increased engineering such as grouting of waste and voids should be considered to meet the relevant dose constraint. Should the project to develop a permanent repository for LLW proceed, it is expected that this preliminary safety assessment would need to be updated to take account of future site-specific investigations and design updates. (author)

  4. Towards understanding household-level forest reliance in Cambodia - study sites, methods, and preliminary findings

    DEFF Research Database (Denmark)

    Ra, Koy; Pichdara, Lonn; Dararath, Yem

    There is growing international interest in the role of forests in poverty prevention and reduction. In consequence, this broad area of investigation has been subject to increased research; one major international research project is that facilitated by the Poverty Environment Network (PEN). This ......). This project covers a large number of sites in 26 countries throughout the tropics. The present report contains contextual details, methodological information and preliminary findings for the PEN sites in Cambodia....

  5. Chemical Analysis of the Moon at the Surveyor VII Landing Site: Preliminary Results.

    Science.gov (United States)

    Turkevich, A L; Franzgrote, E J; Patterson, J H

    1968-10-04

    The alpha-scattering experiment aboard Surveyor VII has provided a chemical analysis of the moon in the area of the crater Tycho. The preliminary results indicate a chemical composition similar to that already found at two mare sites, but with a lower concentration of elements of the iron group (titanium through copper).

  6. How can UNESCO World Heritage Criteria be applied to the ``Windows to the Universe'' Sites?

    Science.gov (United States)

    Cotte, Michel

    2016-10-01

    This communication proposes a methodical approach trying to link the concept of ``Windows to the Universe'' to the uses of the Criteria defined by the World Heritage Convention (UNESCO 1972). The first issue is well advanced today after more than 10 years of active studies and preservation projects such as ``Starlight Reserves'' by specialists of astronomy, archaeoastronomy and environmental sciences. The second issue is related to a UNESCO Convention ruled by the WH Committee that has led to the recognition of around 1000 World Heritage sites over 40 years. The official booklet Operational Guidelines for the Implementation of the World Heritage Convention (latest edition 2015) (UNESCO 2015) summarizes conceptual ideas and methodological recommendations for WH nominations. In practice the WH Committee's decisions rely on the scientific and professional evaluation of each site by UNESCO's advisory bodies: ICOMOS for cultural heritage and IUCN for natural heritage. The first goal of this presentation is to establish appropriate understanding of a very specific conceptual approach (Windows to the Universe) in the context of a very large UN Convention (the World Heritage List) related both to cultural and natural heritage in general. The second goal is to give a readable understanding of the WH requirements coming from the strict evaluation of the ``Outstanding Universal Value'' (OUV) of a given place, including the choice of WH Criteria expressing OUV with respect to the format of the Guidelines. Furthermore, and due to concepts coming from two very different fields, the communication aims to present a practical methodology in the case of a possible WH nomination: how to understand relationships between different classes of value and how to demonstrate OUV and justify the choice of Criteria for the place. Beyond potential WH projects, obviously limited in number, the communication tries to propose an efficient and general methodology for assessing the value and

  7. The evaluation of effective criteria on site selection for energy production units from cellulosic biomass in Iran

    Directory of Open Access Journals (Sweden)

    Majid Azizi

    2017-12-01

    Full Text Available Both Analytical Hierarchy Process (AHP and benefits, opportunities, costs and risks (BOCR techniques were used successfully to evaluate the effective criteria on site selection for energy production unit development from cellulosic biomass in Iran. The results showed that the benefits criteria was at the first level while the initial cellulosic raw materials and opportunities with the aim of the local economy had the second position as the most important indices on site selection. In addition, third criterion has been introduced for the costs criteria (transportation cost and social barriers by the experts. However, risks criteria which referred to instability of providing cellulosic raw materials is one of the less important effective indices on site selection to make energy production unit. The results illustrated that the economy and politics as two environmental effective factors affected on the site selection process generally.

  8. Workshops for state review of site suitability criteria for high-level radioactive waste repositories: analysis and recommendations

    International Nuclear Information System (INIS)

    1978-02-01

    The responses from various discussion groups on site suitability criteria for high-level radioactive waste repositories are presented. The consensus, principal concern, and minority opinion on each issue are given. The visual aids used in the workshop are included

  9. Preliminary Hazard Classification for the Remediation of the 100-B/C Area Remaining Sites (Confirmatory Sampling Effort)

    International Nuclear Information System (INIS)

    Routt, T.M.

    2000-01-01

    This document provides the preliminary hazard classification for the sampling and characterization activities to be conducted at the 100-B/C confirmatory sampling effort sites in support of remedial design and eventual remediation of these sites

  10. Siting a municipal solid waste disposal facility, part II: the effects of external criteria on the final decision.

    Science.gov (United States)

    Korucu, M Kemal; Karademir, Aykan

    2014-02-01

    The procedure of a multi-criteria decision analysis supported by the geographic information systems was applied to the site selection process of a planning municipal solid waste management practice based on twelve different scenarios. The scenarios included two different decision tree modes and two different weighting models for three different area requirements. The suitability rankings of the suitable sites obtained from the application of the decision procedure for the scenarios were assessed by a factorial experimental design concerning the effect of some external criteria on the final decision of the site selection process. The external criteria used in the factorial experimental design were defined as "Risk perception and approval of stakeholders" and "Visibility". The effects of the presence of these criteria in the decision trees were evaluated in detail. For a quantitative expression of the differentiations observed in the suitability rankings, the ranking data were subjected to ANOVA test after a normalization process. Then the results of these tests were evaluated by Tukey test to measure the effects of external criteria on the final decision. The results of Tukey tests indicated that the involvement of the external criteria into the decision trees produced statistically meaningful differentiations in the suitability rankings. Since the external criteria could cause considerable external costs during the operation of the disposal facilities, the presence of these criteria in the decision tree in addition to the other criteria related to environmental and legislative requisites could prevent subsequent external costs in the first place.

  11. Criteria for safety related nuclear plant operator actions: a preliminary assessment of available data

    International Nuclear Information System (INIS)

    Haas, P.M.; Bott, T.F.

    1982-01-01

    The need for a quantitative data base on the reliability of nuclear power plant operators has long been recognised by human factors and reliability analysts, and the great need for further assessment of operator performance under accident conditions has been dramatically emphasised by the incident at Three Mile Island-2. In the US, an effort has been under way for a number of years to develop a design standard to define when required manual operator action can be accepted as part of a nuclear plant design basis. To provide the necessary data base to support such standards and the necessary quantitative assessment of operator reliability, the US Nuclear Regulatory Commission is sponsoring a study at Oak Ridge National Laboratory to develop the data base. A preliminary assessment, completed in April 1979, concluded that sufficient data from US operating experience did not exist to provide an adequate data base. A programme of research using full-scope nuclear plant simulators and results that are correlated to field data was suggested. That programme was recently initiated. This paper reviews the approach, results and conclusions of the preliminary assessment and summarises the planned research programme of simulator studies. (author)

  12. Preliminary site requirements and considerations for a monitored retrievable storage facility

    International Nuclear Information System (INIS)

    1991-08-01

    This report presents preliminary requirements and considerations for siting monitored retrievable storage (MRS) facility. It purpose is to provide guidance for assessing the technical suitability of potential sites for the facility. It has been reviewed by the NRC staff, which stated that this document is suitable for ''guidance in making preliminary determinations concerning MRS site suitability.'' The MRS facility will be licensed by the US Nuclear Regulatory Commission. It will receive spent fuel from commercial nuclear power plants and provide a limited amount of storage for this spent fuel. When a geologic repository starts operations, the MRS facility will also stage spent-fuel shipments to the repository. By law, storage at the MRS facility is to be temporary, with permanent disposal provided in a geologic repository to be developed by the DOE

  13. Full perimeter intersection criteria. Definitions and implementations in SR-Site

    Energy Technology Data Exchange (ETDEWEB)

    Munier, Raymond

    2010-03-15

    Large fractures intersecting canisters have potential to reactivate due to nearby earthquakes and thereby jeopardising the canister/buffer integrity. The use of full perimeter intersection (FPI) as a proxy for fracture size has been explored within SKB since late 2004. A methodology to use FPI as a deposition hole rejection criterion was first reported in and the concept has successively matured ever since. As a response to feedback obtained from various instances of our organisation and external reviewers, additional analyses and benchmarks were reported in 2007. An analytical solution to the canister/fracture intersection probability was introduced, which enabled us to benchmark various aspects of the FPI simulations. The methodology was first applied within the framework of SR-CAN to compute the number of potentially critical canister positions and soon after, based on preliminary DFN models, as one of many prerequisites for repository design. The methodology and simulation logic has evolved substantially ever since it was originally reported in 2006 and the present report is intended to entirely replace previous reports on this subject, to thereby provide the interested reader with an description of the modelling procedure, prerequisites and limitations. As a consequence thereof, major portions of previous reports are repeated herein, though we occasionally refer to these reports for comparative purposes. Furthermore, as the final versions of the site descriptive models have been reported we find it convenient to, within this report, also apply the methodology using the most actual site specific fracture data

  14. Evaluation of population density and distribution criteria in nuclear power plant siting

    International Nuclear Information System (INIS)

    Young, M.

    1994-06-01

    The NRC has proposed revisions to 10 CFR 100 which include the codification of nuclear reactor site population density limits to 500 people per square mile, at the siting stage, averaged over any radial distance out to 30 miles, and 1,000 people per square mile within the 40-year lifetime of a nuclear plant. This study examined whether there are less restrictive alternative population density and/or distribution criteria which would provide equivalent or better protection to human health in the unlikely event of a nuclear accident. This study did not attempt to directly address the issue of actual population density limits because there are no US risk standards established for the evaluation of population density limits. Calculations were performed using source terms for both a current generation light water reactor (LWR) and an advanced light water reactor (ALWR) design. The results of this study suggest that measures which address the distribution of the population density, including emergency response conditions, could result in lower average individual risks to the public than the proposed guidelines that require controlling average population density. Studies also indicate that an exclusion zone size, determined by emergency response conditions and reactor design (power level and safety features), would better serve to protect public health than a rigid standard applied to all sites

  15. A preliminary analysis of the risk of transporting nuclear waste to potential candidate commercial repository sites

    International Nuclear Information System (INIS)

    Madsen, M.M.

    1984-01-01

    In accordance with the provisions of the Nuclear Waste Policy Act of 1982, environmental assessments for potential candidate sites are required to provide a basis for selection of the first site for disposal of commercial radioactive waste in deep geologic repositories. A preliminary analysis of the impacts of transportation for each of the five potential sites will be described. Transportation was assumed to be entirely by truck or entirely by rail in order to obtain bounding impacts. This paper presents both radiological and nonradiological risks for the once-through fuel cycle

  16. Preliminary investigation on determination of radionuclide distribution in field tracing test site

    International Nuclear Information System (INIS)

    Tanaka, Tadao; Mukai, Masayuki; Takebe, Shinichi; Guo Zede; Li Shushen; Kamiyama, Hideo.

    1993-12-01

    Field tracing tests for radionuclide migration have been conducted by using 3 H, 60 Co, 85 Sr and 134 Cs, in the natural unsaturated loess zone at field test site of China Institute for Radiation Protection. It is necessary to obtain confidable distribution data of the radionuclides in the test site, in order to evaluate exactly the migration behavior of the radionuclides in situ. An available method to determine the distribution was proposed on the basis of preliminary discussing results on sampling method of soils from the test site and analytical method of radioactivity in the soils. (author)

  17. Fort Hood Solar Total Energy Project. Volume II. Preliminary design. Part 1. System criteria and design description. Final report

    Energy Technology Data Exchange (ETDEWEB)

    None,

    1979-01-01

    This volume documents the preliminary design developed for the Solar Total Energy System to be installed at Fort Hood, Texas. Current system, subsystem, and component designs are described and additional studies which support selection among significant design alternatives are presented. Overall system requirements which form the system design basis are presented. These include program objectives; performance and output load requirements; industrial, statutory, and regulatory standards; and site interface requirements. Material in this section will continue to be issued separately in the Systems Requirements Document and maintained current through revision throughout future phases of the project. Overall system design and detailed subsystem design descriptions are provided. Consideration of operation and maintenance is reflected in discussion of each subsystem design as well as in an integrated overall discussion. Included are the solar collector subsystem; the thermal storage subsystem, the power conversion sybsystem (including electrical generation and distribution); the heating/cooling and domestic hot water subsystems; overall instrumentation and control; and the STES building and physical plant. The design of several subsystems has progressed beyond the preliminary stage; descriptions for such subsystems are therefore provided in more detail than others to provide complete documentation of the work performed. In some cases, preliminary design parameters require specific verificaton in the definitive design phase and are identified in the text. Subsystem descriptions will continue to be issued and revised separately to maintain accuracy during future phases of the project. (WHK)

  18. A Fuzzy Multi-Criteria SWOT Analysis: An Application to Nuclear Power Plant Site Selection

    Directory of Open Access Journals (Sweden)

    Mehmet Ekmekcioglu

    2011-08-01

    Full Text Available SWOT (Strengths, Weaknesses, Opportunities and Threats analysis is a commonly used and an important technique for analyzing internal and external environments in order to provide a systematic approach and support for a decision making. SWOT is criticized mostly for considering only qualitative examination of environmental factors, no priority for various factors and strategies, and no vagueness of the factors under fuzziness. In this paper, fuzzy TOPSIS (Technique for Order Preference by Similarity to Ideal Solution integrated with fuzzy AHP (Analytical Hierarchy Process is used to develop fuzzy multi-criteria SWOT analysis in order to overcome these shortcomings. Nuclear power plant site selection, which is a strategic and important issue for Turkeyrs energy policy making, is considered as an application case study that demonstrated the applicability of the developed fuzzy SWOT model.

  19. Site selection and rating process, and criteria for a social and political approach

    International Nuclear Information System (INIS)

    Boisseson, P. de; David, J.F.

    1998-01-01

    Full text of publication follows: sensitive projects have been for long the problem of engineers and geologists, which tried to exert a kind of mono-cultural approach upon decisions regarding: a type of technical solution, a choice for a location. Experience drawn from various projects shows that public choices must be targeted to public acceptance and not only to hard-science community. Ways of rating site for sensitive projects according to criteria derived from social and political approach have been set up to provide global advice to decision makers. Bases are found among: socio economical statistics (type and rate of employment), land use regulations, history of public and local acceptance of former projects or public regulations. Representations can be drawn through social modeling and qualitative analysis. They can be of an utmost importance in decision making process. (authors)

  20. Draft environmental impact statement. High-level waste repository site suitability criteria

    International Nuclear Information System (INIS)

    1978-01-01

    The purpose of HLWRSSC is to present guidelines which will help in the development of safe waste management schemes. Current regulations require solidification of all high-level waste within 5 years of their generation and transfer to a Federal waste repository within 10 years. Development of the proposed HLWRSSC is part of the overall NRC program to close the ''back end'' of the commercial LWR fuel cycle. In this document, the need for the HLWRSSC is reviewed, and the national energy policy, the need for electrical energy, and the nuclear fuel cycle are discussed. Considerations for HLWRSSC are presented, including the nature of the repository, important site-related factors, and radiological risk assessment methodology. Radiological and nonradiological environment impacts associated with the HLWRSSC are defined. Alternatives to the criteria are presented, and the cost-benefit-risk evaluation is reviewed

  1. Criteria and approaches for the remediation of sites contaminated with natural radionuclides in Germany

    International Nuclear Information System (INIS)

    Goldammer, W.

    1999-01-01

    In some parts of Germany substantial areas have been contaminated with naturally occurring radioactive material (NORM) from past activities. Particularly important are residues from past uranium mining operations (WISMUT), being subject to a massive 13 billion DM cleanup program, as well as other mining activities dealing with elevated levels of NORM. Decisions concerning the necessity and the required extent of remediation measures are based on a combination of criteria addressing limitations of maximum individual doses for critical groups as well as the optimization of the net benefit from the remediation. From these basic requirements secondary criteria have been derived, defining, for example, soil contamination levels below which a remediation is not required. The optimization analyses, carried-out to identify optimal remediation options, address radiological risks as well as short and long term costs within a cost-benefit analysis framework. Other relevant factors of influence, e.g. chemical risks or ecological damage, are incorporated as well. Comprehensive methodologies utilizing probabilistic methods have been developed to assess site conditions and possible remediation options on this basis. (author)

  2. Lyme Neuroborreliosis: Preliminary Results from an Urban Referral Center Employing Strict CDC Criteria for Case Selection

    Directory of Open Access Journals (Sweden)

    David S. Younger

    2010-01-01

    Full Text Available Lyme neuroborreliosis or “neurological Lyme disease” was evidenced in 2 of 23 patients submitted to strict criteria for case selection of the Centers for Disease Control and Prevention employing a two-tier test to detect antibodies to Borrelia burgdorferi at a single institution. One patient had symptomatic polyradiculoneuritis, dysautonomia, and serological evidence of early infection; and another had symptomatic small fiber sensory neuropathy, distal polyneuropathy, dysautonomia, and serological evidence of late infection. In the remaining patients symptoms initially ascribed to Lyme disease were probably unrelated to B. burgdorferi infection. Our findings suggest early susceptibility and protracted involvement of the nervous system most likely due to the immunological effects of B. burgdorferi infection, although the exact mechanisms remain uncertain.

  3. Preliminary classification criteria for the antiphospholipid syndrome within systemic lupus erythematosus.

    Science.gov (United States)

    Alarcón-Segovia, D; Pérez-Vázquez, M E; Villa, A R; Drenkard, C; Cabiedes, J

    1992-04-01

    Ten percent of 667 consecutive systemic lupus erythematosus (SLE) patients were considered to have definite antiphospholipid syndrome (aPLS) because they had two or more antiphospholipid (aPL)-related clinical manifestations and aPL titers more than 5 SD above the mean of normal controls. Another 14% had either one aPL-related manifestation but high titers of the antibody or two manifestations and low aPL titers (probable aPLS). One fourth of the patients had no manifestations but high titers, one manifestation and low titers, or two or more manifestations and negative aPL titers ("doubtful" aPLS); the other half were considered negative for aPLS. In patients with high-titer aPL, the number of aPL-related manifestations was influenced by disease duration and number of pregnancies, indicating potential mobility of category with time or with risk of recurrent pregnancy loss. Patients with two or more manifestations but variable aPL levels differed in immunosuppressive treatment and in the number of times they had been tested, indicating potential mobility of category with lower treatment and/or further aPL testing. Patients with definite aPLS had increased risk of cutaneous vasculitis, peripheral neuropathy, seizures, psychosis, transient ischemic attacks, and leukopenia. In 11 of 52 SLE patients with definite aPLS the initial manifestation was related to aPL, and in 16 it concurred with an unrelated one. Only two patients fulfilled criteria for aPLS before having other evidence of SLE. The authors conclude that aPLS occurring within SLE is part of the disease rather than an associated condition and propose the use of definite and probable classification categories. These criteria, with appropriate follow-up and clinical and serological exclusion clauses for potential primary conditions, could also be applied to primary aPLS.

  4. Review of criterias for shallow burial sites and geohydrological evaluation around the site of temporary storage of low-level solid radioactive wastes of IPEN-CNEN/SP

    International Nuclear Information System (INIS)

    Chandra, U.; Marcelino, S.

    1986-01-01

    Some comments about norms of pollutants release from nuclear and other industries are made. For radioactive discharges, the strictly implemented national norms/criterias, are much more advanced technically than those existing for other pollutants. Based on the criterias of site selection and site evaluations, the site of IPEN for temporary storage of low level solid radioactive waster has been evaluated geohydrologically. Rainfall infiltration rate (297 cm/y) was determined by tritium labelling technique. Ground water velocity (max. 46.1 cm/d) and direction (to north) was determined by various radioactive (Br-82, I-131, Cr-51) tracers using single well techniques. (Author) [pt

  5. Site study plan for Transportation, Deaf Smith County Site, Texas: Preliminary draft

    International Nuclear Information System (INIS)

    1987-06-01

    This site study plan describes transportation field studies to be conducted during the characterization of the Deaf Smith County, Texas, site for the US Department of Energy's Salt Repository Project. The studies are needed to identify and assess potential project impacts to transportation infrastructure and systems in the project vicinity and along potential transportation routes to the site across the State of Texas. The studies are also needed to locate and design project transportation facilities, and to evaluate and design impact mitigation. After identifying the transportation information requirements needed to comply with Federal, State, and local regulations and repository program requirements, the site study plan describes the study design and rationale, the field data collection procedures and equipment, the data analysis methods and application of results, the data management strategy, the schedule of field activities, the management of the study, and the study's quality assurance program. The field data collection activities are organized into programs for the characterization of site vicinity rail corridors and highway corridors, characterization of alternative statewide transportation routes, monitoring of site characterization effects on transportation, characterization of aircraft overflight patterns and hazardous material transportation patterns, and assessment of emergency response preparedness along alternative statewide transportation routes. 34 refs., 10 figs., 2 tabs

  6. The Japanese version of the modified ACR preliminary diagnostic criteria for fibromyalgia and the fibromyalgia symptom scale: reliability and validity.

    Science.gov (United States)

    Usui, Chie; Hatta, Kotaro; Aratani, Satoko; Yagishita, Naoko; Nishioka, Kenya; Kanazawa, Teruhisa; Itoh, Kenji; Yamano, Yoshihisa; Nakamura, Hiroyuki; Nakajima, Toshihiro; Nishioka, Kusuki

    2013-09-01

    The aim of this study is to investigate the reliability and validity of the Japanese version of the modified American College of Rheumatology (ACR) Preliminary Diagnostic Criteria for Fibromyalgia (mACR 2010-J) and the Fibromyalgia Symptom Scale (mFS-J). According to the ACR 1990 classification criteria, patients with chronic pain were divided into the fibromyalgia group and nonfibromyalgia group (rheumatoid arthritis and osteoarthritis). Patients in both groups were assessed using mACR 2010-J and mFS-J. 294 of 462 (64 %) patients in the fibromyalgia group met mACR 2010-J, whereas 4 % (9/231) of the nonfibromyalgia group did, with sensitivity of 64 %, specificity of 96 %, positive predictive value of 97 %, negative predictive value of 56 %, and positive likelihood ratio of 16.3. Mean total scores on mFS-J significantly differentiated the fibromyalgia from the nonfibromyalgia group. According to the value of the Youden index, the best cutoff score for the mFS-J was 9/10. Our findings indicate that mACR 2010-J as a positive test and mFS-J as a quantification scale might be suitable for assessing fibromyalgia among Japanese chronic pain populations.

  7. Landfill Site Selection by AHP Based Multi-criteria Decision Making Tool: A Case Study in Kolkata, India

    Science.gov (United States)

    Majumdar, Ankush; Hazra, Tumpa; Dutta, Amit

    2017-09-01

    This work presents a Multi-criteria Decision Making (MCDM) tool to select a landfill site from three candidate sites proposed for Kolkata Municipal Corporation (KMC) area that complies with accessibility, receptor, environment, public acceptability, geological and economic criteria. Analytical Hierarchy Process has been used to solve the MCDM problem. Suitability of the three sites (viz. Natagachi, Gangajoara and Kharamba) as landfills as proposed by KMC has been checked by Landfill Site Sensitivity Index (LSSI) as well as Economic Viability Index (EVI). Land area availability for disposing huge quantity of Municipal Solid Waste for the design period has been checked. Analysis of the studied sites show that they are moderately suitable for landfill facility construction as both LSSI and EVI scores lay between 300 and 750. The proposed approach represents an effective MCDM tool for siting sanitary landfill in growing metropolitan cities of developing countries like India.

  8. Radiation shielding aspects for long manned mission to space - Criteria, survey study and preliminary model

    International Nuclear Information System (INIS)

    Sztejnberg, M.; Xiao, S.; Satvat, N.; Limon, F.; Hopkins, J.; Jevremovic, T.; T. Jevremovic)

    2006-01-01

    The prospect of manned space missions out side Earth's or bit is limited by the travel time and shielding against cosmic radiation. The chemical rockets currently used in the space program have no hope of propelling a manned vehicle to a far away location such as Mars due to the enormous mass of fuel that would be required. The specific energy available from nuclear fuel is a factor of 106 higher than chemical fuel; it is there fore obvious that nuclear power production in space is a must. On the other hand, recent considerations to send a man to the Moon for a long stay would require a stable, secured, and safe source of energy (there is hardly anything beyond nuclear power that would provide a useful and reliably safe sustainable supply of energy). National Aeronautics and Space Administration (NASA) anticipates that the mass of a shielding material required for long travel to Mars is the next major design driver. In 2006 NASA identified a need to assess and evaluate potential gaps in existing knowledge and understanding of the level and types of radiation critical to astronauts' health during the long travel to Mars and to start a comprehensive study related to the shielding design of a spacecraft finding the conditions for the mitigation of radiation components contributing to the doses beyond accepted limits. In order to reduce the overall space craft mass, NASA is looking for the novel, multi-purpose and multi-functional materials that will provide effective shielding of the crew and electronics on board. The Laboratory for Neutronics and Geometry Computation in the School of Nuclear Engineering at Purdue University led by Prof. Tatjana Jevremovic began in 2004 the analytical evaluations of different lightweight materials. The preliminary results of the design survey study are presented in this paper. (author)

  9. Radiation shielding aspects for long manned mission to space: Criteria, survey study, and preliminary model

    Directory of Open Access Journals (Sweden)

    Sztejnberg Manuel

    2006-01-01

    Full Text Available The prospect of manned space missions outside Earth's orbit is limited by the travel time and shielding against cosmic radiation. The chemical rockets currently used in the space program have no hope of propelling a manned vehicle to a far away location such as Mars due to the enormous mass of fuel that would be required. The specific energy available from nuclear fuel is a factor of 106 higher than chemical fuel; it is therefore obvious that nuclear power production in space is a must. On the other hand, recent considerations to send a man to the Moon for a long stay would require a stable, secured and safe source of energy (there is hardly anything beyond nuclear power that would provide a useful and reliably safe sustainable supply of energy. National Aeronautics and Space Administration (NASA anticipates that the mass of a shielding material required for long travel to Mars is the next major design driver. In 2006 NASA identified a need to assess and evaluate potential gaps in existing knowledge and understanding of the level and types of radiation critical to astronauts' health during the long travel to Mars and to start a comprehensive study related to the shielding design of a spacecraft finding the conditions for the mitigation of radiation components contributing to the doses beyond accepted limits. In order to reduce the overall space craft mass, NASA is looking for the novel, multi-purpose and multi-functional materials that will provide effective shielding of the crew and electronics on board. The Laboratory for Neutronics and Geometry Computation in the School of Nuclear Engineering at Purdue University led by Prof. Tatjana Jevremović began in 2004 the analytical evaluations of different lightweight materials. The preliminary results of the design survey study are presented in this paper.

  10. Preliminary Evaluation of Removing Used Nuclear Fuel From Nine Shutdown Sites

    Energy Technology Data Exchange (ETDEWEB)

    Maheras, Steven J.; Best, Ralph; Ross, Steven B.; Buxton, Kenneth A.; England, Jeffery L.; McConnell, Paul

    2013-04-30

    The Blue Ribbon Commission on America’s Nuclear Future identified removal of stranded used nuclear fuel at shutdown sites as a priority so that these sites may be completely decommissioned and put to other beneficial uses. In this report, a preliminary evaluation of removing used nuclear fuel from nine shutdown sites was conducted. The shutdown sites included Maine Yankee, Yankee Rowe, Connecticut Yankee, Humboldt Bay, Big Rock Point, Rancho Seco, Trojan, La Crosse, and Zion. At these sites a total of 7649 used nuclear fuel assemblies and a total of 2813.2 metric tons heavy metal (MTHM) of used nuclear fuel are contained in 248 storage canisters. In addition, 11 canisters containing greater-than-Class C (GTCC) low-level radioactive waste are stored at these sites. The evaluation was divided in four components: • characterization of the used nuclear fuel and GTCC low-level radioactive waste inventory at the shutdown sites • an evaluation of the onsite transportation conditions at the shutdown sites • an evaluation of the near-site transportation infrastructure and experience relevant to the shipping of transportation casks containing used nuclear fuel from the shutdown sites • an evaluation of the actions necessary to prepare for and remove used nuclear fuel and GTCC low-level radioactive waste from the shutdown sites. Using these evaluations the authors developed time sequences of activities and time durations for removing the used nuclear fuel and GTCC low-level radioactive waste from a single shutdown site, from three shutdown sites located close to each other, and from all nine shutdown sites.

  11. Preliminary Geological Survey on the Proposed Sites for the New Research Reactor

    International Nuclear Information System (INIS)

    Lim, In Cheol; Ha, J. J.; Oh, K. B.

    2010-12-01

    · Performing the preliminary geological survey on the proposed sites for the new research reactor through the technical service · Ordering a technical service from The Geological Society of Korea · Contents of the geological survey - Confirmation of active fault - Confirmation of a large-scale fracture zone or weak zone - Confirmation of inappropriate items related to the underground water - Confirmation of historical seismicity and instrumental earthquakes data · Synthesized analysis and holding a report meeting · Results of the geological survey - Confirmation of the geological characteristics of the sites and drawing the requirements for the precise geological survey in the future

  12. Site Study Plan for land use, Deaf Smith County site, Texas: Environmental Field Program: Preliminary draft

    International Nuclear Information System (INIS)

    1987-06-01

    The Land Use Site Study Plan describes a field program consisting of characterization of the site; seismic survey rights-of-way and transportation and utility corridors, the vicinity, the region, future land use, and monitoring land-use change. Aerial photography will be used to characterize the site, seismic rows and transportation and utility corridors, and the vicinity. The resulting land-use maps and overlays will then be verified in the field. Interviews with farm managers and local experts will provide additional information. A Geographic Information System (GIS) and satellite imagery will be used to characterize the region, monitor land-use change, and provide information to assist with the future land use study. The site study plan describes the study design and rationale, the filed data collection procedures and equipment, the data analysis methods and application of results, the data management strategy, the schedule of field activities, the personnel requirements and management of the study, and the study's quality assurance program. The directives and requirements that drive these studies are derived from the Salt Repository Project Requirements Document. 51 refs; 6 figs; 3 tabs

  13. Site Study Plan for Aesthetics, Deaf Smith County Site, Texas: Environmental Field Program: Preliminary draft

    International Nuclear Information System (INIS)

    1987-06-01

    The Aesthetic Site Study Plan describes a field program consisting of identification of the visually affected area; determination of scenic quality, visual sensitivity, and visual management classes of the site and vicinity; and analysis of the level of visual contrast that would be created by the project. Field ratings of scenic quality, visual sensitivity, and visual contrast will be supplemented by a public perception survey designed to incorporate the views of the public. This plan describes the need for the study, the study design, data management and use, schedule for proposed activities, and quality assurance program. This study will provide data needed to satisfy requirements contained in, or derived from, SRPO Requirement Document (SRP-RD). 35 refs., 6 figs., 2 tabs

  14. Site Study Plan for salt, Deaf Smith County site, Texas: Environmental Field Program: Preliminary draft

    International Nuclear Information System (INIS)

    1987-06-01

    The Salt Site Study Plan (SSP) describes a program for characterizing the existing salt environment in the site vicinity. A step-by-step approach is described which proceeds from published data and planned theoretical studies, to planned laboratory studies, and finally to planned field studies, to provide the necessary data to meet program requirements contained in the Salt Repository Project - Requirements Document (SRP-RD). The plan also draws on the results of other SSP's for certain data; for example, soil salinity data are to be provided under the Soils SSP. The salt studies consist of evaluation of control and mitigation measures, salt monitoring studies, emission factors development, air models development and validation, and risk assessment. For each study, its design and design rationale; analysis, management, and use of data; schedule of activities; organization of personnel and sample management; and quality assurance requirements are described. 90 refs., 9 figs., 7 tabs

  15. Site Study Plan for Acoustics, Deaf Smith County Site, Texas: Environmental Field Program: Preliminary draft

    International Nuclear Information System (INIS)

    1987-06-01

    The Acoustics site study plan describes a field program which characterizes existing sound levels, determines the area's sound propagation characteristics, and monitors the project-related sound emissions. The plan describes for each study: the need for the study, study design, data management and use, schedule, and quality assurance requirements. These studies will provide data needed to satisfy requirements contained in, or derived from, the Salt Repository Requirements Document. 37 refs., 9 figs., 3 tabs

  16. Preliminary Safety Analysis of the Gorleben Site: Safety Concept and Application to Scenario Development Based on a Site-Specific Features, Events and Processes (FEP) Database - 13304

    Energy Technology Data Exchange (ETDEWEB)

    Moenig, Joerg; Beuth, Thomas; Wolf, Jens [Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) mbH, Theodor-Heuss-Str. 4, D-38122 Braunschweig (Germany); Lommerzheim, Andre [DBE TECHNOLOGY GmbH, Eschenstr. 55, D-31224 Peine (Germany); Mrugalla, Sabine [Federal Institute for Geosciences and Natural Resources (BGR), Stilleweg 2, D-30655 Hannover (Germany)

    2013-07-01

    Based upon the German safety criteria, released in 2010 by the Federal Ministry of the Environment (BMU), a safety concept and a safety assessment concept for the disposal of heat-generating high-level waste have both been developed in the framework of the preliminary safety case for the Gorleben site (Project VSG). The main objective of the disposal is to contain the radioactive waste inside a defined rock zone, which is called containment-providing rock zone. The radionuclides shall remain essentially at the emplacement site, and at the most, a small defined quantity of material shall be able to leave this rock zone. This shall be accomplished by the geological barrier and a technical barrier system, which is required to seal the inevitable penetration of the geological barrier by the construction of the mine. The safe containment has to be demonstrated for probable and less probable evolutions of the site, while evolutions with very low probability (less than 1 % over the demonstration period of 1 million years) need not to be considered. Owing to the uncertainty in predicting the real evolution of the site, plausible scenarios have been derived in a systematic manner. Therefore, a comprehensive site-specific features, events and processes (FEP) data base for the Gorleben site has been developed. The safety concept was directly taken into account, e.g. by identification of FEP with direct influence on the barriers that provide the containment. No effort was spared to identify the interactions of the FEP, their probabilities of occurrence, and their characteristics (values). The information stored in the data base provided the basis for the development of scenarios. The scenario development methodology is based on FEP related to an impairment of the functionality of a subset of barriers, called initial barriers. By taking these FEP into account in their probable characteristics the reference scenario is derived. Thus, the reference scenario describes a

  17. Site 300 hazardous-waste-assessment project. Interim report: December 1981. Preliminary site reconnaissance and project work plan

    International Nuclear Information System (INIS)

    Raber, E.; Helm, D.; Carpenter, D.; Peifer, D.; Sweeney, J.

    1982-01-01

    This document was prepared to outline the scope and objectives of the Hazardous Waste Assessment Project (HWAP) at Site 300. This project was initiated in October, 1981, to investigate the existing solid waste landfills in an effort to satisfy regulatory guidelines and assess the potential for ground-water contamination. This involves a site-specific investigation (utilizing geology, hydrology, geophysics and geochemistry) with the goal of developing an effective ground-water quality monitoring network. Initial site reconnaissance work has begun and we report the results, to date, of our geologic hydrogeologic studies. All known solid waste disposal locations are underlain by rocks of either the Late Miocene Neroly Formation or the Cierbo Formation, both of which are dominantly sandstones interbedded with shale and claystone. The existence of a regional confined (artesian) aquifer, as well as a regional water-table aquifer is postulated for Site 300. Preliminary analysis has led to an understanding of directions and depths of regional ground-water flow

  18. Using a site-specific technical error to establish training responsiveness: a preliminary explorative study.

    Science.gov (United States)

    Weatherwax, Ryan M; Harris, Nigel K; Kilding, Andrew E; Dalleck, Lance C

    2018-01-01

    Even though cardiorespiratory fitness (CRF) training elicits numerous health benefits, not all individuals have positive training responses following a structured CRF intervention. It has been suggested that the technical error (TE), a combination of biological variability and measurement error, should be used to establish specific training responsiveness criteria to gain further insight on the effectiveness of the training program. To date, most training interventions use an absolute change or a TE from previous findings, which do not take into consideration the training site and equipment used to establish training outcomes or the specific cohort being evaluated. The purpose of this investigation was to retrospectively analyze training responsiveness of two CRF training interventions using two common criteria and a site-specific TE. Sixteen men and women completed two maximal graded exercise tests and verification bouts to identify maximal oxygen consumption (VO 2 max) and establish a site-specific TE. The TE was then used to retrospectively analyze training responsiveness in comparison to commonly used criteria: percent change of >0% and >+5.6% in VO 2 max. The TE was found to be 7.7% for relative VO 2 max. χ 2 testing showed significant differences in all training criteria for each intervention and pooled data from both interventions, except between %Δ >0 and %Δ >+7.7% in one of the investigations. Training nonresponsiveness ranged from 11.5% to 34.6%. Findings from the present study support the utility of site-specific TE criterion to quantify training responsiveness. A similar methodology of establishing a site-specific and even cohort specific TE should be considered to establish when true cardiorespiratory training adaptations occur.

  19. Site study plan for ecology, Deaf Smith County Site, Texas: Environmental Field Program: Preliminary Draft

    International Nuclear Information System (INIS)

    1987-06-01

    The Ecology Site Study Plan describes a field program consisting of studies which include surveys for endangered, threatened, and candidate species; vegetation characterization, including mapping and cover typing, plant succession, wetlands description, and preexisting stresses; and wildlife community characterization, including availability and quality of habitats and descriptions of mammal, bird, reptile, amphibian, and invertebrate populations. The plan for each study describes the need for the study, study design, data management and use, schedule and personnel requirements, and quality assurance. These studies will provide data needed to satisfy requirements contained in, or derived from, the Salt Repository Project Requirements Document (SRP-RD). 83 refs., 3 tabs

  20. Preliminary identification of potentially disruptive scenarios at the Greater Confinement Disposal Facility, Area 5 of the Nevada Test Site

    International Nuclear Information System (INIS)

    Guzowski, R.V.; Newman, G.

    1993-12-01

    The Greater Confinement Disposal location is being evaluated to determine whether defense-generated transuranic waste buried at this location complies with the Containment Requirements established by the US Environmental Protection Agency. One step in determining compliance is to identify those combinations of events and processes (scenarios) that define possible future states of the disposal system for which performance assessments must be performed. An established scenario-development procedure was used to identify a comprehensive set of mutually exclusive scenarios. To assure completeness, 761 features, events, processes, and other listings (FEPS) were compiled from 11 references. This number was reduced to 205 primarily through the elimination of duplications. The 205 FEPs were screened based on site-specific, goal-specific, and regulatory criteria. Four events survived screening and were used in preliminary scenario development: (1) exploratory drilling penetrates a GCD borehole, (2) drilling of a withdrawal/injection well penetrates a GCD borehole, (3) subsidence occurs at the RWMS, and (4) irrigation occurs at the RWMS. A logic diagram was used to develop 16 scenarios from the four events. No screening of these scenarios was attempted at this time. Additional screening of the currently retained events and processes will be based on additional data and information from site-characterization activities. When screening of the events and processes is completed, a final set of scenarios will be developed and screened based on consequence and probability of occurrence

  1. Second report: development of site suitability criteria for the high level waste repository for Lawrence Livermore Laboratory

    International Nuclear Information System (INIS)

    1977-11-01

    Results are presented of mining and geotechnical studies provided to the University in support of the development of site suitability criteria. The work involved literature research, further evaluation of geotechnical and mining site suitability factors, further development of specific geotechnical descriptions and coefficients relating to uncertainties, additional documentation of descriptors and coefficients developed for the Cycle II model, and geotechnical and mining guidance to the overall LLL site suitability work. Work results are summarized in sections on general site suitability, geotechnical data base, descriptors and coefficients, uncertainty considerations, natural resources, hydrology, geology, and documentation

  2. Development of site selection criteria for radioactive waste disposal in view of favourable geological settings in Germany

    International Nuclear Information System (INIS)

    Baltes, B.; Brewitz, W.

    2001-01-01

    In Germany it is intended to dispose of all types of radioactive waste in deep geological formations. Since the government has doubts regarding the suitability of the Gorleben site, further sites in different host rock formations have to be investigated. This investigation process has to be carried out with respect to technical suitability and safety as well as to public acceptance. A Committee has been established whose mandate is to develop a comprehensible procedure for the selection of sites for radioactive waste disposal in Germany. The Committee developed an iterative procedure which provides, besides the increase of transparency, the necessary flexibility in dealing with assessment results. The method is governed by geo-scientific and social-scientific criteria that are presented in this paper. 7 steps have been identified in the procedure: 1) exclusion of areas with obviously unfavourable conditions, 2) identification of areas with favourable geological settings, 3) exclusion of areas for socio-scientific reasons, 4) identification of regions with favourable conditions and ranking of regions, 5) identification of sites for further identification, 6) above-ground site investigation and ranking of potentially suitable sites, and 7) identification of sites for suitability investigations. The first 3 steps give the remaining areas that meet the minimum requirements. The criteria of the first 3 steps are: extensive vertical movements, active disturbance zones, seismic activity and volcanic activity, as for the 4 last steps criteria are based on geo- and socio- scientific weighing, voluntariness and regional mediation. (A.C.)

  3. Development of site selection criteria for radioactive waste disposal in view of favourable geological settings in Germany

    Energy Technology Data Exchange (ETDEWEB)

    Baltes, B.; Brewitz, W. [Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) mbH, Cologne (Germany)

    2001-07-01

    In Germany it is intended to dispose of all types of radioactive waste in deep geological formations. Since the government has doubts regarding the suitability of the Gorleben site, further sites in different host rock formations have to be investigated. This investigation process has to be carried out with respect to technical suitability and safety as well as to public acceptance. A Committee has been established whose mandate is to develop a comprehensible procedure for the selection of sites for radioactive waste disposal in Germany. The Committee developed an iterative procedure which provides, besides the increase of transparency, the necessary flexibility in dealing with assessment results. The method is governed by geo-scientific and social-scientific criteria that are presented in this paper. 7 steps have been identified in the procedure: 1) exclusion of areas with obviously unfavourable conditions, 2) identification of areas with favourable geological settings, 3) exclusion of areas for socio-scientific reasons, 4) identification of regions with favourable conditions and ranking of regions, 5) identification of sites for further identification, 6) above-ground site investigation and ranking of potentially suitable sites, and 7) identification of sites for suitability investigations. The first 3 steps give the remaining areas that meet the minimum requirements. The criteria of the first 3 steps are: extensive vertical movements, active disturbance zones, seismic activity and volcanic activity, as for the 4 last steps criteria are based on geo- and socio- scientific weighing, voluntariness and regional mediation. (A.C.)

  4. Site study plan for exploratory shaft monitoring wells, Deaf Smith County Site, Texas: Preliminary Draft

    International Nuclear Information System (INIS)

    1988-01-01

    As part of site characterization studies, two exploratory shafts will be constructed at the Deaf Smith County site, Texas. Twelve wells at five locations have been proposed to monitor potential impacts of shaft construction on water-bearing zones in the Ogallala Formation and the Dockum Group. In addition, tests have been proposed to determine the hydraulic properties of the water-bearing zones for use in design and construction of the shafts. Samples of the Blackwater Draw Formation, Ogallala Formation, and Dockum Group will be obtained during construction of these wells. Visual indentification, laboratory testing, and in situ testing will yield data necessary for Exploratory Shaft Facility design and construction. This activity provides the earliest data on the Blackwater Drew Formation, Ogallala Formation, and Dockum Group near the exploratory shaft locations. Drilling and hydrologic testing are scheduled prior to other subsurface activity at the Exploratory Shaft Facility to establish ground-water baseline conditions. The Technical Field Services Contractor is responsible for conducting the field program of drilling and testing. Samples and data will be handled and reported in accordance with established Salt Repository Project procedures. A quality assurance program will be utilized to assure that activities affecting quality are performed correctly and that the appropriate documentation is maintained. 45 refs., 11 figs., 4 tabs

  5. Alternative risk-based criteria for transportation of radioactive materials on the United States Department of Energy Hanford Site

    International Nuclear Information System (INIS)

    Mercado, J.E.; Field, J.G.; Smith, R.J.; Wang, O.S.

    1993-01-01

    This paper presents the development of an alternative method to evaluate packaging safety for radioactive material transported solely within the boundaries of a restricted site; the method uses risk-based criteria to assess and document packaging safety. These criteria offer a standard against which the results of a risk assessment are compared to evaluate the safety of a transportation operation. Numerous payloads are transported entirely within the U.S. Department of Energy's Hanford Site boundaries. The U.S. Department of Energy requires that the safety of onsite transportation be equivalent to the safety provided for transporting radioactive materials in commerce as regulated by the U.S. Department of Transportation and the U.S. Nuclear Regulatory Commission. Some onsite packaging configurations do not meet the performance criteria that form the basis of these regulations, necessitating the establishment of alternative criteria to evaluate safety. Quantitatively defined criteria have been derived from the U.S. Department of Transportation limits for package radiation levels, curie content, activity release, and external contamination levels. Recommendations of the International Committee on Radiation Protection may further restrict the criteria. The proposed method documents packaging safety in a transportation risk assessment. The assessment estimates accident frequencies, conservatively evaluates the dose consequences of these accidents, and compares the results to the established risk acceptance criteria. Specific Hanford Site onsite packaging and transportation issues illustrate the alternative method. The paper compares the solutions resulting from the application of risk-based criteria to those resulting from strict compliance with commercial transportation regulations. (author)

  6. CATE 2016 Indonesia: normalized radial graded filtering, site-to-site image registration, and preliminary results

    Science.gov (United States)

    Jensen, L.; Kovac, S. A.; Hare, H. S.; Mitchell, A. M.; McKay, M. A.; Bosh, R.; Watson, Z.; Penn, M.

    2016-12-01

    An area of the solar corona from 1 out to approximately 2.5 solar radii is currently poorly sampled in astronomy. This is largely due to difficulties inherent in observing the sun from space and from the ground. Specifically focusing on ground based observations, the main problem is scattered light in the Earth's atmosphere and in the telescopes themselves. A total solar eclipse solves this problem by blocking the light from the photosphere of the sun before it enters the atmosphere, reducing the scattered light in the atmosphere by a factor of 10,000. However, using a total solar eclipse introduces another challenge due to the small window of time it provides. At any given location in 2017, the totality will last for only about 2.5 minutes and such a small data set limits the studies that can be done on the inner corona. The Citizen Continental-America Telescopic Eclipse Experiment plans to overcome this issue by taking advantage of America's infrastructure and using 60 identical telescopes to collect continuous data of the solar eclipse as the shadow travels from Oregon to South Carolina. By splicing these data together 90 minutes of one-of-a-kind data can be collected, revealing the dynamics of the inner corona as never seen before. For the 2016 Indonesian total solar eclipse the CATE project collected data using 5 sites along the eclipse path. These data were then used to develop processing programs to use on future data. These processes included site-to-site image registration as well as normalized radial graded filtering of the images. Programs were also developed to begin performing studies on the data including overlapping CATE and LASCO space telescope data for a total coronal image as well as thread tracing routines to quantify direction in the coronal filaments. This work was made possible through the National Solar Observatory Research Experiences for Undergraduates (REU) Program, which is funded by the National Science Foundation (NSF). The NSO

  7. Site Study Plan for soils, Deaf Smith County site, Texas: Environmental Field Program: Preliminary draft

    International Nuclear Information System (INIS)

    1987-06-01

    The Soils Site Study Plan describes a field program consisting of a soil characterization survey, impact monitoring of soils, predisturbance soil salinity survey, and a reclamation suitability study. This information will be used to plan for soil stripping, stockpiling, and replacement; reclamation of soils; determining predisturbance chemical and physical characteristics of the soils; including salinity levels; and monitoring for changes in chemical and physical characteristics of the soil. The SSP describes for each study the need for the study, the study design, data management and use, schedule of proposed activities, and the quality assurance program. These studies will provide data needed to satisfy requirements contained in, or derived from, the Salt Repository Project Requirements Document. 75 refs., 10 figs., 5 tabs

  8. A new type of headache, headache associated with airplane travel: preliminary diagnostic criteria and possible mechanisms of aetiopathogenesis.

    Science.gov (United States)

    Berilgen, M Said; Müngen, Bulent

    2011-09-01

    In recent years, there has been an increase in the reports indicating a form of headache that occurs during commercial aircraft travel. This headache, called airplane headache by some authors, is believed to be a new type of headache. The headache has very specific characteristics and all of the cases exhibited very stereotypical symptoms. The headache starts suddenly during the ascent and/or descent of the commercial aircraft. It has a mean duration of 20 minutes, which is usually unilateral and commonly localized to periorbital region. The headache is described to be severe, and has a stabbing or jabbing nature, and generally subsides in a short time. In some cases, an organic cause can be identified whereas in others no organic pathology could be found. We described the clinical features of 22 cases who suffered from a headache that occurred during airplane travel. We examined other cases with similar features reported in the literature and proposed preliminary diagnostic criteria for this new form of headache. We also discussed the possible patholophysiological mechanisms that may cause this headache.

  9. Preliminary geologic site selection factors for the National Waste Terminal Storage Program

    International Nuclear Information System (INIS)

    1977-06-01

    The geologic considerations and the associated factors that have to be addressed in the selection of repository sites in deep geologic formations are listed and described. In addition a description is given of the information necessary to assess the geologic factors. The methods of obtaining this information are described. An illustration is given of a general approach of how the geologic factors could be applied and integrated to assess the acceptability of candidate sites. No consideration is given to a detailed description of the application of integration of the geologic factors. The criteria associated with each factor that will be used are not defined

  10. Preliminary site characterization radiological monitoring plan for the Nevada Nuclear Waste Storage Investigations Project, Yucca Mountain Site

    International Nuclear Information System (INIS)

    1987-03-01

    The activities described in this plan occur in the early phases of site characterization. This document presents the Preliminary Site Characterization Radiological Monitoring Plan (PSCRMP) for collecting and evaluating data in support of the NNWSI Project. The PSCRMP defines and identifies control procedures for the monitoring activities. The PSCRMP activity will utilize integrating radon monitoring devices, a continuous radon monitor, and a particulate air sampler. These instruments will be used to establish the baseline radioactivity and/or radioactivity released due to early site characterization activities. The sections that follow provide a general project description, the specifics of the monitoring program, and the practices that will be employed to ensure the validity of the collected data by integrating quality assurance into all activities. Section 2 of this document describes the regulatory base of this document. Section 3 describes the site characterization activities which may lead to release of radioactivity. Section 4 provides a description of the potential sources of radioactivity that site characterization could generate. Section 5 summarizes the sampling and monitoring methodology, which will be used to monitor the potential sources of radioactivity. The network of sampling and monitoring equipment is described in Section 6, and Section 7 summarizes the systems operation activities. The data reporting activities are described in Section 8. Finally, a description of the Quality Assurance (QA) and Quality Control (QC) activities is provided in Section 9. Appendix A contains a summary of the procedures to be used in this program, and Appendix B contains technical specification on equipment and services. 20 refs., 11 figs., 2 tabs

  11. Preliminary risk assessment of Power Plant Plomin site contaminated by radioactive slag and ash

    International Nuclear Information System (INIS)

    Skanata, D.; Sinka, D.; Lokner, V.; Schaller, A.

    1996-01-01

    There is a certain number of radioactively contaminated sites in the Republic of Croatia, one of them being known as Power Plant Plomin site, which contains radioactive slag and ash. Due to a relatively high quantity of the deposited material, as well as relatively high population density of the neighbouring area, it is very important to assess the impact of the site on human health and environment. Using RESRAD computer code and PATHRAE method a preliminary assessment of doses and radiation risks for the workers who spend most of their working day at the pile has been performed. PATHRAE method has also been used for the assessment of radiation risks for the neighbouring population. The assessment is preliminary in its character due to the lack of input data. On the basis of assessment results, recommendations are being given comprising measurements to be taken with a view to coming up with the final risk assessment, as well as protective measures which should be undertaken in the meantime. (author)

  12. Demands and criteria for the site selection from the view of the power plant owners

    International Nuclear Information System (INIS)

    Staebler, K.; Beising, R.

    1975-01-01

    Function of electricity supply utilities from the point of view of choice of site; energy business background; references to the mode of procedure in site selection; pragmatic principle of site choice. (HP) [de

  13. Regulatory principles, criteria and guidelines for site selection, design, construction and operation of uranium tailings retention systems

    International Nuclear Information System (INIS)

    Coady, J.R.; Henry, L.C.

    1978-01-01

    Principles, criteria and guidelines developed by the Atomic Energy Control Board for the management of uranium mill tailings are discussed. The application of these concepts is considered in relation to site selection, design and construction, operation and decommissioning of tailings retention facilities

  14. American National Standard: criteria and guidelines for assessing capability for surface faulting at nuclear power plant sites

    International Nuclear Information System (INIS)

    Anon.

    1982-01-01

    This standard provides applicants and consultants with criteria and guidelines for investigations directed toward the assessment of the capability for surface faulting at nuclear power plant sites. Assessment of vibratory ground motion resulting from faulting is not treated in these guidelines

  15. A new spatial multi-criteria decision support tool for site selection for implementation of managed aquifer recharge.

    Science.gov (United States)

    Rahman, M Azizur; Rusteberg, Bernd; Gogu, R C; Lobo Ferreira, J P; Sauter, Martin

    2012-05-30

    This study reports the development of a new spatial multi-criteria decision analysis (SMCDA) software tool for selecting suitable sites for Managed Aquifer Recharge (MAR) systems. The new SMCDA software tool functions based on the combination of existing multi-criteria evaluation methods with modern decision analysis techniques. More specifically, non-compensatory screening, criteria standardization and weighting, and Analytical Hierarchy Process (AHP) have been combined with Weighted Linear Combination (WLC) and Ordered Weighted Averaging (OWA). This SMCDA tool may be implemented with a wide range of decision maker's preferences. The tool's user-friendly interface helps guide the decision maker through the sequential steps for site selection, those steps namely being constraint mapping, criteria hierarchy, criteria standardization and weighting, and criteria overlay. The tool offers some predetermined default criteria and standard methods to increase the trade-off between ease-of-use and efficiency. Integrated into ArcGIS, the tool has the advantage of using GIS tools for spatial analysis, and herein data may be processed and displayed. The tool is non-site specific, adaptive, and comprehensive, and may be applied to any type of site-selection problem. For demonstrating the robustness of the new tool, a case study was planned and executed at Algarve Region, Portugal. The efficiency of the SMCDA tool in the decision making process for selecting suitable sites for MAR was also demonstrated. Specific aspects of the tool such as built-in default criteria, explicit decision steps, and flexibility in choosing different options were key features, which benefited the study. The new SMCDA tool can be augmented by groundwater flow and transport modeling so as to achieve a more comprehensive approach to the selection process for the best locations of the MAR infiltration basins, as well as the locations of recovery wells and areas of groundwater protection. The new spatial

  16. Description of surface systems. Preliminary site description. Forsmark area Version 1.2

    Energy Technology Data Exchange (ETDEWEB)

    Lindborg, Tobias [ed.

    2005-06-01

    Swedish Nuclear Fuel and Waste Management Co (SKB) started site investigations for a deep repository for spent nuclear fuel in 2002 at two different sites in Sweden, Forsmark and Oskarshamn. The investigations should provide necessary information for a license application aimed at starting underground exploration. For this reason, ecosystem data need to be interpreted and assessed into site descriptive models, which in turn are used for safety assessment studies and for environmental impact assessment. Descriptions of the surface system are also needed for further planning of the site investigations. This report describes the surface ecosystems of the Forsmark site (e.g. hydrology, Quaternary deposits, chemistry, vegetation, animals and the human land use). The ecosystem description is an integration of the site and its regional setting, covering the current state of the biosphere as well as the ongoing natural processes affecting the longterm development. Improving the descriptions is important during both the initial and the complete site investigation phase. Before starting of the initial phase in Forsmark, version 0 of the site descriptive model was developed. The results of the initial site investigation phase is compiled into a preliminary site description of Forsmark (version 1.2) in June 2005. This report provides the major input and background to the biosphere description, in the 1.2 version of the Forsmark site description. The basis for this interim version is quality-assured field data from the Forsmark sub area and regional area, available in the SKB SICADA, and GIS data bases as of July 31th 2004 as well as version 1.1 of the Site Descriptive Model. To achieve an ecosystem site description there is a need to develop discipline-specific models by interpreting and analysing primary data. The different discipline-specific models are then integrated into a system describing interactions and flows and stocks of matter between and within functional units in

  17. Description of surface systems. Preliminary site description. Forsmark area Version 1.2

    International Nuclear Information System (INIS)

    Lindborg, Tobias

    2005-06-01

    Swedish Nuclear Fuel and Waste Management Co (SKB) started site investigations for a deep repository for spent nuclear fuel in 2002 at two different sites in Sweden, Forsmark and Oskarshamn. The investigations should provide necessary information for a license application aimed at starting underground exploration. For this reason, ecosystem data need to be interpreted and assessed into site descriptive models, which in turn are used for safety assessment studies and for environmental impact assessment. Descriptions of the surface system are also needed for further planning of the site investigations. This report describes the surface ecosystems of the Forsmark site (e.g. hydrology, Quaternary deposits, chemistry, vegetation, animals and the human land use). The ecosystem description is an integration of the site and its regional setting, covering the current state of the biosphere as well as the ongoing natural processes affecting the longterm development. Improving the descriptions is important during both the initial and the complete site investigation phase. Before starting of the initial phase in Forsmark, version 0 of the site descriptive model was developed. The results of the initial site investigation phase is compiled into a preliminary site description of Forsmark (version 1.2) in June 2005. This report provides the major input and background to the biosphere description, in the 1.2 version of the Forsmark site description. The basis for this interim version is quality-assured field data from the Forsmark sub area and regional area, available in the SKB SICADA, and GIS data bases as of July 31th 2004 as well as version 1.1 of the Site Descriptive Model. To achieve an ecosystem site description there is a need to develop discipline-specific models by interpreting and analysing primary data. The different discipline-specific models are then integrated into a system describing interactions and flows and stocks of matter between and within functional units in

  18. A Preliminary Assessment of Daily Weather Conditions in Nuclear Site for Development of Effective Emergency Plan

    International Nuclear Information System (INIS)

    Han, Seok Jung; Ahn, Kwang Il

    2012-01-01

    A radiological emergency preparedness for nuclear sites is recognized as an important measure against anticipated severe accidents with environmental releases of radioactive materials. While there are many individual means in the emergency preparedness for nuclear accidents, one of most important means is to make a decision of evacuation or shelter of the public residents with the emergency plan zone (EPZ) of a nuclear site. In order to prepare an effective strategy for the evacuation as a basis of the emergency preparedness, it may need the understanding of atmospheric dispersion characteristics of radiation releases to the environment, mainly depending upon the weather conditions of a radiation releases location, i.e., a nuclear site. As a preliminary study for the development of an effective emergency plan, the basic features of the weather conditions of a specific site were investigated. A main interest of this study is to identify whether or not the site weather conditions have specific features helpful for a decision making of evacuation of the public residents

  19. The accumulation of a platelet protein, thrombospondin, at the site of arterial thrombus formation: Preliminary report

    International Nuclear Information System (INIS)

    Perlman, S.B.; Hammes, R.J.; Besozzi, M.C.; Folts, J.D.; Mosher, D.F.

    1987-01-01

    There are many methods available for the detection of thrombosis, none of which are noninvasive, rapid and accurate. Thrombosponding is a platelet protein that is present in the developing thrombus and may be an effective substance to use for imaging thrombosis. Vascular stenosis and thrombosis were produced in coronary, carotid and femoral arteries in eleven adult mongrel dogs. 131 I labeled thrombosponding was administered to each animal to determine whether the radiotracer accumulated at the site of thrombus formation. The radioactivity per gram of vessels with thrombi was significantly different from the control vessels or whole blood (p=0.0037 and p=0.015, respectively, paired t-test). This preliminary work suggests that iodinated thrombosponding accumulates at the site of thrombus formation. Labeled thrombosponding may be a rapid, safe and accurate method of detecting arterial thrombosis. (orig.)

  20. 76 FR 82201 - General Site Suitability Criteria for Nuclear Power Stations

    Science.gov (United States)

    2011-12-30

    ... guidelines in identifying suitable candidate sites for nuclear power stations. The decision that a station... combination and a cost-benefit analysis comparing it with alternative site-plant combinations, as discussed in...

  1. Radiological criteria for the remediation of sites for spent fuel and radioactive waste storage in the Russian Northwest.

    Science.gov (United States)

    Shandala, N K; Sneve, M K; Titov, A V; Smith, G M; Novikova, N Ya; Romanov, V V; Seregin, V A

    2008-12-01

    In the 1960s, two technical bases of the Northern Fleet were created in Northwest Russia, at Andreeva Bay in the Kola Peninsula and Gremikha village on the coast of the Barents Sea. They maintained nuclear submarines, performing receipt and storage of radioactive waste and spent nuclear fuel, and are now designated sites of temporary storage (STSs). An analysis of the radiation situation at these sites demonstrates that substantial long-term remediation work will be required after the removal of the waste and spent nuclear fuel. Regulatory guidance is under development to support this work. Having in mind modern approaches to guaranteeing radiation safety, the primary regulatory focus is on a justification of dose constraints for determining acceptable residual contamination which might lead to exposure to workers and the public. For these sites, four principal options for remediation have been considered-renovation, conversion, conservation and liquidation. This paper describes a system of recommended dose constraints and derived control levels formulated for each option. The unconditional guarantee of long-term radioecological protection provides the basis for criteria development. Non-exceedance of these dose constraints and control levels implies compliance with radiological protection objectives related to the residual contamination. Dose reduction below proposed dose constraint values must also be carried out according to the optimisation principle. The developed criteria relate to the condition of the facilities and the STS areas after the termination of remediation activities. The proposed criteria for renovation, conversion, conservation and liquidation are entirely within the dose limits adopted in Russia for the management of man-made radiation sources, and are consistent with ICRP recommendations and national practice in other countries. The proposed criteria for STS remediation and new industrial (non-radiation-hazardous) facilities and buildings on

  2. Use of toxicity assessment to develop site specific remediation criteria for oil and gas facilities : guidance manual

    International Nuclear Information System (INIS)

    1996-01-01

    The results of a two year study into the evaluation of toxicity-based methods to develop site-specific, risk-based cleanup objectives for the decommissioning of oil and gas facilities were compiled into a manual of guidance. The two basic approaches used in determining remediation criteria for contaminated sites are: (1) comparison of the concentrations of chemicals found on-site with broad regional or national soil and water quality objectives developed for the chemicals involved, and (2) site-specific risk assessment. Toxicity tests are used to test organisms such as earthworms, lettuce seeds, or larval fish directly in the soil, water or sediment suspected of being contaminated. The effects of any contamination on the survival, growth, reproduction, and behaviour of the test organisms are then evaluated. The manual provides guidance in: (1) using toxicity assessments within the regulatory framework of site decommissioning, (2) performing a toxicity assessment, and (3) developing site-specific criteria for a risk assessment. 18 refs., 3 tabs., 5 figs

  3. Recommended new criteria for the selection of nuclear waste repository sites in Columbia River basalt and US Gulf Coast domed salt

    International Nuclear Information System (INIS)

    Steinborn, T.L.; Wagoner, J.L.; Qualheim, B.; Fitts, C.R.; Stetkar, R.E.; Turnbull, R.W.

    1980-01-01

    Screening criteria and specifications are recommended to aid in the evaluation of sites proposed for nuclear waste disposal in basalt and domed salt. The recommended new criteria proposed in this report are intended to supplement existing repository-related criteria for nuclear waste disposal. The existing criteria are contained in 10 CFR 60 sections which define siting criteria of the Nuclear Regulatory Commission (NRC), and ONWI 33(2) which defines siting criteria of the Office of Nuclear Waste Isolation (ONWI) for the Department of Energy. The specifications are conditions or parameter values that the authors recommend be applied in site acceptance evaluations. The siting concerns covered in this report include repository depth, host rock extent, seismic setting, structural and tectonic conditions, groundwater and rock geochemistry, volcanism, surface and subsurface hydrology, and socioeconomic issues, such as natural resources, land use, and population distribution

  4. Clinical relevance of surgical site infection as defined by the criteria of the Centers for Disease Control and Prevention

    DEFF Research Database (Denmark)

    Henriksen, N A; Meyhoff, C S; Wetterslev, J

    2010-01-01

    Surgical site infection (SSI) is a common complication after abdominal surgery and the Centers for Disease Control and Prevention (CDC) criteria are commonly used for diagnosis and surveillance. The aim of this study was to evaluate whether SSI diagnosed according to CDC is clinically relevant...... diagnosed with SSI and a matched control group (N=46) without SSI according to the CDC criteria after laparotomy. Two blinded experienced surgeons evaluated the hospital records and determined whether patients had CRSSI, based on the following criteria: antibiotic treatment, surgical intervention, prolonged...... hospital stay or referral to an intensive care unit for SSI. The rate of CRSSI was 38 of 54 (70%) in patients with CDC-diagnosed SSI and none in patients without a CDC-diagnosed SSI. Sixty-one percent of the CDC-diagnosed SSIs were superficial, of which 48% were considered clinically relevant...

  5. A preliminary guidebook for identifying stratigraphic contacts at the Nevada Test Site

    International Nuclear Information System (INIS)

    Pawloski, G.A.; McKague, H.L.; Wagoner, J.L.; McKinnis, W.B.

    1992-01-01

    Lithologic variation, regional depositional trends, and the lack of written guidelines have resulted in inconsistencies in the recognition of stratigraphic contacts in drill holes at the Nevada Test Site (NTS). Stratigraphic identification, based on mineralogy of discrete samples, can be augmented by geophysical logs and downhole movies to more accurately and consistently locate contacts between units. Criteria are established for locating the base of the Pahute Mesa ash-flow tuff, the top of the Ammonia Tanks ash-flow tuff, the top of the Ammonia Tanks bedded tuff, and the top and the base of the Rainier Mesa Tuff

  6. Can multi-criteria analysis models support the site selection for a repository for heat-generating waste?

    International Nuclear Information System (INIS)

    Gutberlet, Daniela

    2015-01-01

    The decision for or against a potential site for a nuclear waste repository is highly complex and requires decision-makers to consider multiple assessment criteria. The complexity of each site and its characteristics, and the differing opinions among members of the public and advocacy groups mean t hat conflicts of interest are likely to arise. In this paper, the author suggests that multi-criteria analysis models could be used to provide methodological support during the selection process. The models can map these types of decision situations and suggest coherent solutions with relatively little formal effort. They allow users to compare different opt ions simultaneously and ensure that t heir decision-making Is conscious rather than arbitrary.

  7. Geochemical site-selection criteria for HLW repositories in Europe and North America

    International Nuclear Information System (INIS)

    Savage, David; Arthur, Randolph C.; Sasamoto, Hiroshi; Shibata, Masahiro; Yui, Mikazu

    2000-01-01

    Geochemical as well as socio-economic issues associated with the selection of potential sites to host a high-level nuclear waste repository have received considerable attention in repository programs in Europe (Belgium, Finland, France, Germany, Spain, Sweden, Switzerland and the U.K.) and North America (Canada and the United States). The objective of the present study is to summarize this international experience with particular emphasis on geochemical properties that factor into the adopted site-selection strategies. Results indicate that the geochemical properties of a site play a subordinate role, at best, to other geotechnical properties in the international site-selection approaches. In countries where geochemical properties are acknowledged in the site-selection approach, requirements are stated qualitatively and tend to focus on associated impacts on the stability of the engineered barrier system and on radionuclide transport. Site geochemical properties that are likely to control the long-term stability of geochemical conditions and radionuclide migration behavior are unspecified, however. This non-prescriptive approach may be reasonable for purposes of screening among potential sites, but a better understanding of site properties that are most important in controlling the long-term geochemical evolution of the site over a range of possible scenarios would enable the potential sites to be ranked in terms of their suitability to host a repository. (author)

  8. Development of Site-Specific Water Quality Criteria for the Arpa Harbor Wastewater Treatment Plant in Tipalao Bay, Guam

    Science.gov (United States)

    2016-07-01

    flats, estuaries, and coastal creeks. It is usually found within tidally influenced waters , but it may enter freshwater, ascending about 10...based on a dissolved metal concentration endpoint in the receiving body of water . In other words , the translator supports estimations of the fraction of...TECHNICAL REPORT 2068 July 2016 Development of Site-Specific Water Quality Criteria for the Arpa Harbor Wastewater Treatment Plant

  9. Final disposal of radioactive wastes. Site selection criteria. Technical and economical factors

    International Nuclear Information System (INIS)

    Granero, J.J.

    1984-01-01

    General considerations, geological and socioeconomical criteria for final disposal of radioactive wastes in geological formations are treated. More attention is given to the final disposal of high level radioactive wastes and different solutions searched abroad which seems of interest for Spain. (author)

  10. Preliminary results from comparisons of redundant tiltmeters at three sites in central california

    Science.gov (United States)

    Mortensen, C.E.; Johnston, M.J.S.

    1979-01-01

    The U.S. Geological Survey has been operating a network of shallow-borehole tiltmeters in central California since June 1973. At six sites redundant instruments have been installed as a check on data coherency. These include the Sage Ranch, Tres Pinos, New Idria, Aromas, Bear Valley and San Juan Bautista tiltmeter sites. Preliminary results from the comparison of redundant data from the Aromas, Bear Valley and San Juan Bautista sites for periods of eight, three and seven months respectively, suggest that short period tilt signals in the range 5 min < T < 3-5 h and ranging in amplitude from 5 ?? 10-8 to 10-6 rad, but not including step offsets, show excellent agreement on closely spaced instruments. Agreement is not as good in this period range for instruments at San Juan Bautista with a separation of 200 m. Signals of interest observed in this period range include coseismic tilts, teleseisms and tilts associated with creep events. Tilt signals in the period range 3-5 h < T < 2- 5 weeks are not always coherent at all three of the redundant tilt sites studied. Tilt signals in this period range have amplitudes up to 5 ?? 10-6 rad and wavelengths down to at least the instrument separation at the closely spaced sites (~several meters). Regarding longerterm coherency, the instruments at San Juan Bautista with 200-m spacing, agree within 0.5 ??rad for the N-S component and 0.7 jurad for the E-W component for a period of two months. The closely spaced redundant instruments at Aromas agree within 2 ??rad for the N-S component and 1 ??rad for the E-W component for the eight-month period of operation. Data from the three sites have been checked for effects of temperature, atmospheric pressure and rainfall. The latter appears to be critically site dependent. The worst case tilts for 1 inch of rainfall can be more than 1 jurad with a duration of a few days to a week. Typical rain-induced tilts are less than 0.3 ??rad for 1 inch of rain. The two instruments at the Sage Ranch

  11. Preliminary constitutive properties for salt and nonsalt rocks from four potential repository sites

    International Nuclear Information System (INIS)

    Pfeifle, T.W.; Mellegard, K.D.; Senseny, P.E.

    1983-07-01

    Results are presented from laboratory strength and creep tests performed on salt and nonsalt specimens from the Richton Dome in Mississippi, the Vacherie Dome in Louisiana, the Permian Basin in Texas, and the Paradox Basin in Utah. The constititive properties obtained for salt are the elastic moduli and the failure envelope at 24 0 C and parameter values for the exponential-time creep law. Some additional data are presented to indicate how the elastic moduli and strength change with temperature. The nonsalt constitutive properties reported are the elastic moduli, the unconfined compressive strength and the tensile strength at 24 0 C. The properties given in this report will be used in subsequent numerical simulations that will provide information to assist in the screening and selection of site locations for a nuclear waste repository and to assist in the repository design at the selected site. The matrix of tests performed is the minimum effort required to obtain these constitutive properties. The preliminary values obtained will be supplemented by additional testing for sites that are selected for further investigation

  12. Preliminary report on the utilization of the Fermilab site for a future accelerator

    International Nuclear Information System (INIS)

    1996-10-01

    This report is a preliminary assessment of the utility of the Fermilab site for future accelerator projects. It responds to a request from the Director to evaluate how the Fermilab site and infrastructure may be relevant to future accelerator projects in the U.S. The SSC experience suggests that any major new project will have to be based on the existing infrastructure at one of the National Laboratories. This work presents only the technical issues and the benefits of the Fermilab site and infrastructure. The projects treated are: (1) A really large hadron collider based on the ''Pipetron'' vision of low-field (2 Tesla) magnets in a small diameter tunnel. Another option, not treated in detail, is a hadron collider using high field magnets. (2) Muon Colliders with 250 GeV and 2 TeV per beam. (3) A linear electron collider with 250 to 500 GeV per beam. The infrastructure of the state of Illinois - geology, hydrology, power and surface water- seems remarkably well suited to any of these projects. The geology of most of Illinois, including Fermilab, contains a dolomite layer that: has low seismic activity, is at an appropriate depth to provide radiation protection, is essentially impervious to water movement and thus satisfies hydrology requirements. There is adequate electrical power - both locally and statewide. We first give brief overviews of the Fermilab and Illinois infrastructure - geology, hydrology, power, and water - and then a summary of each project. On the basis of what we have learned, we feel that Fermilab must be considered seriously as a site for any of these projects. Beyond this point, however site-specific plans will need to be developed for each of the projects

  13. Design principle of TVO's final repository and preliminary adaptation to site specific conditions

    International Nuclear Information System (INIS)

    Salo, J-P.; Reikkola, R.

    1995-01-01

    Teollisuuden Voima Oy (TVO) is responsible for the management of spent fuel produced by the Olkiluoto power plant. TVO's current programme of spent fuel management is based on the guidelines and time schedule set by the Finnish Government. TVO has studied a final disposal concept in which the spent fuel bundles are encapsulated in copper canisters and emplaced in Finnish bedrock. According to the plan the final repository for spent fuel will be in operation by 2020. TVO's updated technical plans for the disposal of spent fuel together with a performance analysis (TVO-92) were submitted to the authorities in 1992. The paper describes the design principle of TVO's final repository and preliminary adaptation of the repository to site specific conditions. (author). 10 refs., 5 figs

  14. Regional hydrogeological simulations using CONECTFLOW. Preliminary site description. Laxemar sub area - version 1.2

    Energy Technology Data Exchange (ETDEWEB)

    Hartley, Lee; Hunter, Fiona; Jackson, Peter; McCarthy, Rachel [Serco Assurance, Risley (United Kingdom); Gylling, Bjoern; Marsic, Niko [Kemakta Konsult AB, Stockholm (Sweden)

    2006-04-15

    The main objective of this study is to support the development of a preliminary Site Description of the Laxemar subarea on a regional-scale based on the available data of November 2004 (Data Freeze L1.2). A more specific objective of this study is to assess the role of both known and less quantified hydrogeological conditions in determining the present-day distribution of saline groundwater in the Laxemar subarea on a regional-scale. An improved understanding of the palaeo-hydrogeology is necessary in order to gain credibility for the Site Description in general and the hydrogeological description in particular. This is to serve as a basis for describing the present hydrogeological conditions on a local-scale, as well as predictions of future hydrogeological conditions. Another objective is to assess the flow-paths from the local-scale model domain, based on the present-day flow conditions, to assess the distribution of discharge and recharge areas connected to the flow at the approximate repository depth to inform the Preliminary Safety Evaluation. Significant new features incorporated in the modelling include: a depth variation in hydraulic properties within the deformation zones; a dependence on rock domain and depth in the rock mass properties in regional-scale models; a more detailed model of the overburden in terms of a layered system of spatially variable thickness made up of several different types of Quaternary deposits has been implemented; and several variants on the position of the watertable have been tried. The motivation for introducing a dependence on rock domain was guided by the hydrogeological interpretation with the aim of honouring the observed differences in hydraulic properties measured at the boreholes.

  15. Regional hydrogeological simulations using CONECTFLOW. Preliminary site description. Laxemar sub area - version 1.2

    International Nuclear Information System (INIS)

    Hartley, Lee; Hunter, Fiona; Jackson, Peter; McCarthy, Rachel; Gylling, Bjoern; Marsic, Niko

    2006-04-01

    The main objective of this study is to support the development of a preliminary Site Description of the Laxemar subarea on a regional-scale based on the available data of November 2004 (Data Freeze L1.2). A more specific objective of this study is to assess the role of both known and less quantified hydrogeological conditions in determining the present-day distribution of saline groundwater in the Laxemar subarea on a regional-scale. An improved understanding of the palaeo-hydrogeology is necessary in order to gain credibility for the Site Description in general and the hydrogeological description in particular. This is to serve as a basis for describing the present hydrogeological conditions on a local-scale, as well as predictions of future hydrogeological conditions. Another objective is to assess the flow-paths from the local-scale model domain, based on the present-day flow conditions, to assess the distribution of discharge and recharge areas connected to the flow at the approximate repository depth to inform the Preliminary Safety Evaluation. Significant new features incorporated in the modelling include: a depth variation in hydraulic properties within the deformation zones; a dependence on rock domain and depth in the rock mass properties in regional-scale models; a more detailed model of the overburden in terms of a layered system of spatially variable thickness made up of several different types of Quaternary deposits has been implemented; and several variants on the position of the watertable have been tried. The motivation for introducing a dependence on rock domain was guided by the hydrogeological interpretation with the aim of honouring the observed differences in hydraulic properties measured at the boreholes

  16. Preliminary assessment of potential underground stability (wedge and spalling) at Forsmark, Simpevarp and Laxemar sites

    Energy Technology Data Exchange (ETDEWEB)

    Martin, Derek [Univ. of Alberta, Edmonton (Canada). Geotechnical Engineering

    2005-12-15

    In SKB's Underground Design Premises the objective in the early design phase is to estimate if there is sufficient space for the repository at a site. One of the conditions that could limit the space available is stability of the underground openings, i.e., deposition tunnels and deposition boreholes. The purpose of this report is to provide a preliminary assessment of the potential for wedge instability and spalling that may be encountered at the Forsmark, Simpevarp and Laxemar sites based on information from the site investigations program up to July 30, 2004. The rock mass spalling strength was defined using the in-situ results from SKB's Aespoe Pillar Stability Experiment and AECL's Mine-by Experiment. These experiments suggest that the rock mass spalling strength for crystalline rocks can be estimated as 0.57 of the mean laboratory uniaxial compressive strength. A probability-based methodology utilizing this in-situ rock mass spalling strength has been developed for assessing the risk for spalling in a repository at the Forsmark, Simpevarp and Laxemar sites. The in-situ stresses and the uniaxial compressive strength data from these sites were used as the bases for the analyses. Preliminary findings from all sites suggest that, generally, the risk for spalling increases as the depth of the repository increases, simply because the stress magnitudes increase with depth. The depth at which the risk for spalling is significant, depends on the individual sites which are discussed below. The greatest uncertainty in the spalling analyses for Forsmark is related to the uncertainty in the horizontal stress magnitudes and associated stress gradients with depth. The confidence in these analyses can only be increased by increasing the confidence in the stress and geology model for the site. From the analyses completed it appears that spalling in the deposition tunnels can be controlled by orienting the tunnels approximately parallel to the maximum horizontal

  17. Demands and criteria for the site selection from the view of the power plant owners

    International Nuclear Information System (INIS)

    Beising, R.; Staebler, K.

    1976-01-01

    The methods as shown by the concrete example of the site provision plan for Baden-Wuerttemberg have proved extremely useful. The pragmatic method of site selection which ensures as little clash of interests as possible between the power plant and other preservation interests such as e.g. environment preservation, recreation areas, development axes, water economics is the only possible method for the densely populated areas of the Federal Republic. The numerous physical constraints in our Land only allow an optimisation of site search within the limited possibilities. (HP) [de

  18. Using a risk assessment protocol to develop soil cleanup criteria for petroleum contaminated sites

    International Nuclear Information System (INIS)

    Asante-Duah, D.K.

    1991-01-01

    Petroleum contaminated site may prose significant risks to the public because of potential health and environmental effects, and to Potentially Responsible Parties (PRPs) because of financial liabilities that could result from such effects. The effective management of petroleum contaminated sites has therefore become an important environmental priority and will be a growing challenge for years to come. It has also become evident that the proper management of such sites poses great challenges. Risk assessment seems to be one of the fastest evolving tools for developing appropriate management decisions, including those relating to the levels of cleanup warranty under specific scenarios. This paper reports that the U.S. Environmental Protection Agency (U.S. EPA) recognizes the use of risk assessment to facilitate decisions on whether or not remedial actions are needed to abate site-related risks, and also in the enforcement of regulatory standards. Risk assessment techniques have been used in various regulatory programs employed by federal, state, and local agencies

  19. Optimal site selection for sitting a solar park using multi-criteria decision analysis and geographical information systems

    Science.gov (United States)

    Georgiou, Andreas; Skarlatos, Dimitrios

    2016-07-01

    Among the renewable power sources, solar power is rapidly becoming popular because it is inexhaustible, clean, and dependable. It has also become more efficient since the power conversion efficiency of photovoltaic solar cells has increased. Following these trends, solar power will become more affordable in years to come and considerable investments are to be expected. Despite the size of solar plants, the sitting procedure is a crucial factor for their efficiency and financial viability. Many aspects influence such a decision: legal, environmental, technical, and financial to name a few. This paper describes a general integrated framework to evaluate land suitability for the optimal placement of photovoltaic solar power plants, which is based on a combination of a geographic information system (GIS), remote sensing techniques, and multi-criteria decision-making methods. An application of the proposed framework for the Limassol district in Cyprus is further illustrated. The combination of a GIS and multi-criteria methods produces an excellent analysis tool that creates an extensive database of spatial and non-spatial data, which will be used to simplify problems as well as solve and promote the use of multiple criteria. A set of environmental, economic, social, and technical constrains, based on recent Cypriot legislation, European's Union policies, and expert advice, identifies the potential sites for solar park installation. The pairwise comparison method in the context of the analytic hierarchy process (AHP) is applied to estimate the criteria weights in order to establish their relative importance in site evaluation. In addition, four different methods to combine information layers and check their sensitivity were used. The first considered all the criteria as being equally important and assigned them equal weight, whereas the others grouped the criteria and graded them according to their objective perceived importance. The overall suitability of the study

  20. Documentation of Hanford Site independent review of the Hanford Waste Vitrification Plant Preliminary Safety Analysis Report

    International Nuclear Information System (INIS)

    Herborn, D.I.

    1993-11-01

    Westinghouse Hanford Company (WHC) is the Integrating Contractor for the Hanford Waste Vitrification Plant (HWVP) Project, and as such is responsible for preparation of the HWVP Preliminary Safety Analysis Report (PSAR). The HWVP PSAR was prepared pursuant to the requirements for safety analyses contained in US Department of Energy (DOE) Orders 4700.1, Project Management System (DOE 1987); 5480.5, Safety of Nuclear Facilities (DOE 1986a); 5481.lB, Safety Analysis and Review System (DOE 1986b) which was superseded by DOE order 5480-23, Nuclear Safety Analysis Reports, for nuclear facilities effective April 30, 1992 (DOE 1992); and 6430.lA, General Design Criteria (DOE 1989). The WHC procedures that, in large part, implement these DOE requirements are contained in WHC-CM-4-46, Nonreactor Facility Safety Analysis Manual. This manual describes the overall WHC safety analysis process in terms of requirements for safety analyses, responsibilities of the various contributing organizations, and required reviews and approvals

  1. Geological criteria for site selection of an LILW radioactive waste repository in the Philippines

    International Nuclear Information System (INIS)

    Aurelio, Mario; Taguibao, Kristine Joy; Vargas, Edmundo; Palattao, Maria Visitacion; Reyes, Rolando; Nohay, Carl; Singayan, Alfonso

    2013-01-01

    In the selection of sites for disposal facilities involving low- and intermediate-level radioactive waste (LILW), International Atomic Energy Agency (IAEA) recommendations require that 'the region in which the site is located shall be such that significant tectonic and surface processes are not expected to occur with an intensity that would compromise the required isolation capability of the repository'. Evaluating the appropriateness of a site therefore requires a deep understanding of the geological and tectonic setting of the area. The Philippines sits in a tectonically active region frequented by earthquakes and volcanic activity. Its highly variable morphology coupled with its location along the typhoon corridor in the west Pacific region subjects the country to surface processes often manifested in the form of landslides. The Philippine LILW near surface repository project site is located on the north eastern sector of the Island of Luzon in northern Philippines. This island is surrounded by active subduction trenches; to the east by the East Luzon Trough and to the west by the Manila Trench. The island is also traversed by several branches of the Philippine Fault System. The Philippine LILW repository project is located more than 100 km away from any of these major active fault systems. In the near field, the project site is located less than 10 km from a minor fault (Dummon River Fault) and more than 40 km away from a volcanic edifice (Mt. Caguas). This paper presents an analysis of the potential hazards that these active tectonic features may pose to the project site. The assessment of such geologic hazards is imperative in the characterization of the site and a crucial input in the design and safety assessment of the repository. (authors)

  2. Geological criteria for site selection of an LILW radioactive waste repository in the Philippines

    Energy Technology Data Exchange (ETDEWEB)

    Aurelio, Mario; Taguibao, Kristine Joy [National Institute of Geological Sciences, University of the Philippines, Quezon City (Philippines); Vargas, Edmundo; Palattao, Maria Visitacion; Reyes, Rolando; Nohay, Carl; Singayan, Alfonso [Philippine Nuclear Research Institute, Department of Science and Technology, Quezon City (Philippines)

    2013-07-01

    In the selection of sites for disposal facilities involving low- and intermediate-level radioactive waste (LILW), International Atomic Energy Agency (IAEA) recommendations require that 'the region in which the site is located shall be such that significant tectonic and surface processes are not expected to occur with an intensity that would compromise the required isolation capability of the repository'. Evaluating the appropriateness of a site therefore requires a deep understanding of the geological and tectonic setting of the area. The Philippines sits in a tectonically active region frequented by earthquakes and volcanic activity. Its highly variable morphology coupled with its location along the typhoon corridor in the west Pacific region subjects the country to surface processes often manifested in the form of landslides. The Philippine LILW near surface repository project site is located on the north eastern sector of the Island of Luzon in northern Philippines. This island is surrounded by active subduction trenches; to the east by the East Luzon Trough and to the west by the Manila Trench. The island is also traversed by several branches of the Philippine Fault System. The Philippine LILW repository project is located more than 100 km away from any of these major active fault systems. In the near field, the project site is located less than 10 km from a minor fault (Dummon River Fault) and more than 40 km away from a volcanic edifice (Mt. Caguas). This paper presents an analysis of the potential hazards that these active tectonic features may pose to the project site. The assessment of such geologic hazards is imperative in the characterization of the site and a crucial input in the design and safety assessment of the repository. (authors)

  3. Rock mechanics site descriptive model-theoretical approach. Preliminary site description Forsmark area - version 1.2

    Energy Technology Data Exchange (ETDEWEB)

    Fredriksson, Anders; Olofsson, Isabelle [Golder Associates AB, Uppsala (Sweden)

    2005-12-15

    The present report summarises the theoretical approach to estimate the mechanical properties of the rock mass in relation to the Preliminary Site Descriptive Modelling, version 1.2 Forsmark. The theoretical approach is based on a discrete fracture network (DFN) description of the fracture system in the rock mass and on the results of mechanical testing of intact rock and on rock fractures. To estimate the mechanical properties of the rock mass a load test on a rock block with fractures is simulated with the numerical code 3DEC. The location and size of the fractures are given by DFN-realisations. The rock block was loaded in plain strain condition. From the calculated relationship between stresses and deformations the mechanical properties of the rock mass were determined. The influence of the geometrical properties of the fracture system on the mechanical properties of the rock mass was analysed by loading 20 blocks based on different DFN-realisations. The material properties of the intact rock and the fractures were kept constant. The properties are set equal to the mean value of each measured material property. The influence of the variation of the properties of the intact rock and variation of the mechanical properties of the fractures are estimated by analysing numerical load tests on one specific block (one DFN-realisation) with combinations of properties for intact rock and fractures. Each parameter varies from its lowest values to its highest values while the rest of the parameters are held constant, equal to the mean value. The resulting distribution was expressed as a variation around the value determined with mean values on all parameters. To estimate the resulting distribution of the mechanical properties of the rock mass a Monte-Carlo simulation was performed by generating values from the two distributions independent of each other. The two values were added and the statistical properties of the resulting distribution were determined.

  4. Rock mechanics site descriptive model-theoretical approach. Preliminary site description Forsmark area - version 1.2

    International Nuclear Information System (INIS)

    Fredriksson, Anders; Olofsson, Isabelle

    2005-12-01

    The present report summarises the theoretical approach to estimate the mechanical properties of the rock mass in relation to the Preliminary Site Descriptive Modelling, version 1.2 Forsmark. The theoretical approach is based on a discrete fracture network (DFN) description of the fracture system in the rock mass and on the results of mechanical testing of intact rock and on rock fractures. To estimate the mechanical properties of the rock mass a load test on a rock block with fractures is simulated with the numerical code 3DEC. The location and size of the fractures are given by DFN-realisations. The rock block was loaded in plain strain condition. From the calculated relationship between stresses and deformations the mechanical properties of the rock mass were determined. The influence of the geometrical properties of the fracture system on the mechanical properties of the rock mass was analysed by loading 20 blocks based on different DFN-realisations. The material properties of the intact rock and the fractures were kept constant. The properties are set equal to the mean value of each measured material property. The influence of the variation of the properties of the intact rock and variation of the mechanical properties of the fractures are estimated by analysing numerical load tests on one specific block (one DFN-realisation) with combinations of properties for intact rock and fractures. Each parameter varies from its lowest values to its highest values while the rest of the parameters are held constant, equal to the mean value. The resulting distribution was expressed as a variation around the value determined with mean values on all parameters. To estimate the resulting distribution of the mechanical properties of the rock mass a Monte-Carlo simulation was performed by generating values from the two distributions independent of each other. The two values were added and the statistical properties of the resulting distribution were determined

  5. Preliminary Correlation Map of Geomorphic Surfaces in North-Central Frenchman Flat, Nevada Test Site

    International Nuclear Information System (INIS)

    Bechtel Nevada

    2005-01-01

    This correlation map (scale = 1:12,000) presents the results of a mapping initiative that was part of the comprehensive site characterization required to operate the Area 5 Radioactive Waste Management Site, a low-level radioactive waste disposal facility located in northern Frenchman Flat at the Nevada Test Site. Eight primary map units are recognized for Quaternary surfaces: remnants of six alluvial fan or terrace surfaces, one unit that includes colluvial aprons associated with hill slopes, and one unit for anthropogenically disturbed surfaces. This surficial geology map provides fundamental data on natural processes for reconstruction of the Quaternary history of northern Frenchman Flat, which in turn will aid in the understanding of the natural processes that act to develop the landscape, and the time-frames involved in landscape development. The mapping was conducted using color and color-infrared aerial photographs and field verification of map unit composition and boundaries. Criteria for defining the map unit composition of geomorphic surface units are based on relative geomorphic position, landform morphology, and degree of preservation of surface morphology. The bedrock units identified on this map were derived from previous published mapping efforts and are included for completeness

  6. The main demands and criteria for building site choice for radioactive waste repositories

    International Nuclear Information System (INIS)

    Angelova, R.; Sandul, G.A.; Sen'ko, T.Ya.

    2002-01-01

    There are considered the main demands of building site choice for RAW repositories. At this the accent is placed on geological repositories (underground repositories of geological type) and near surface repositories assigned to disposal of low- and intermediate-level short- and mediate-lived radionuclides. These demands are conditionally separated into two blocks: account of social development of the adjoining territories; account of natural factors characterizing building site. Further there are discussed the questions of anthropogenous influence on a safety functioning of RAW repositories and of urgency of stable development of the adjoining territories. In context of the Ukrainian and other states nuclear laws there is also considered the lawful aspect defining the building site choice for RAW repositories

  7. Multi criteria analysis in environmental management: Selecting the best stormwater erosion and sediment control measure in Malaysian construction sites

    Energy Technology Data Exchange (ETDEWEB)

    Al-Hadu, Ibrahiem Abdul Razak; Sidek, Lariyah Mohd; Desa, Mohamed Nor Mohamed [Civil Engineering, Universiti Tenga Nasional, Kajang, Selangor (Malaysia); Basri, Noor Ezlin Ahmad [Civil and Structural Engineering, Universiti Kebangsaan Malyasia, Bangi, Selangor (Malaysia)

    2011-07-01

    Malaysia located in a tropical region which is interested with a heavy rainfall through the whole seasons of the year. Construction stages usually associated with soil disturbing due to land clearing and grading activities, this combined with the tropical climate in Malaysia, will generate an enormous amount of soil to be eroded and then deposited in the adjacent water bodies. There are many kinds of mitigation measures used so as to reduce the impact of erosion and sedimentation that are generated due to the stormwater in construction sites. This paper presents the application of Multi Criteria Analysis (MCA) tool in choosing the best stormwater control measure by depending on specified criteria and criterion weight. The results obtained from the application of MCA in stormwater pollution control have many benefits to the contractors, consultants and decision makers by making them able to select the best control measure for every stage of construction.

  8. Site selection process for radioactive waste repository (radioactive facility) in Cuba as a fundamental safety criteria

    International Nuclear Information System (INIS)

    Vital, Jose Luis Peralta; Castillo, Reinaldo Gil; Chales Suarez, Gustavo; Rodriguez Reyes, Aymee

    1999-01-01

    The paper show the process of search carried out for the selection of the safest site in the National territory, in order to sitting the Facility (Repository) that will disposal the low and intermediate level radioactive wastes, as well as the possible Storage Facility for nuclear spent Fuel (radioactive wastes of high activity). We summarize the obtained Methodology and the Criterions of exclusion adopted for the development of the Process of site selection, as well as the current condition of the researches that will permit the obtaining of the nominative objectives. (author)

  9. Criteria for compilation of a site-specific thermodynamic database for geochemical speciation calculations

    International Nuclear Information System (INIS)

    Chandratillake, M.; Trivedi, D.P.; Randall, M.G.; Humphreys, P.N.

    1998-01-01

    A methodology has been developed to establish a site-specific database appropriate to geochemical modelling the critical components and the wide range of near field conditions expected in the low level radioactive waste disposal site at Drigg in the UK. Several databases available in the public domain have been compared to select a foundation database. The foundation database was 'trimmed-down' and then customised to suit Drigg applications. The species dominant at Drigg have been identified and the thermodynamic constants of these species have been critically evaluated. The evaluated database has been validated for quality by comparing speciation calculations with plutonium and uranium experimental solubility results. (orig.)

  10. PROBLEMS OF APPLYING FIXED FORMULAE TO SAFETY CRITERIA AND SITE SELECTION

    Energy Technology Data Exchange (ETDEWEB)

    Davis, W. K.

    1963-10-15

    The problem of developing a formula or calculation procedure for that could more-or-less automatically indicate whether or not a nuclear plant would be considered safe at a particular location is discussed. The difficulties and impossibilities of any sach formula for making decisions on siting and safety involving large amounts of money and public safety are considered. (P.C.H.)

  11. Restoration principles and criteria: superfund program policy for cleanup at radiation contaminated sites

    International Nuclear Information System (INIS)

    Walker, Stuart

    2006-01-01

    The Environmental Protection Agency (EPA) Office of Superfund Remediation and Technology Innovation (OSRTI) is responsible 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 Superfund, including how radiation is addressed by the Superfund program. 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 a consistent manner as with chemical contamination, except to account for the technical differences between radionuclides and chemicals. This consistency is important since at every radioactively contaminated site being addressed under Superfund's primary program for long-term cleanup, the National Priorities List (NPL), chemical contamination is also present. (author)

  12. Selection criteria for a radioactive waste disposal site in the Republic of South Africa

    International Nuclear Information System (INIS)

    Toens, P.D.; Hambleton-Jones, B.B.

    1986-01-01

    A program commenced in 1978 to select a suitable site for the disposal of nuclear waste in South Africa. This entailed the examination of a variety of socio-economic and earthscience related parameters over large parts of South Africa. The site selection program, for which the Geology Department of the Atomic Energy Corporation of South Africa Ltd (AEC) (previously the Nuclear Development Corporation (NUCOR)) accepted responsibility, commenced with an initial screening phase and led to the identification of potentially suitable areas by mid 1980. A site suitability phase involving regional, and subsequently detailed socio-economic, geological, geohydrological and geophysical studies in the areas identified by the screening phase was completed in December 1982. As a result of very positive indications that the district of Namaqualand was the most suitable candidate area it was possible, after further detailed investigations, to identify and purchase a site judged to be suitable for the disposal of low- and intermediate-level waste by February 1983. The area acquired measures some 10 000ha in extent and is situated 100km southeast of Springbok in the northwestern Cape and 600km north of the Koeberg nuclear power station near Cape Town

  13. 10 CFR Appendix A to Part 100 - Seismic and Geologic Siting Criteria for Nuclear Power Plants

    Science.gov (United States)

    2010-01-01

    ... materials has occurred parallel to the fracture plane. It is distinct from other types of ground disruptions... history; (2) Identification and evaluation of tectonic structures underlying the site and the region... in order to permit appropriate consideration of the geologic history of such faults in establishing...

  14. Risk of surgical site infection in paediatric herniotomies without any prophylactic antibiotics: A preliminary experience

    Directory of Open Access Journals (Sweden)

    Dhananjay Vaze

    2014-01-01

    Full Text Available Background: Different studies underline the use of pre-operative antibiotic prophylaxis in clean surgeries like herniotomy and inguinal orchiopexy. But, the meta-analyses do not recommend nor discard the use of prophylactic pre-operative antibiotics. The scarcity of controlled clinical trials in paediatric population further vitiates the matter. This study assessed the difference in the rate of early post-operative wound infection cases in children who received single dose of pre-operative antibiotics and children who did not receive antibiotics after inguinal herniotomy and orchiopexy. Materials and Methods: This randomised prospective study was conducted in Paediatric Surgery department of PGIMER Chandigarh. Out of 251 patients, 112 patients were randomised to the case group and 139 were ascribed to the control group. The patients in control group were given a standard regimen of single dose of intravenous antibiotic at the time of induction followed by 3-4 days of oral antibiotic. Case group patients underwent the surgical procedure in similar manner with no antibiotic either at the time of induction or post-operatively. Results: The incidence of surgical site infection in case group was 3.73 % and that in control group was 2.22%. The observed difference in the incidence of surgical site infection was statistically insignificant (P value = 0.7027. The overall infection rate in case and control group was 2.89%. Conclusions: Our preliminary experience suggests that there is no statistically significant difference in the proportion of early post-operative wound infection between the patients who received single dose of pre-operative antibiotics and the patients who received no antibiotics after inguinal herniotomy and orchiopexy. The risk of surgical site infection in paediatric heriotomies does not increase even if the child′s weight is less than his/her expected weight for age.

  15. Development of a design basis tornado and structural design criteria for the Nevada Test Site, Nevada. Final report

    International Nuclear Information System (INIS)

    McDonald, J.R.; Minor, J.E.; Mehta, K.C.

    1975-06-01

    In order to evaluate the ability of critical facilities at the Nevada Test Site to withstand the possible damaging effects of extreme winds and tornadoes, parameters for the effects of tornadoes and extreme winds and structural design criteria for the design and evaluation of structures were developed. The meteorological investigations conducted are summarized, and techniques used for developing the combined tornado and extreme wind risk model are discussed. The guidelines for structural design include methods for calculating pressure distributions on walls and roofs of structures and methods for accommodating impact loads from wind-driven missiles. Calculations for determining the design loads for an example structure are included

  16. Integrating knowledge-based multi-criteria evaluation techniques with GIS for landfill site selection: A case study using AHP

    Directory of Open Access Journals (Sweden)

    Fagbohun B.J.

    2016-09-01

    Full Text Available A major challenge in most growing urban areas of developing countries, without a pre-existing land use plan is the sustainable and efficient management of solid wastes. Siting a landfill is a complicated task because of several environmental regulations. This challenge gives birth to the need to develop efficient strategies for the selection of proper waste disposal sites in accordance with all existing environmental regulations. This paper presents a knowledge-based multi-criteria decision analysis using GIS for the selection of suitable landfill site in Ado-Ekiti, Nigeria. In order to identify suitable sites for landfill, seven factors - land use/cover, geology, river, soil, slope, lineament and roads - were taken into consideration. Each factor was classified and ranked based on prior knowledge about the area and existing guidelines. Weights for each factor were determined through pair-wise comparison using Saaty’s 9 point scale and AHP. The integration of factors according to their weights using weighted index overlay analysis revealed that 39.23 km2 within the area was suitable to site a landfill. The resulting suitable area was classified as high suitability covering 6.47 km2 (16.49%, moderate suitability 25.48 km2 (64.95% and low suitability 7.28 km2 (18.56% based on their overall weights.

  17. Documentation information for peer group review report site suitability criteria study

    International Nuclear Information System (INIS)

    1977-10-01

    This report presents documentation of the geotechnical input data provided by Golder Associates, Inc. (GAI) for the Cycle II repository model analysis. Information relating to the proposed uncertainty analysis and several appropriate comments pertinent to the overall site suitability study are also included. GAI was responsible for developing descriptors and coefficients for the TASC model hydrologic analog; permeability and porosity values for the geologic formations (excepting salt); occurrence and properties of the bore hole seals, backfill, and mine fracture zones; and properties of fracture zones associated with faults. All data are presented with a preferred value and maximum credible range. These values relate to a generic repository in a sedimentary basin and not a specific site. 13 figures, 6 tables

  18. Design criteria for a worldwide directory of radioactively contaminated sites (DRCS)

    International Nuclear Information System (INIS)

    2001-11-01

    The publication attempts to fulfil two main objectives: (a) to describe the activities and underlying considerations and concepts for the development by the IAEA of a worldwide Directory of Radioactively Contaminated Sites; (b) to give some recommendations for the development of such directories at the Member States level. In addition to a discussion of the conceptual considerations on the design of an IAEA-level directory, the results of previous efforts on data collation are presented. The DRCS also intends to collate technical information on remedial actions taken or proposed, thus giving examples for consultation in similar cases. Hence, the information available in such a Directory is intended to provide decision makers with a useful reference frame for their own actions. In this the IAEA attempts to assume the role of a clearing-house of information pertinent to characterization of radioactively contaminated sites and their remediation and restoration

  19. Design criteria for a worldwide directory of radioactively contaminated sites (DRCS)

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-11-01

    The publication attempts to fulfil two main objectives: (a) to describe the activities and underlying considerations and concepts for the development by the IAEA of a worldwide Directory of Radioactively Contaminated Sites; (b) to give some recommendations for the development of such directories at the Member States level. In addition to a discussion of the conceptual considerations on the design of an IAEA-level directory, the results of previous efforts on data collation are presented. The DRCS also intends to collate technical information on remedial actions taken or proposed, thus giving examples for consultation in similar cases. Hence, the information available in such a Directory is intended to provide decision makers with a useful reference frame for their own actions. In this the IAEA attempts to assume the role of a clearing-house of information pertinent to characterization of radioactively contaminated sites and their remediation and restoration.

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

    International Nuclear Information System (INIS)

    Shapiro, M.

    2000-01-01

    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)

  1. OPTIMAL ALLOCATION OF LANDFILL DISPOSAL SITE: A FUZZY MULTI-CRITERIA APPROACH

    Directory of Open Access Journals (Sweden)

    Ajit P. Singh, A. K. Vidyarthi

    2008-01-01

    Full Text Available The arbitrary disposal through land-fill sites and also the unscientific management of solid wastes generated by domestic, commercial and industrial activities leading to serious problems of health, sanitation and environmental degradation in India demand an immediate proper solid waste disposal planning otherwise it may cause a serious problem, especially in small and medium-sized cities/towns if proper steps are not initiated now. The present paper aims to develop decision support systems to allocate the best landfill disposal site among the given alternative sites for Vidya Vihar, Pilani, Rajasthan, India. The technique is applied to determine the overall strategy for planning of solid waste disposal and management, while taking into account its environmental impact, as well as economical, technical and sustainable development issues. The model effectively reflects dynamic, interactive, and uncertain characteristics of the solid waste management system and provides decision-makers with a decision tool to make a better decision while choosing a municipal solid waste management strategy.

  2. Criteria for siting of nuclear power plants with regard for radiation hazards

    International Nuclear Information System (INIS)

    Shevts, I; Kunz, Eh.

    1976-01-01

    Reviewed are different approaches to a problem of the nuclear power plant construction expediency from the point of view of earlier and remote consequencies of ionizing radiation in the case of accident releases of radioactive products. The method of a risk and benefit comparison is considered the most expedient approach to decide on the nuclear power plant construction as well as to minimize the accident risk. As at present the probabilities of different accident types are not known or there are only approximate estimates, it is necessary to choose a modified approach, but so that it approximates to the main approach, recommended by ICRP. It is assumed, that the requirements can be met by the following design criteria: Limitation of maximum risk separate persons most subjected to irradiation hazard; introduction of dose limits which is not to be exceeded even in the case of maximum permissible desighned accident (MPDA); application of principle of minimizing the accident risk when estimating the engineering protective buildings at least from the point of view of MPDA or those accident types, which probabilities can be estimated; application of a tentative limit of a collective dose in such a way not to exceed the cumulative collective population dose by a collective dose due to MPDA, under normal operation during all the nuclear power plant operating period [ru

  3. Radiological criteria and methods for remediation of contaminated former mining sites

    International Nuclear Information System (INIS)

    Biesold, H.; Thielen, H.; Weiss, D.

    2001-01-01

    Mining and ore processing have a long history in the New States of Germany, Saxony, Thuringia and Saxony-Anhalt. The ores were often mineralized with uranium and therefore the residues are a radiological hazard to man and environment. Immediately after World War II the Soviet Union started to develop its nuclear capability by mining uranium ores in the occupied zone of East Germany. At the beginning the exploitation was concentrated on former underground mines of silver and other non ferrous ores. Afterwards, new uranium deposits were explored in Saxony and eastern Thuringia. Numerous waste rock piles and tailings ponds of considerable size resulted from these mining activities. Uranium production reached some 220,000 t between 1946 and 1990. After the reunification in 1990, production was finished for economic and other reasons. The German Federal Government was faced with one of the largest ecological, social and economic challenges. In this report an overview is given on kind and amount of the mining residues, the radiation protection criteria, models and data bases used for risk assessment and dose calculation are explained and remediation methods are described. (authors)

  4. Radiological criteria and methods for remediation of contaminated former mining sites

    Energy Technology Data Exchange (ETDEWEB)

    Biesold, H.; Thielen, H. [Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) mbH, Cologne (Germany); Weiss, D. [Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) mbH, Berlin (Germany)

    2001-07-01

    Mining and ore processing have a long history in the New States of Germany, Saxony, Thuringia and Saxony-Anhalt. The ores were often mineralized with uranium and therefore the residues are a radiological hazard to man and environment. Immediately after World War II the Soviet Union started to develop its nuclear capability by mining uranium ores in the occupied zone of East Germany. At the beginning the exploitation was concentrated on former underground mines of silver and other non ferrous ores. Afterwards, new uranium deposits were explored in Saxony and eastern Thuringia. Numerous waste rock piles and tailings ponds of considerable size resulted from these mining activities. Uranium production reached some 220,000 t between 1946 and 1990. After the reunification in 1990, production was finished for economic and other reasons. The German Federal Government was faced with one of the largest ecological, social and economic challenges. In this report an overview is given on kind and amount of the mining residues, the radiation protection criteria, models and data bases used for risk assessment and dose calculation are explained and remediation methods are described. (authors)

  5. Selection of adequate site location during early stages of construction project management: A multi-criteria decision analysis approach

    Science.gov (United States)

    Marović, Ivan; Hanak, Tomaš

    2017-10-01

    In the management of construction projects special attention should be given to the planning as the most important phase of decision-making process. Quality decision-making based on adequate and comprehensive collaboration of all involved stakeholders is crucial in project’s early stages. Fundamental reasons for existence of this problem arise from: specific conditions of construction industry (final products are inseparable from the location i.e. location has a strong influence of building design and its structural characteristics as well as technology which will be used during construction), investors’ desires and attitudes, and influence of socioeconomic and environment aspects. Considering all mentioned reasons one can conclude that selection of adequate construction site location for future investment is complex, low structured and multi-criteria problem. To take into account all the dimensions, the proposed model for selection of adequate site location is devised. The model is based on AHP (for designing the decision-making hierarchy) and PROMETHEE (for pairwise comparison of investment locations) methods. As a result of mixing basis feature of both methods, operational synergies can be achieved in multi-criteria decision analysis. Such gives the decision-maker a sense of assurance, knowing that if the procedure proposed by the presented model has been followed, it will lead to a rational decision, carefully and systematically thought out.

  6. Clinical relevance of surgical site infection as defined by the criteria of the Centers for Disease Control and Prevention

    DEFF Research Database (Denmark)

    Henriksen, N A; Meyhoff, C S; Wetterslev, J

    2010-01-01

    Surgical site infection (SSI) is a common complication after abdominal surgery and the Centers for Disease Control and Prevention (CDC) criteria are commonly used for diagnosis and surveillance. The aim of this study was to evaluate whether SSI diagnosed according to CDC is clinically relevant (C...... a suitable standard definition for monitoring and identifying SSI, even if some cases of less clinically significant superficial SSI are included.......Surgical site infection (SSI) is a common complication after abdominal surgery and the Centers for Disease Control and Prevention (CDC) criteria are commonly used for diagnosis and surveillance. The aim of this study was to evaluate whether SSI diagnosed according to CDC is clinically relevant...... hospital stay or referral to an intensive care unit for SSI. The rate of CRSSI was 38 of 54 (70%) in patients with CDC-diagnosed SSI and none in patients without a CDC-diagnosed SSI. Sixty-one percent of the CDC-diagnosed SSIs were superficial, of which 48% were considered clinically relevant...

  7. Drift design methodology and preliminary application for the Yucca Mountain Site Characterization Project

    International Nuclear Information System (INIS)

    Hardy, M.P.; Bauer, S.J.

    1991-12-01

    Excavation stability in an underground nuclear waste repository is required during construction, emplacement, retrieval (if required), and closure phases to ensure worker health and safety, and to prevent development of potential pathways for radionuclide migration in the post-closure period. Stable excavations are developed by appropriate excavation procedures, design of the room shape, design and installation of rock support reinforcement systems, and implementation of appropriate monitoring and maintenance programs. In addition to the loads imposed by the in situ stress field, the repository drifts will be impacted by thermal loads developed after waste emplacement and, periodically, by seismic loads from naturally occurring earthquakes and underground nuclear events. A priori evaluation of stability is required for design of the ground support system, to confirm that the thermal loads are reasonable, and to support the license application process. In this report, a design methodology for assessing drift stability is presented. This is based on site conditions, together with empirical and analytical methods. Analytical numerical methods are emphasized at this time because empirical data are unavailable for excavations in welded tuff either at elevated temperatures or under seismic loads. The analytical methodology incorporates analysis of rock masses that are systematically jointed, randomly jointed, and sparsely jointed. In situ thermal and seismic loads are considered. Methods of evaluating the analytical results and estimating ground support requirements for all the full range of expected ground conditions are outlines. The results of a preliminary application of the methodology using the limited available data are presented. 26 figs., 55 tabs

  8. Water-quality monitoring at the Hoe Creek test site: review and preliminary conclusions

    Energy Technology Data Exchange (ETDEWEB)

    Wang, F T; Mead, S W; Stuermer, D H

    1982-05-20

    It has been shown that underground coal gasification (UCG) may introduce a broad range of residual gasification products into the groundwater of a coal aquifer. Sorption of many contaminants by the coal itself is an important factor in restricting the migration of these contaminants in the ground water. However, field studies, conducted at Lawrence Livermore National Laboratory's Hoe Creek site, have shown that sorption of organic compounds by coal is not as effective as expected, perhaps because the coal surface area is limited. Furthermore, if severe roof collapse has taken place during gasification, non-coal aquifers located above the gasified coal seam may be interconnected with the coal aquifer, and contaminants may enter these non-coal aquifers, in which sorption is even less effective. The Hoe Creek II and III experiments have provided opportunities to study the contamination of a sand aquifer located above a gasified coal seam in a hydrological recharge area. Preliminary results indicate that the water in the overlying sand aquifer is much less contaminated with organic compounds than the water in the gasified coal aquifer. In conducting these field investigations, valuable lessons ere learned concerning groundwater monitoring. A suggested monitoring strategy is discussed.

  9. Dry-run of site investigation planning using the manual for preliminary investigation in Japan

    International Nuclear Information System (INIS)

    Akamura, Shigeki; Miwa, Tadashi; Tanaka, Tatsuya; Shiratsuchi, Hiroshi; Horio, Atsushi

    2011-01-01

    A stepwise site selection process has been adopted for geological disposal of HLW in Japan. Literature surveys, followed by preliminary investigations (PI) and, finally, detailed investigations in underground facilities will be carried out in the successive selection stages. In the PI stage, surface-based investigations such as borehole surveys and geophysical prospecting will be implemented. In order to conduct the PI appropriately and efficiently within a restricted timeframe and budget, planning and management of PI are very important. NUMO therefore compiled existing knowledge and experience in the planning and managing of investigations in the form of manuals to be used to improve and maintain internal expertise. The first editions of the two manuals were prepared on the basis of experience overseas, and then they were revised by taking technological environment, laws and regulation in Japan into consideration. This paper introduces the procedure of PI planning using manual as well as the results of the dry-run, with the Yokosuka area as a hypothetical PI area, where the monstraction study is under way. Based on the dry-run, applicability of the manual is checked and, at the same time, further revisions are made to improve the content. (author)

  10. Effect of corrosive marine atmosphere on construction materials in Tanzania: Exposure sites and preliminary results

    International Nuclear Information System (INIS)

    Mmari, A.G.; Uiso, C.B.S.; Makundi, I.N.; Potgieter-Vermaak, S.S.; Potgieter, J.H.; Van Grieken, R.

    2007-01-01

    Air pollution studies in Africa are limited and the influence of ambient air quality on buildings and constructions have not been investigated in the larger part of Sub-Saharan Africa. The increasing burden of emission from industry, traffic and coal power plants on ambient air pollution in Sub-Saharan Africa necessitated reviewing previous and current studies. In South Africa a 20-year exposure program, focusing on the effect of ambient exposure on various metals and alloys, showed that the amount of rainfall, relative humidity, atmospheric pollution, wind speed, solar radiation and structural design are some of the factors controlling atmospheric corrosion. Tanzania, being among the Sub-Saharan African countries and partly bordered by Indian ocean, the main source of marine atmosphere, experiences corrosive degradation on metal roofing and cementitious materials. This paper describes the exposure site set-up and will report on some preliminary results of air quality and its relation with the meteorological conditions, as well as surface changes observed, for the year one of exposure. These will thereafter be compared to the completed European and Asian studies, as reported by CLRTAP and RAPIDC respectively. (author)

  11. Developing a strategy and closure criteria for radioactive and mixed waste sites in the ORNL remedial action program: Regulatory interface

    International Nuclear Information System (INIS)

    Trabalka, J.R.

    1987-09-01

    Some options for stabilization and treatment of contaminated sites can theoretically provide a once-and-for-all solution (e.g., removal or destruction of contaminants). Most realizable options, however, leave contaminants in place (in situ), potentially isolated by physical or chemical, but more typically, by hydrologic measures. As a result of the dynamic nature of the interactions between contaminants, remedial measures, and the environment, in situ stablization measures are likely to have limited life spans, and maintenance and monitoring of performance become an essential part of the scheme. The length of formal institutional control over the site and related questions about future uses of the land and waters are of paramount importance. Unique features of the ORNL site and environs appear to be key ingredients in achieving the very long term institutional control necessary for successful financing and implementation of in situ stabilization. Some formal regulatory interface is necessary to ensure that regulatory limitations and new guidance which can affect planning and implementation of the ORNL Remedial Action Program are communicated to ORNL staff and potential technical and financial limitations which can affect schedules or alternatives for achievement of long-term site stabilization and the capability to meet environmental regulations are provided to regulatory bodies as early as possible. Such an interface should allow decisions on closure criteria to be based primarily on technical merit and protection of human health and the environment. A plan for interfacing with federal and state regulatory authorities is described. 93 refs., 1 fig., 4 tabs

  12. Soil criteria to protect terrestrial wildlife and open-range livestock from metal toxicity at mining sites.

    Science.gov (United States)

    Ford, Karl L; Beyer, W Nelson

    2014-03-01

    Thousands of hard rock mines exist in the western USA and in other parts of the world as a result of historic and current gold, silver, lead, and mercury mining. Many of these sites in the USA are on public lands. Typical mine waste associated with these sites are tailings and waste rock dumps that may be used by wildlife and open-range livestock. This report provides wildlife screening criteria levels for metals in soil and mine waste to evaluate risk and to determine the need for site-specific risk assessment, remediation, or a change in management practices. The screening levels are calculated from toxicity reference values based on maximum tolerable levels of metals in feed, on soil and plant ingestion rates, and on soil to plant uptake factors for a variety of receptors. The metals chosen for this report are common toxic metals found at mining sites: arsenic, cadmium, copper, lead, mercury, and zinc. The resulting soil screening values are well above those developed by the US Environmental Protection Agency. The difference in values was mainly a result of using toxicity reference values that were more specific to the receptors addressed rather than the most sensitive receptor.

  13. Site Specific Metal Criteria Developed Using Kentucky Division of Water Procedures

    International Nuclear Information System (INIS)

    Kszos, L.A.; Phipps, T.L.

    1999-01-01

    Alternative limits for Cu, Ni, Pb, and Zn were developed for treated wastewater from four outfalls at a Gaseous Diffusion Plant. Guidance from the Kentucky Division of Water (KDOW) was used to (1) estimate the toxicity of the effluents using water fleas (Ceriodaphnia dubia) and fathead minnow (Pimephales promelas) larvae; (2) determine total recoverable and dissolved concentrations of Cu, Pb, Ni, and Zn ; (3) calculate ratios of dissolved metal (DM) to total recoverable metal (TRM); and (4) assess chemical characteristics of the effluents. Three effluent samples from each outfall were collected during each of six test periods; thus, a total of 18 samples from each outfall were evaluated for toxicity, DM and TRM. Subsamples were analyzed for alkalinity, hardness, pH, conductivity, and total suspended solids. Short-term (6 or 7 d), static renewal toxicity tests were conducted according to EPA methodology. Ceriodaphnia reproduction was reduced in one test of effluent from Outfall A , and effluent from Outfall B was acutely toxic to both test species during one test. However, the toxicity was not related to the metals present in the effluents. Of the 18 samples from each outfall, more than 65% of the metal concentrations were estimated quantities. With the exception of two total recoverable Cu values in Outfall C, all metal concentrations were below the permit limits and the federal water quality criteria. Ranges of TR for all outfalls were: Cd, ,0.1-0.4 microg/L; Cr,1.07-3.93 microg/L; Cu, 1.59-7.24 microg/L; Pb, 39%. Thus, the alternative, calculated total recoverable metal concentration provides the discharger with a ''cushion'' for meeting permit limits

  14. Summary of climatic input for waste management site suitability criteria and state of progress

    International Nuclear Information System (INIS)

    Potter, G.L.

    1978-01-01

    Because groundwater movement can have important effects on buried nuclear wastes, hydrologists need to know if future climatic changes will influence the accuracy of groundwater flow calculations. Groundwater recharge (and therefore groundwater flow) depends on surface water balance. (Surface water balance equals precipitation less losses to evaporation, runoff, and storage.) To develop input data for modeling future climatic effects, we have made the following simplifying assumptions: (1) Climate (and therefore water balance) will behave in the future very much as it has in the past. (2) Groundwater recharge responds linearly to precipitation. (3) Future long-term climatic changes can be classified into groups or regimes that are similar to those of the past. Our current research is aimed at providing input data to the Waste Management Program's site suitability task. 16 figures, 1 table

  15. Operating experience and licensing criteria relating to on-site electric power systems in Italy

    Energy Technology Data Exchange (ETDEWEB)

    Ciattaglia, S.; Grimaldi, G. [ENEA/DISP, Via Vitaliano Brancati, 48, 00144 Roma/Rome (Italy)

    1986-02-15

    The most significant events of on-site electrical power supply degradation in Italian plants took place in coincidence with severe atmospheric conditions or with the propagation of disturbances by lightning stroke inside the plant. Essential instrumentation was lost in two cases so that, for some time, no indication of the plant status was allowed. In both cases the recovery of the plant was achieved by restoration of external power supply. Corrective actions included both improvement in immunity to disturbances, redundancy, capability and physical separation and DG's reliability demonstration. Design and safety analysis of new plants are now carried out with the help of reliability studies and probabilistic risk assessment. As a result, design changes were performed on new plants to improve the reliability of DGs start-up and the independence of the electrical emergency divisions. (authors)

  16. Operating experience and licensing criteria relating to on-site electric power systems in Italy

    International Nuclear Information System (INIS)

    Ciattaglia, S.; Grimaldi, G.

    1986-01-01

    The most significant events of on-site electrical power supply degradation in Italian plants took place in coincidence with severe atmospheric conditions or with the propagation of disturbances by lightning stroke inside the plant. Essential instrumentation was lost in two cases so that, for some time, no indication of the plant status was allowed. In both cases the recovery of the plant was achieved by restoration of external power supply. Corrective actions included both improvement in immunity to disturbances, redundancy, capability and physical separation and DG's reliability demonstration. Design and safety analysis of new plants are now carried out with the help of reliability studies and probabilistic risk assessment. As a result, design changes were performed on new plants to improve the reliability of DGs start-up and the independence of the electrical emergency divisions. (authors)

  17. Optimal Site Characterization and Selection Criteria for Oyster Restoration using Multicolinear Factorial Water Quality Approach

    Science.gov (United States)

    Yoon, J.

    2015-12-01

    Elevated levels of nutrient loadings have enriched the Chesapeake Bay estuaries and coastal waters via point and nonpoint sources and the atmosphere. Restoring oyster beds is considered a Best Management Practice (BMP) to improve the water quality as well as provide physical aquatic habitat and a healthier estuarine system. Efforts include declaring sanctuaries for brood-stocks, supplementing hard substrate on the bottom and aiding natural populations with the addition of hatchery-reared and disease-resistant stocks. An economic assessment suggests that restoring the ecological functions will improve water quality, stabilize shorelines, and establish a habitat for breeding grounds that outweighs the value of harvestable oyster production. Parametric factorial models were developed to investigate multicolinearities among in situ water quality and oyster restoration activities to evaluate posterior success rates upon multiple substrates, and physical, chemical, hydrological and biological site characteristics to systematically identify significant factors. Findings were then further utilized to identify the optimal sites for successful oyster restoration augmentable with Total Maximum Daily Loads (TMDLs) and BMPs. Factorial models evaluate the relationship among the dependent variable, oyster biomass, and treatments of temperature, salinity, total suspended solids, E. coli/Enterococci counts, depth, dissolved oxygen, chlorophyll a, nitrogen and phosphorus, and blocks consist of alternative substrates (oyster shells versus riprap, granite, cement, cinder blocks, limestone marl or combinations). Factorial model results were then compared to identify which combination of variables produces the highest posterior biomass of oysters. Developed Factorial model can facilitate maximizing the likelihood of successful oyster reef restoration in an effort to establish a healthier ecosystem and to improve overall estuarine water quality in the Chesapeake Bay estuaries.

  18. Preliminary results of the search for possible Martian landing sites to be considered for future European exploration missions

    Science.gov (United States)

    Martin, P.

    2007-08-01

    considered, as well as lessons learned from past landing experiences. Finally, nolanding zones shall be identified based on a number of available criteria. A preliminary investigation and classification of potential landing sites for future European Mars exploration missions is summarised here, with the assumed following general requirements: • Moderate latitudes (e.g., 15ºS to 45ºN). Such a latitude range would be suitable for Exomars. • Low-to-moderate elevation (e.g., below 2000 m) • Relatively flat surface in the landing ellipse (e.g., slopes Power and communications systems requirements - Illumination and temperature requirements - Biological potential and planetary protection Possible landing regions on Mars resulting from this preliminary investigation can be categorised into two classes, depending on the level of risk assessed for the landing in terms of, e.g., roughness and rock abundance: • Low-risk regions: Amazonis Planitia, Utopia Planitia, and Elysium Planitia. One of their potential drawbacks is that most areas of these regions exhibit a relatively high dust index which could be detrimental to the scientific interest of the in-situ mission. • Moderate-risk regions: - Syrtis Major / Nili Fossae, where phyllosilicates and hydrated minerals can be found based on recent evidence from orbit (Mars Express/OMEGA). - Isidis Planitia, in particular because this region presents a low vertical roughness. - Chryse/Acidalia Planitia, where phyllosilicates, hydrated minerals and sulfates can be found. - The region that spans the terrains from Sinus Meridiani to Syrtis Major, between 15ºS and 45ºN. This region exhibits a high dust index, and is represented by rougher, heavily cratered terrains in many areas. Within these regions, a more detailed identification of landing sites can be performed by refining the study (top-down approach) using higher-resolution geological and compositional maps (e.g., Mars Express/HRSC-OMEGA and/or MRO/HiRISECRISM) coupled with

  19. Multi-criteria site selection for fire services: the interaction with analytic hierarchy process and geographic information systems

    Directory of Open Access Journals (Sweden)

    T. Erden

    2010-10-01

    Full Text Available This study combines AHP and GIS to provide decision makers with a model to ensure optimal site location(s for fire stations selected. The roles of AHP and GIS in determining optimal locations are explained, criteria for site selection are outlined, and case study results for finding the optimal fire station locations in Istanbul, Turkey are included. The city of Istanbul has about 13 million residents and is the largest and most populated city in Turkey. The rapid and constant growth of Istanbul has resulted in the increased number of fire related cases. Fire incidents tend to increase year by year in parallel with city expansion, population and hazardous material facilities. Istanbul has seen a rise in reported fire incidents from 12 769 in 1994 to 30 089 in 2009 according to the interim report of Istanbul Metropolitan Municipality Department of Fire Brigade. The average response time was approximately 7 min 3 s in 2009. The goal of this study is to propose optimal sites for new fire station creation to allow the Fire Brigade in Istanbul to reduce the average response time to 5 min or less. After determining the necessity of suggesting additional fire stations, the following steps are taken into account: six criteria are considered in this analysis. They are: High Population Density (HPD; Proximity to Main Roads (PMR; Distance from Existing Fire Stations (DEF; Distance from Hazardous Material Facilities (DHM; Wooden Building Density (WBD; and Distance from the Areas Subjected to Earthquake Risk (DER. DHM criterion, with the weight of 40%, is the most important criterion in this analysis. The remaining criteria have a weight range from 9% to 16%. Moreover, the following steps are performed: representation of criterion map layers in GIS environment; classification of raster datasets; calculating the result raster map (suitability map for potential fire stations; and offering a model that supports decision makers in selecting fire station sites

  20. Radioecological condition assessment and remediation criteria for sites of spent fuel and radioactive waste storage in the russian northwest

    International Nuclear Information System (INIS)

    Shandala, Nataliya; Titov, Alex; Novikova, Natalia; Kiselev, Mikhail; Romanov, Vladimir; Sneve, Malgorzata; Smith, Graham

    2008-01-01

    The Norwegian Radiation Protection Authority and the Federal Medical-Biological Agency of the Russian Federation have a regulatory cooperation programme which is concerned with management of the nuclear legacy in northwest Russia, and, in particular, the remediation of facilities for spent fuel and radioactive waste management at the former Shore Technical Bases at Andreeva Bay and Gremikha Village. New regulatory guidance documents have been developed, necessary because of the special abnormal situation at these sites, now designated as Sites of Temporary Storage, but also because of the transition from military to civilian regulatory supervision and the evolving regulatory system in the Russian Federation. This paper presents the progress made and on-going projects in 2008 which involve development of the radio-ecological basis for identifying radiation supervision area boundaries and a system of recommended dose constraints and derived control levels for protection of workers and the public. Unconditional guarantee of long-term radioecological protection serves as the basis for criteria development. Non-exceedance of these dose constraints and control levels implies compliance with radiological protection objectives related to the residual contamination. Dose reduction below proposed dose constraint values must also be carried out according to the optimization principle. A number of remediation strategies are considered, corresponding to different future land use assumptions, including interim continued use in a nuclear context. The developed criteria relate to conditions of facilities and surrounding areas at the sites of temporary storage after completion of their remediation, and during the interim stages of remediation, depending upon the remediation strategy adopted. (author)

  1. Siting of Carsharing Stations Based on Spatial Multi-Criteria Evaluation: A Case Study of Shanghai EVCARD

    Directory of Open Access Journals (Sweden)

    Wenxiang Li

    2017-01-01

    Full Text Available Carsharing is one of the effective ways to relieve the problems of traffic jams, parking difficulties, and air pollution. In recent years, the numbers of carsharing services and their members have remarkably increased around the world. The project of electric carsharing in Shanghai, called EVCARD, has also developed rapidly with very large demand and supply. Aiming to determine the optimal locations of future stations of the EVCARD, this research employs a novel method combining the analytic hierarchy process (AHP and geographical information system (GIS with big data. Potential users, potential travel demand, potential travel purposes, and distance from existing stations are selected as the decision criteria. A siting decision system is established, consisting of 15 evaluation indicators which are calculated from multi-source data on mobile phones, taxi trajectory, point of interests (POI, and the EVCARD operation. The method of the AHP is used to determine the indicator weights, and the “Spatial Analyst” tool of ArcGIS is adopted to generate the indicator values for every 1 km × 1 km decision unit. Finally, synthetic scores are calculated to evaluate the candidate sites of EVCARD stations. The results of the case study verify the effectiveness of the proposed method, which can provide a more scientific and feasible method for carsharing operators to site stations, avoiding aimless and random decisions.

  2. GIS-BASED SOLAR AND WIND TURBINE SITE SELECTION USING MULTI-CRITERIA ANALYSIS: CASE STUDY TEHRAN, IRAN

    Directory of Open Access Journals (Sweden)

    M. Sadeghi

    2017-09-01

    Full Text Available Renewable energy has less negative impacts on environment than fossil fuels. Iran has many resources for renewable energy exploitation but because of their high price, it has not been developed. Site selection is an important step for utilizing large investments like solar farms and wind turbines. Multi-criteria evaluation methods are commonly used for site selection. The purpose of this paper is to determine suitable sites for solar farm and wind turbine using GIS and AHP in Tehran, in order to generate a distributed network to increase power network stability. The final land suitability index was grouped in four categories as “most suitable”, “suitable”, “moderate” and “low suitable”. As a result 94.61% (789939.63 km2 is low suitable, 4.47% (37337.17 km2 is moderate, 0.59% (4964.22 km2 is suitable and 0.32% (2680.70 km2 is the most suitable for building wind turbine and for solar farm, 44.07% (8116.88 km2 is low suitable, 12.81% (2359.79 km2 is moderate, 35.10% (6464.29 km2 is suitable and 8.02% (1477.28 km2 is the most suitable.

  3. Gis-Based Solar and Wind Turbine Site Selection Using Multi-Criteria Analysis: Case Study Tehran, Iran

    Science.gov (United States)

    Sadeghi, M.; Karimi, M.

    2017-09-01

    Renewable energy has less negative impacts on environment than fossil fuels. Iran has many resources for renewable energy exploitation but because of their high price, it has not been developed. Site selection is an important step for utilizing large investments like solar farms and wind turbines. Multi-criteria evaluation methods are commonly used for site selection. The purpose of this paper is to determine suitable sites for solar farm and wind turbine using GIS and AHP in Tehran, in order to generate a distributed network to increase power network stability. The final land suitability index was grouped in four categories as "most suitable", "suitable", "moderate" and "low suitable". As a result 94.61% (789939.63 km2) is low suitable, 4.47% (37337.17 km2) is moderate, 0.59% (4964.22 km2) is suitable and 0.32% (2680.70 km2) is the most suitable for building wind turbine and for solar farm, 44.07% (8116.88 km2) is low suitable, 12.81% (2359.79 km2) is moderate, 35.10% (6464.29 km2) is suitable and 8.02% (1477.28 km2) is the most suitable.

  4. Preliminary site survey report for the Uniroyal Chemical Company, formerly the Diamond Magnesium Company, 720 Fairport-Nursery Road, Painesville, Ohio (DMP001)

    International Nuclear Information System (INIS)

    Foley, R.D.; Floyd, L.M.

    1990-03-01

    At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducted a preliminary radiological survey at the Uniroyal Chemical Company, formerly the Diamond Magnesium Company, 720 Fairport-Nursery Road, Painesville, Ohio (DMP001), in 1988. The purpose of the survey was to determine whether the property was contaminated with radioactive residues from the former Manhattan Engineer District (MED) project. The scope of this preliminary survey primarily covered the area west of the buildings around the railroad car spill containment basin. The survey included direct measurement of gamma radiation levels at the surface and soil sampling for radionuclide analyses. Results of the survey demonstrated radionuclide concentrations in excess of the DOE Formerly Utilized Sites Remedial Action Program criteria for both 238 U and 226 Ra in soil. Based on the results of this radiological assessment, it is recommended that a follow-up, detailed radiological survey of both surface and subsurface environs be performed to more precisely define the extent of the contamination. 5 refs., 10 figs., 3 tabs

  5. Preliminary recommendations on the design of the characterization program for the Hanford Site single-shell tanks: A system analysis

    International Nuclear Information System (INIS)

    Buck, J.W.; Peffers, M.S.; Hwang, S.T.

    1991-11-01

    The work described in this volume was conducted by Pacific Northwest Laboratory to provide preliminary recommendations on data quality objectives (DQOs) to support the Waste Characterization Plan (WCP) and closure decisions for the Hanford Site single-shell tanks (SSTs). The WCP describes the first of a two-phase characterization program that will obtain information to assess and implement disposal options for SSTs. This work was performed for the Westinghouse Hanford Company (WHC), the current operating contractor on the Hanford Site. The preliminary DQOs contained in this volume deal with the analysis of SST wastes in support of the WCP and final closure decisions. These DQOs include information on significant contributors and detection limit goals (DLGs) for SST analytes based on public health risk

  6. A geographic information system and multi criteria analysis method for site selection of spent nuclear fuel disposal

    International Nuclear Information System (INIS)

    Martins, Vivian Borges

    2009-01-01

    This thesis aims to develop a site selection methodology for the construction of final repository for the spent nuclear fuel disposal, by using geographic information systems (GIS) and multi-criteria decision analysis. Decision making processes of this kind are often complex, given the great number of space parameters to consider and also the typically conflicting opinions of the diverse stake holders. By using GIS, data from different space parameters can be quickly and reliably stored, treated and analyzed. Multi-criteria techniques allow for the incorporation of different stake holders' opinions. These tools, when jointly used, allow for the decision process to be more transparent, quick and reliable. The method developed was applied to the particular case of the state of Rio de Janeiro. Weights obtained from an expert panel and also by using the Hierarchical Analysis Method and cartographic data were combined in the GIS. The application showed that it is possible not only to select and classify areas as to their aptness for the proposed objective, but also to exclude those clearly inadequate areas, thus optimizing the selection process by reducing the search space and consequently minimizing costs and the time spent in the search. (author)

  7. Geological Storage of CO2. Site Selection Criteria; Almacenamiento Geologico de CO2. Criterios de Selecci0n de Emplazamientos

    Energy Technology Data Exchange (ETDEWEB)

    Ruiz, C; Martinez, R; Recreo, F; Prado, P; Campos, R; Pelayo, M; Losa, A de la; Hurtado, A; Lomba, L; Perez del Villar, L; Ortiz, G; Sastre, J; Zapatero, M A; Suarez, I; Arenillas, A

    2007-09-18

    In year 2002 the Spanish Parliament unanimously passed the ratification of the Kyoto Protocol, signed December 1997, compromising to limiting the greenhouse gas emissions increase. Later on, the Environment Ministry submitted the Spanish National Assignment Emissions Plan to the European Union and in year 2005 the Spanish Greenhouse Gas market started working, establishing taxes to pay in case of exceeding the assigned emissions limits. So, the avoided emissions of CO2 have now an economic value that is promoting new anthropogenic CO2 emissions reduction technologies. Carbon Capture and Storage (CCS) are among these new technological developments for mitigating or eliminate climate change. CO2 can be stored in geological formations such as depleted oil or gas fields, deep permeable saline water saturated formations and unmailable coal seams, among others. This report seeks to establish the selection criteria for suitable geological formations for CO2 storage in the Spanish national territory, paying attention to both the operational and performance requirements of these storage systems. The report presents the physical and chemical properties and performance of CO2 under storage conditions, the transport and reaction processes of both supercritical and gaseous CO2, and CO2 trapping mechanisms in geological formations. The main part of the report is devoted to geological criteria at watershed, site and formation scales. (Author) 100 refs.

  8. Geological Storage of CO2. Site Selection Criteria; Almacenamiento Geologico de CO2. Criterios de Seleccion de Emplazamientos

    Energy Technology Data Exchange (ETDEWEB)

    Ruiz, C; Martinez, R; Recreo, F; Prado, P; Campos, R; Pelayo, M; Losa, A de la; Hurtado, A; Lomba, L; Perez del Villar, L; Ortiz, G; Sastre, J

    2006-07-01

    In year 2002 the Spanish Parliament unanimously passed the ratification of the Kyoto Protocol, signed December 1997, compromising to limiting the greenhouse gas emissions increase. Later on, the Environment Ministry submitted the Spanish National Assignment Emissions Plan to the European Union and in year 2005 the Spanish Greenhouse Gas market started working, establishing taxes to pay in case of exceeding the assigned emissions limits. So, the avoided emissions of CO2 have now an economic value that is promoting new anthropogenic CO2 emissions reduction technologies. Carbon Capture and Storage (CCS) are among these new technological developments for mitigating or eliminate climate change. CO2 can be stored in geological formations such as depleted oil or gas fields, deep permeable saline water saturated formations and unmineable coal seams, among others. This report seeks to establish the selection criteria for suitable geological formations for CO2 storage in the Spanish national territory, paying attention to both the operational and performance requirements of these storage systems. The report presents the physical and chemical properties and performance of CO2 under storage conditions, the transport and reaction processes of both supercritical and gaseous CO2, and CO2 trapping mechanisms in geological formations. The main part of the report is devoted to geological criteria at watershed, site and formation scales. (Author) 100 ref.

  9. GIS and Multi Criteria Decision Method Based Approach of Identifying Appropriate Landfill Sites for the City Of Chittagong

    Directory of Open Access Journals (Sweden)

    M. Ali Ashraf

    2015-02-01

    Full Text Available  Urban solid waste management is a serious environmental issue confronting the cities in developing countries like Bangladesh. Apathy towards the problem, inadequacy of field level information and data, and resource constraints may be blamed for the dismal situation of solid waste management often visible in our cities. The most common problems associated with the absence of sustainable solid waste management practice include diseases transmission, odour nuisance, atmospheric and water pollution, visual blight, fire hazards and economic losses. In the three major cities of Bangladesh, Dhaka, Chittagong & Khulna, per capita production of solid waste is around 0.4kg /capita / day, but only a fraction of this waste is carried to the final disposal site. A recent study on Municipal Solid Waste Management found that waste generated in Chittagong was 0.352kg/cap/day. Considering per capita generation of solid waste as 0.352kg to 0.4kg per capita per day, for a population of 25, 92,459 distributed within the 41 wards of the city (BBS, 2011, total solid waste generated in Chittagong will be around 913 tons to 1037 tons per day in 2012. Currently, Chittagong City Corporation (CCC has only two dumping yards: one at Ananda Bazar, Halishahar at the mid western part of the city and the other at Arefin Nagar, Pahartali at the northern tip of the city. None of these sites are sanitary landfill. Considering the city area of 168 sq. kms, only two dumping sites are not sufficient to cater to the requirement of the city. Long distances between the collection points and the disposal site are responsible for inefficient utilization of the CCC trucks and the resulting increase in the haulage time that eventually increases the costs of collection and disposal. This study utilized Geographic Information System (GIS and Multi-Criteria Decision Method (MCDM for the identification and selection of appropriate landfill sites within the city of Chittagong. Thirteen sites

  10. Artificially regenerating longleaf pine on wet sites: preliminary analysis of effects of site preparation treatments on early survival and growth

    Science.gov (United States)

    Benjamin O. Knapp; G. Geoff Wang; Joan L. Walker

    2010-01-01

    Our study, conducted over two years on poorly drained, sandy sites in Onslow County, NC, compared the effects of eight common site preparation treatments on early survival and growth of planted longleaf pine seedlings. Through two growing seasons, we found survival to be similar across all treatments (p = 0.8806), but root collar diameter was greatest with combinations...

  11. Results of the preliminary radiological survey at the former Diamond Magnesium Company site, Luckey, Ohio (DML001)

    International Nuclear Information System (INIS)

    Foley, R.D.; Crutcher, J.W.

    1990-02-01

    As part of the Formerly Utilized Sites Remedial Action Program, the US Department of Energy (DOE) is implementing a radiological survey program to determine the radiological conditions at sites that were used by the department's predecessor agencies. One such site is the former Diamond Magnesium Company facility in Luckey, Ohio. The preliminary radiological survey discussed in this report was conducted at the request of DOE by members of the Measurement Applications and Development group of Oak Ridge National Laboratory in December 1988. The former Diamond Magnesium Company site in Luckey, Ohio, was used as a magnesium reduction plant during World War 2. It was closed in 1945 and reopened in 1949 as a beryllium production facility, operated by Brush Wellman for the US Atomic Energy Commission. The preliminary radiological survey included: a surface gamma scan of part of the property outdoors, collection of surface and subsurface soil samples, and collection of water samples. Laboratory analysis of soil samples showed concentrations of 226 Ra in excess of applicable DOE guidelines. A follow-up, detailed survey is recommended. 9 refs., 10 figs., 4 tabs

  12. Optimal Siting of Charging Stations for Electric Vehicles Based on Fuzzy Delphi and Hybrid Multi-Criteria Decision Making Approaches from an Extended Sustainability Perspective

    Directory of Open Access Journals (Sweden)

    Huiru Zhao

    2016-04-01

    Full Text Available Optimal siting of electric vehicle charging stations (EVCSs is crucial to the sustainable development of electric vehicle systems. Considering the defects of previous heuristic optimization models in tackling subjective factors, this paper employs a multi-criteria decision-making (MCDM framework to address the issue of EVCS siting. The initial criteria for optimal EVCS siting are selected from extended sustainability theory, and the vital sub-criteria are further determined by using a fuzzy Delphi method (FDM, which consists of four pillars: economy, society, environment and technology perspectives. To tolerate vagueness and ambiguity of subjective factors and human judgment, a fuzzy Grey relation analysis (GRA-VIKOR method is employed to determine the optimal EVCS site, which also improves the conventional aggregating function of fuzzy Vlsekriterijumska Optimizacijia I Kompromisno Resenje (VIKOR. Moreover, to integrate the subjective opinions as well as objective information, experts’ ratings and Shannon entropy method are employed to determine combination weights. Then, the applicability of proposed framework is demonstrated by an empirical study of five EVCS site alternatives in Tianjin. The results show that A3 is selected as the optimal site for EVCS, and sub-criteria affiliated with environment obtain much more attentions than that of other sub-criteria. Moreover, sensitivity analysis indicates the selection results remains stable no matter how sub-criteria weights are changed, which verifies the robustness and effectiveness of proposed model and evaluation results. This study provides a comprehensive and effective method for optimal siting of EVCS and also innovates the weights determination and distance calculation for conventional fuzzy VIKOR.

  13. Site study plan for regional hydrologic sampling and monitoring: Preliminary draft

    International Nuclear Information System (INIS)

    Dutton, A.R.

    1987-01-01

    The purpose of the Regional Hydrologic Studies Plan is to describe those field activities required for completion of the objectives of hydrologic activities. Many of these activities are regional in scope and are designed to provide a framework for understanding the hydrologic setting of the site and the hydrologic processes that influence site characteristics. Site Study Plans (SSPs) define activates at and in the immediate vicinity of the site. The activities specified in the Regional Hydrologic Studies Plan are performed beyond the confines of the site because the hydrologic systems extend beyond the site boundaries, because pertinent data that bear on site suitability are available outside of the site, and because natural analogues exist outside of the site that allow analysis of processes that are expected to operate within the site. 15 refs., 5 figs., 1 tab

  14. Hydrogeochemical evaluation. Preliminary site description Forsmark area - version 1.2

    International Nuclear Information System (INIS)

    Laaksoharju, Marcus

    2005-03-01

    bedrock is estimated to be less than in other investigated sites such as Simpevarp and Laxemar, where the presence of Quaternary overburden is less important. The hydrogeologic behaviour of the Quaternary overburden in Forsmark provides a plausible explanation for the preservation of Littorina Sea signatures found in several groundwater samples, even at very shallow depths. Other (and complementary) explanations can be related with the flat topography, as well as with the fact that the Forsmark site has emerged over the sea level more recently than other investigated sites. The modelling indicates also that the groundwater composition at repository depths is such that the representative samples from KFM02A: 509-516 m and KFM03A: 448-453 m can meet the SKB chemical stability criteria for Eh, pH, TDS, DOC and Ca+Mg. In this evaluation the groundwater flow model has been updated, the salinity distribution, mixing processes and the major reactions altering the groundwaters have been modelled down to a depth of 1,000 m, and an updated Hydrogeochemical site descriptive model version 1.2 has been produced. More groundwater and isotopic data, together with microbial information, colloids and gases, provided additional site descriptive information. Finally, the introduction of coupled modelling provided further possibilities to address independently the various processes in question

  15. Hydrogeochemical evaluation. Preliminary site description Forsmark area - version 1.2

    Energy Technology Data Exchange (ETDEWEB)

    Laaksoharju, Marcus (ed.) [Geopoint AB, Stockholm (Sweden)

    2005-03-15

    effective recharge into the granitic bedrock is estimated to be less than in other investigated sites such as Simpevarp and Laxemar, where the presence of Quaternary overburden is less important. The hydrogeologic behaviour of the Quaternary overburden in Forsmark provides a plausible explanation for the preservation of Littorina Sea signatures found in several groundwater samples, even at very shallow depths. Other (and complementary) explanations can be related with the flat topography, as well as with the fact that the Forsmark site has emerged over the sea level more recently than other investigated sites. The modelling indicates also that the groundwater composition at repository depths is such that the representative samples from KFM02A: 509-516 m and KFM03A: 448-453 m can meet the SKB chemical stability criteria for Eh, pH, TDS, DOC and Ca+Mg. In this evaluation the groundwater flow model has been updated, the salinity distribution, mixing processes and the major reactions altering the groundwaters have been modelled down to a depth of 1,000 m, and an updated Hydrogeochemical site descriptive model version 1.2 has been produced. More groundwater and isotopic data, together with microbial information, colloids and gases, provided additional site descriptive information. Finally, the introduction of coupled modelling provided further possibilities to address independently the various processes in question.

  16. 75 FR 984 - Draft Recommended Interim Preliminary Remediation Goals for Dioxin in Soil at CERCLA and RCRA Sites

    Science.gov (United States)

    2010-01-07

    ...The Environmental Protection Agency (EPA or the Agency) is announcing a 50-day public comment period for draft recommended interim preliminary remediation goals (PRGs) developed in the Draft Recommended Interim Preliminary Remediation Goals for Dioxin in Soil at Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) and Resource Conservation and Recovery Act (RCRA) Sites. EPA's Office of Solid Waste and Emergency and Emergency Response (OSWER) has developed the draft recommended interim PRGs for dioxin in soil. These draft recommended interim PRGs were calculated using existing, peer- reviewed toxicity values and current EPA equations and default exposure assumptions. This Federal Register notice is intended to provide an opportunity for public comment on the draft recommended interim PRGs. EPA will consider any public comments submitted in accordance with this notice and may revise the draft recommended interim PRGs thereafter.

  17. Lessons learned from the preliminary performance assessment exercise for the Vienne site strategies for investigating the granodiorite confinement capability

    International Nuclear Information System (INIS)

    Lebon, P.

    1999-01-01

    One of the three sites under study by ANDRA is located on the Poitou shoal in the Vienne Department. The granitic basement rock is overlain by a 160 m thick layer of Jurassic sediments containing two seasonally pumped aquifers. The preliminary hydrogeological model of the granitic basement assumed that regional flow is SE-NW, and circulates in the hecto-metric fractures, and that groundwater flow velocity is very low. A preliminary performance assessment exercise focusing on the geological barrier was carried out based on these assumptions and a disposal concept where radwaste is stored in separate granodiorite 'blocks' delimited by the water-bearing fractures. As regards of the granodioritic blocks, the programme goals include analysing of detailed structure, obtaining uncontaminated samples of interstitial ground water in order to determine its physicochemical properties and evaluating transport and retention parameters. (author)

  18. Effect of ionizing radiation on radionuclide speciation: Preliminary results from site-specific experiments in a basaltic system

    International Nuclear Information System (INIS)

    Reed, D.T.; Burnell, J.R.

    1986-01-01

    Rockwell Hanford Operations, under contract to the Department of Energy, is investigating the suitability of the Hanford site in the state of Washington as a high level nuclear waste repository. An important consideration in these investigations is the effect of ionizing radiation on the speciation of radionuclides in the groundwater after the high-level-waste container has been breached and there is direct contact between the groundwater and the waste form (controlled released period). The effect of ionizing radiation on radionuclide speciation depends on the radiation environment and site-specific chemistry near the waste container. With respect to these two aspects, the following results will be presented: a definition of the radiation environment during the controlled release period; preliminary site-specific experimental results: (1) basaltic systems spiked with radionuclides; (2) spent fuel-groundwater-basalt experiments

  19. What requirements does the KBS-3 repository make on the host rock? Geoscientific suitability indicators and criteria for siting and site evaluation

    International Nuclear Information System (INIS)

    Andersson, Johan; Stroem, Anders; Svemar, Christer; Almen, Karl-Erik; Ericsson, Lars O.

    2000-04-01

    This report gives an account of what requirements are made on the rock, what conditions in the rock are advantageous and how the fulfilment of requirements and preferences is to be judged prior to the selection of sites for a site investigation and during a site investigation. The conclusions and results of the report are based on the knowledge and experience acquired by SKB over many years of research and development. The results, and particularly the stipulated criteria, apply to a repository for spent fuel of the KBS-3 type, i.e. a repository where the fuel is contained in copper canisters embedded in bentonite clay at a depth of 400 - 700 m in the Swedish crystalline basement. The report analyzes how the rock's different geological conditions, mechanical, thermal, hydrogeological, chemical and transport properties influence the functions of the deep repository, and whether it is possible to determine requirements and preferences regarding the influence of these properties. Where possible, these requirements or preferences have then been translated into requirements or preferences regarding the individual properties. Criteria are formulated that are based on the quantities that can be measured or estimated at the relevant stage of the investigation. The following requirements are made on the rock: The rock in the repository's deposition zone may not have any ore potential. Regional plastic shear zones shall be avoided if it cannot be demonstrated that the properties of the zone do not deviate from those of the rest of the rock. There may, however, be so-called 'tectonic lenses' near regional plastic shear zones where the bedrock is homogeneous and relatively unaffected. Deposition tunnels and deposition holes for canisters may not pass through or be positioned too close to major regional and major local fracture zones. Deposition holes may not intersect identified local minor fracture zones. The rock's strength, fracture geometry and initial stresses may not be

  20. Chemical Analysis of the Moon at the Surveyor VI Landing Site: Preliminary Results.

    Science.gov (United States)

    Turkevich, A L; Patterson, J H; Franzgrote, E J

    1968-06-07

    The alpha-scattering experiment aboard soft-landing Surveyor VI has provided a chemical analysis of the surface of the moon in Sinus Medii. The preliminary results indicate that, within experimental errors, the composition is the same as that found by Surveyor V in Mare Tranquillitatis. This finding suggests that large portions of the lunar maria resemble basalt in composition.

  1. Transforming Pinus pinaster forest to recreation site: preliminary effects on LAI, some forest floor, and soil properties.

    Science.gov (United States)

    Öztürk, Melih; Bolat, İlyas

    2014-04-01

    This study investigates the effects of forest transformation into recreation site. A fragment of a Pinus pinaster plantation forest was transferred to a recreation site in the city of Bartın located close to the Black Sea coast of northwestern Turkey. During the transformation, some of the trees were selectively removed from the forest to generate more open spaces for the recreationists. As a result, Leaf Area Index (LAI) decreased by 0.20 (about 11%). Additionally, roads and pathways were introduced into the site together with some recreational equipment sealing parts of the soil surface. Consequently, forest environment was altered with a semi-natural landscape within the recreation site. The purpose of this study is to assess the effects of forest transformation into recreation site particularly in terms of the LAI parameter, forest floor, and soil properties. Preliminary monitoring results indicate that forest floor biomass is reduced by 26% in the recreation site compared to the control site. Soil temperature is increased by 15% in the recreation site where selective removal of trees expanded the gaps allowing more light transmission. On the other hand, the soil bulk density which is an indicator of soil compaction is unexpectedly slightly lower in the recreation site. Organic carbon (C(org)) and total nitrogen (N(total)) together with the other physical and chemical parameter values indicate that forest floor and soil have not been exposed to much disturbance. However, subsequent removal of trees that would threaten the vegetation, forest floor, and soil should not be allowed. The activities of the recreationists are to be concentrated on the paved spaces rather than soil surfaces. Furthermore, long-term monitoring and management is necessary for both the observation and conservation of the site.

  2. Developing remediation criteria on the basis of health and ecological risks at a former sour gas plant site

    International Nuclear Information System (INIS)

    Brown, G. L.; Wilson, R. M.; Clyde, G. A.; Chollak, D. F.

    1997-01-01

    A human health and ecological risk assessment was completed for the Okotoks sour gas processing gas plant, based on the existing environmental sampling and toxicity testing that has been collected at the site since 1987. For the human health risk assessment, two potential scenarios were considered, including industrial use and parkland use. The ecological risk assessment involved synthesis of existing sampling and toxicity testing results as well as the assessment of potential risk to ecological receptors such as the meadow vole, red-tailed hawk and cattle. The assessment included chemical screening, receptor and exposure pathway selection, toxicity assessment of chemicals of concern, estimation of exposures, risk characterization and generation of soil and groundwater remediation criteria. Results of the assessments to date indicate that limited subsurface remediation is required for the protection of human health under industrial/parkland use. In contrast, ecological considerations will require remediation or reclamation of surface soil and the imposition of certain risk management controls, such as e. g. encumbrances on land title. 2 figs

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

    International Nuclear Information System (INIS)

    1987-06-01

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

  4. Site Study Plan for meteorology/air quality, Deaf Smith County site, Texas: Environmental Field Program: Preliminary draft

    International Nuclear Information System (INIS)

    1987-06-01

    The Meteorological/Air Quality Site Study Plan describes a field program consisting of continuous measurements of surface (10-meter) wind speed and direction, temperature, humidity, dew point, pressure, and sensible heat flux (vertical). Air quality measurements will be limited to suspended particulate matter. After the first year of measurements, a 60-meter tower will be added to incorporate measurements needed for later modeling and dose calculations; these will include upper level winds, vertical temperature structure, and vertical wind speed. All of these measurements will be made at a site located within the 9-mi 2 site area but remote from the ESF. A second site, located near and downwind from the ESF, will monitor only particulate matter. The SSP describes the need for each study; its design and design rationale; analysis, management, and use of data, schedule of field activities, organization of field personnel and sample management, and quality assurance requirements. These studies will provide data needed to satisfy requirements contained in, or derived from the Salt Repository Project Requirements Document. 38 refs., 8 figs., 3 tabs

  5. Preliminary screening analysis of the off-site environment downstream of the US Department of Energy Oak Ridge Reservation

    International Nuclear Information System (INIS)

    Blaylock, B.G.; Hoffman, F.O.; Frank, M.L.

    1990-01-01

    Operations and waste disposal activities at the Y-12 Plant, the Oak Ridge National Laboratory (ORNL), and the Oak Ridge Gaseous Diffusion Plant (ORGDP), located on the US Department of Energy (DOE) Oak Ridge Reservation (ORR) in eastern Tennessee, have introduced airborne, liquid, and solid wastes into the surrounding environment. Some of these wastes may affect off-site areas by entering local streams that ultimately drain into the Clinch River. Previously reported concentrations of radionuclides, metals, and organic compounds in water, sediment, and biota of the Clinch River and Watts Bar Reservoir suggest the presence of contaminants of possible concern to the protection of human health and the environment. A preliminary screening was conducted of contaminants in the off-site surface water environments downstream of the DOE ORR. This screening analysis represents part of a scoping phase of the Clinch River Resource Conservation and Recovery Facilities Investigation (CRRFI). The purpose of this preliminary screening analysis is to use existing data on off-site contaminant concentrations to identify and prioritize potential contaminants of concern for further evaluation and investigation. The primary objective of this screening analysis is to ensure that CRRFI sampling and analysis efforts focus on those contaminants that may possibly contribute to human health or environmental risk. 8 refs., 3 figs., 6 tabs

  6. Preliminary site investigation for LL and IL radwaste disposal for Qinshan NPP

    International Nuclear Information System (INIS)

    Huang Yawen; Chen Zhangru

    1993-01-01

    With the purpose of selecting a disposal site for the low- and intermediate-level radwastes arising from Qinshan NPP, site investigations were carried out in several districts of Zhejiang Province. Investigation objectives included the circumstances of geology, hydrogeology, environmental ecology, and social economy. On the basis of collected data, five possible sites were recommended for policy-making reference and further investigation

  7. Evaluation of the state of stress at the Forsmark site. Preliminary site investigation Forsmark area - version 1.2

    Energy Technology Data Exchange (ETDEWEB)

    Sjoeberg, Jonny; Lindfors, Ulf; Perman, Fredrik; Ask, Daniel [SwedPower AB, Stockholm (Sweden)

    2005-09-15

    This report presents an evaluation of the state of stress at the Forsmark site, based on all conducted stress measurements to date at the site, indirect stress estimates, geological and tectonic description of the site, and regional stress data from nearby locations. The work included (i) compilation of measurement results from Forsmark, as well as from nearby (regional) sites/locations, (ii) analysis of confidence intervals for each group of measurement, (iii) assessment of the stress state for the Forsmark site accounting for geological/tectonic evolution at the site, (iv) assessment of stress state for selected nearby (regional) sites/locations, and (v) comparison and combined interpretation of similarities and/or differences in stress state from a regional perspective. The combined assessment of the local (site-scale) and regional stress data for Forsmark showed that the major stress is orientated sub-horizontally and trending NW-SE; however, with significant local variation. A thrust faulting ({sigma}H > {sigma}h > {sigma}v) or possibly strike-slip faulting ({sigma}H > {sigma}v > {sigma}h) stress regime is evident at the Forsmark site. The maximum horizontal stress tends to be higher at the site compared to nearby sites and regional conditions. The site and regional data indicate that the vertical stress seems to be solely due to the overburden pressure. The lack of solid core discing for large portions of the boreholes at Forsmark was used to estimate an upper limit of the maximum horizontal stress magnitude. However, such an estimation is highly uncertain due to e.g. partly unknown mechanism for core discing failure, and unknown effects of the simplifying assumptions made in the analysis. The possible effects of shallow-dipping deformation zones on the stress state, could not be verified from the currently available data. However, the possibility of different stress regimes above and below deformation zones must be considered in future work. Slightly lower

  8. Evaluation of the state of stress at the Forsmark site. Preliminary site investigation Forsmark area - version 1.2

    International Nuclear Information System (INIS)

    Sjoeberg, Jonny; Lindfors, Ulf; Perman, Fredrik; Ask, Daniel

    2005-09-01

    This report presents an evaluation of the state of stress at the Forsmark site, based on all conducted stress measurements to date at the site, indirect stress estimates, geological and tectonic description of the site, and regional stress data from nearby locations. The work included (i) compilation of measurement results from Forsmark, as well as from nearby (regional) sites/locations, (ii) analysis of confidence intervals for each group of measurement, (iii) assessment of the stress state for the Forsmark site accounting for geological/tectonic evolution at the site, (iv) assessment of stress state for selected nearby (regional) sites/locations, and (v) comparison and combined interpretation of similarities and/or differences in stress state from a regional perspective. The combined assessment of the local (site-scale) and regional stress data for Forsmark showed that the major stress is orientated sub-horizontally and trending NW-SE; however, with significant local variation. A thrust faulting (σH > σh > σv) or possibly strike-slip faulting (σH > σv > σh) stress regime is evident at the Forsmark site. The maximum horizontal stress tends to be higher at the site compared to nearby sites and regional conditions. The site and regional data indicate that the vertical stress seems to be solely due to the overburden pressure. The lack of solid core discing for large portions of the boreholes at Forsmark was used to estimate an upper limit of the maximum horizontal stress magnitude. However, such an estimation is highly uncertain due to e.g. partly unknown mechanism for core discing failure, and unknown effects of the simplifying assumptions made in the analysis. The possible effects of shallow-dipping deformation zones on the stress state, could not be verified from the currently available data. However, the possibility of different stress regimes above and below deformation zones must be considered in future work. Slightly lower horizontal stress was found in

  9. TRANSIT: model for providing generic transportation input for preliminary siting analysis

    International Nuclear Information System (INIS)

    McNair, G.W.; Cashwell, J.W.

    1985-02-01

    To assist the US Department of Energy's efforts in potential facility site screening in the nuclear waste management program, a computerized model, TRANSIT, is being developed. Utilizing existing data on the location and inventory characteristics of spent nuclear fuel at reactor sites, TRANSIT derives isopleths of transportation mileage, costs, risks and fleet requirements for shipments to storage sites and/or repository sites. This technique provides a graphic, first-order method for use by the Department in future site screening efforts. 2 refs

  10. Preliminary studies on trace element contamination in dumping sites of municipal wastes in India and Vietnam

    Science.gov (United States)

    Agusa, T.; Kunito, T.; Nakashima, E.; Minh, T. B.; Tanabe, S.; Subramanian, A.; Viet, P. H.

    2003-05-01

    The disposal of wastes in dumping sites has increasingly caused concem about adverse health effects on the populations living nearby. However, no investigation has been conducted yet on contamination in dumping sites of municipal wastes in Asian developing countries. In this study, concentrations of 11 trace elements (V, Cr, Mn, Co, Cu, Zn, Mo, Ag, Cd, Sb and Pb) were detennined in scalp hair from the population living nearby and in soil from dumping sites and control sites of India and Vietnam. Soil samples in dumping site in India showed significantly higher concentrations of some trace elements than soils in control site, whereas this trend was not notable in Vietnam. This is probably due to the fact that the wastes were covered with the soil in the dumping site of Vietnam. Cadmium concentrations in some hair samples of people living near dumping site in India and Vietnam exceeded the level associated with learning disorder in children. Levels of most of the trace elements in hair were significantly higher in dumping site than those in control site in India and Vietnam, suggesting direct or indirect exposure to those elements from dumping wastes. To our knowledge, this is the first study of trace element contamination in dumping sites in India and Vietnam.

  11. Geoscientific long-term prognosis. Preliminary safety analysis for the site Gorleben; Geowissenschaftliche Langzeitprognose. Bericht zum Arbeitspaket 2. Vorlaeufige Sicherheitsanalyse fuer den Standort Gorleben

    Energy Technology Data Exchange (ETDEWEB)

    Mrugalla, Sabine [Bundesanstalt fuer Geowissenschaften und Rohstoffe, Hannover (Germany)

    2011-07-15

    The preliminary safety analysis of the site Gorleben includes the following chapters: (1) Introduction; (2) Aim and content of the geoscientific long-term prognosis for the site Gorleben; (3) Boundary conditions at the site Gorleben: climate; geomorphology; overlying rocks and adjoining rocks; hydrogeology; salt deposit Gorleben. (4) Probable future geological developments at the site Gorleben: supraregional developments with effects on the site Gorleben; glacial period developments; developments of the geomorphology, overlying and adjoining rocks; future developments of the hydrological systems at the site Gorleben; future saliniferous specific developments of the salt deposit Gorleben. (5) Commentary on the unlikely or excludable developments of the site Gorleben.

  12. Site Study Plan for background environmental radioactivity, Deaf Smith County site, Texas: Environmental Field Program: Preliminary draft

    International Nuclear Information System (INIS)

    1987-06-01

    The Background Environmental Radioactivity Site Study Plan describes a field program consisting of an initial radiological survey and a radiological sampling program. The field program includes measurement of direct radiation and collection and analysis of background radioactivity samples of air, precipitation, soil, water, milk, pasture grass, food crops, meat, poultry, game, and eggs. The plan describes for each study: the need for the study, the study design, data management and use, schedule of proposed activities, and quality assurance requirements. These studies will provide data needed to satisfy requirements contained in, or derived from, the Salt Repository Project (SRP) Requirements Document. 50 refs., 11 figs., 7 tabs

  13. Technical procedures for implementation of acoustics site studies, Deaf Smith County site, Texas: Environmental Field Program: Preliminary draft

    International Nuclear Information System (INIS)

    1987-09-01

    The purpose and scope of the technical procedure for processing data from the tethered meteorological system are covered. Definitions, interfaces, and concurrent data needs are also addressed. This technical procedure describes how to control, organize, verify, and archive tethered meteorological system data. These data will be received at the processing location from the field measurement location and are part of the characterization of the Deaf Smith County Site, Texas for the salt repository program. These measurements will be made in support of the sound propagation study and are a result of environmental data requirements for acoustics. 6 refs., 15 figs., 5 tabs

  14. Preliminary research on groundwater flow characteristics of the low- and Intermediate-level radioactive waste disposal site

    International Nuclear Information System (INIS)

    Koh, Young Kwon; Bae, Dae Seok; Kim, Geon Young; Ryu, Ji Hoon; Park, Kyung Woo; Ji, Sung Hoon; Kim, Kyung Su

    2009-08-01

    Preliminary site survey and candidate survey complements the purpose of the current site selection and disposal place selected for the study because of hydraulic to the geological survey done for the general idea was brought in the field of geochemistry survey was made. Therefore, this report hydraulic - the underlying structure of the model deterministic deformation zone model to focus on the configuration kept, according to data survey by hydraulic and hydraulic rock star pitcher trying to figure out the scope of the structure factors were hydraulic. Groundwater and related land place shares characteristics of the existing data and complementary research and laboratory research performed on the basis of geochemical data, based on the following major finding were present

  15. Preliminary Information on the Vertebrate Fauna (Animalia: Vertebrata of the NATURA2000 Site “Rice Fields Tsalapitsa” (Bulgaria

    Directory of Open Access Journals (Sweden)

    Ivayla L. Klimentova

    2011-12-01

    Full Text Available The study was carried out by tree visits in different areas of the Natura 2000 site “Rice Fields Tsalapitsa” BG 0002086 (West of Plovdiv city, near village of Tsalapitsa. Our preliminary research showed that in the area vertebrates with high conservation status occurred included in the Bulgarian Bidiversity Act, Appendix II and III, Appendix II of the Bern convention, Natura 2000 species list, the Bonn convention, Appendix II, the Convention of the International Trade of Endangered Species, and the list of the International Union for Conservation of the Nature. This information will help in future preparation of the management plan of the Natura 2000 site and showed the need of studies focused on such areas which will help undertaking adequate measures for their proper way of conservation.

  16. A study on safety concept and criteria of site release of nuclear installation proposed by international organizations and adopted in decommissioning practices

    International Nuclear Information System (INIS)

    Enokido, Yuji; Miyasaka, Yasuhiko; Ishikawa, Hironori

    2008-01-01

    Regulatory systems and safety criteria of site release of nuclear installation proposed by international organizations such as IAEA and applied in decommissioning in domestic and foreign countries have been studied, in order to avail them to deliberate the relevant domestic regulation and guides. In addition, the applicability of the proposal and practices to domestic legislation have been discussed. Regarding the national safety criteria, the annual individual dose constraint is optimized between 10 μSv and 300 μSv after recommendation and/or guides of IAEA etc. Unconditional release should be achieved, but the conditional and/or partial site release are possible under the same safety criteria to make the selection flexible for licensees. (author)

  17. A criticism of applications with multi-criteria decision analysis that are used for the site selection for the disposal of municipal solid wastes

    International Nuclear Information System (INIS)

    Kemal Korucu, M.; Erdagi, Bora

    2012-01-01

    Highlights: ► The existing structure of the multi-criteria decision analysis for site selection is criticized. ► Fundamental problematic points based on the critics are defined. ► Some modifications are suggested in order to provide solutions to these problematical points. ► A new structure for the decision making mechanism is proposed. ► The feasibility of the new method is subjected to an evaluation process. - Abstract: The main aim of this study is to criticize the process of selecting the most appropriate site for the disposal of municipal solid wastes which is one of the problematic issues of waste management operations. These kinds of problems are pathological symptoms of existing problematical human–nature relationship which is related to the syndrome called ecological crisis. In this regard, solving the site selection problem, which is just a small part of a larger entity, for the good of ecological rationality and social justice is only possible by founding a new and extensive type of human–nature relationship. In this study, as a problematic point regarding the discussions on ecological problems, the existing structure of the applications using multi-criteria decision analysis in the process of site selection with three main criteria is criticized. Based on this critique, fundamental problematic points (to which applications are insufficient to find solutions) will be defined. Later, some modifications will be suggested in order to provide solutions to these problematical points. Finally, the criticism addressed to the structure of the method with three main criteria and the feasibility of the new method with four main criteria is subjected to an evaluation process. As a result, it is emphasized that the new structure with four main criteria may be effective in solution of the fundamental problematic points.

  18. A criticism of applications with multi-criteria decision analysis that are used for the site selection for the disposal of municipal solid wastes

    Energy Technology Data Exchange (ETDEWEB)

    Kemal Korucu, M., E-mail: kemal.korucu@kocaeli.edu.tr [University of Kocaeli, Department of Environmental Engineering, 41380 Kocaeli (Turkey); Erdagi, Bora [University of Kocaeli, Department of Philosophy, 41380 Kocaeli (Turkey)

    2012-12-15

    Highlights: Black-Right-Pointing-Pointer The existing structure of the multi-criteria decision analysis for site selection is criticized. Black-Right-Pointing-Pointer Fundamental problematic points based on the critics are defined. Black-Right-Pointing-Pointer Some modifications are suggested in order to provide solutions to these problematical points. Black-Right-Pointing-Pointer A new structure for the decision making mechanism is proposed. Black-Right-Pointing-Pointer The feasibility of the new method is subjected to an evaluation process. - Abstract: The main aim of this study is to criticize the process of selecting the most appropriate site for the disposal of municipal solid wastes which is one of the problematic issues of waste management operations. These kinds of problems are pathological symptoms of existing problematical human-nature relationship which is related to the syndrome called ecological crisis. In this regard, solving the site selection problem, which is just a small part of a larger entity, for the good of ecological rationality and social justice is only possible by founding a new and extensive type of human-nature relationship. In this study, as a problematic point regarding the discussions on ecological problems, the existing structure of the applications using multi-criteria decision analysis in the process of site selection with three main criteria is criticized. Based on this critique, fundamental problematic points (to which applications are insufficient to find solutions) will be defined. Later, some modifications will be suggested in order to provide solutions to these problematical points. Finally, the criticism addressed to the structure of the method with three main criteria and the feasibility of the new method with four main criteria is subjected to an evaluation process. As a result, it is emphasized that the new structure with four main criteria may be effective in solution of the fundamental problematic points.

  19. Chapter 3: detailed discussion on the site selection criteria; Capitulo 3: discussao detalhada dos criterios de selecao de sitio

    Energy Technology Data Exchange (ETDEWEB)

    Atala, Drausio Lima

    2009-07-01

    This chapter discusses full detail each selection criterion and their application. A certain degree of 'customization' can be necessary for each region of interest. Some criteria can be applied depending upon the situation. Some of those criteria can be modified due to the modification on the regulation, advances of the knowledge or specific conditions which can be introduced.

  20. 40 CFR 201.23 - Test site, weather conditions and background noise criteria for measurement at a 30 meter (100...

    Science.gov (United States)

    2010-07-01

    ... background noise criteria for measurement at a 30 meter (100 feet) distance of the noise from locomotive and... and background noise criteria for measurement at a 30 meter (100 feet) distance of the noise from... meters (4 feet) above the ground at the microphone location, except as provided in paragraph (c) of this...

  1. A GIS-BASED MULTI-CRITERIA EVALUATION SYSTEM FOR SELECTION OF LANDFILL SITES: a case study from Abu Dhabi, United Arab Emirates

    Directory of Open Access Journals (Sweden)

    S. M. Issa

    2012-07-01

    Full Text Available Landfill sites receive 92% of total annual solid waste produced by municipalities in the emirate of Abu Dhabi. In this study, candidate sites for an appropriate landfill location for the Abu Dhabi municipal area are determined by integrating geographic information systems (GIS and multi-criteria evaluation (MCE analysis. To identify appropriate landfill sites, eight input map layers including proximity to urban areas, proximity to wells and water table depth, geology and topography, proximity to touristic and archeological sites, distance from roads network, distance from drainage networks, and land slope are used in constraint mapping. A final map was generated which identified potential areas showing suitability for the location of the landfill site. Results revealed that 30% of the study area was identified as highly suitable, 25% as suitable, and 45% as unsuitable. The selection of the final landfill site, however, requires further field research.

  2. What requirements does the KBS-3 repository make on the host rock? Geoscientific suitability indicators and criteria for siting and site evaluation

    Energy Technology Data Exchange (ETDEWEB)

    Andersson, Johan [Golder Grundteknik AB (Sweden); Stroem, Anders; Svemar, Christer [Swedish Nuclear Fuel and Waste Management Co., Stockholm (Sweden); Almen, Karl-Erik [KEA Geo-Konsult AB, Naessjoe (Sweden); Ericsson, Lars O. [Chalmers University of Technology, Goeteborg (Sweden)

    2000-04-01

    This report gives an account of what requirements are made on the rock, what conditions in the rock are advantageous and how the fulfilment of requirements and preferences is to be judged prior to the selection of sites for a site investigation and during a site investigation. The conclusions and results of the report are based on the knowledge and experience acquired by SKB over many years of research and development. The results, and particularly the stipulated criteria, apply to a repository for spent fuel of the KBS-3 type, i.e. a repository where the fuel is contained in copper canisters embedded in bentonite clay at a depth of 400 - 700 m in the Swedish crystalline basement. The report analyzes how the rock's different geological conditions, mechanical, thermal, hydrogeological, chemical and transport properties influence the functions of the deep repository, and whether it is possible to determine requirements and preferences regarding the influence of these properties. Where possible, these requirements or preferences have then been translated into requirements or preferences regarding the individual properties. Criteria are formulated that are based on the quantities that can be measured or estimated at the relevant stage of the investigation. The following requirements are made on the rock: The rock in the repository's deposition zone may not have any ore potential. Regional plastic shear zones shall be avoided if it cannot be demonstrated that the properties of the zone do not deviate from those of the rest of the rock. There may, however, be so-called 'tectonic lenses' near regional plastic shear zones where the bedrock is homogeneous and relatively unaffected. Deposition tunnels and deposition holes for canisters may not pass through or be positioned too close to major regional and major local fracture zones. Deposition holes may not intersect identified local minor fracture zones. The rock's strength, fracture geometry and

  3. Frictional sliding in layered rock model: Preliminary experiments. Yucca Mountain Site Characterization Project

    International Nuclear Information System (INIS)

    Perry, K.E. Jr.; Buescher, B.J.; Anderson, D.; Epstein, J.S.

    1995-09-01

    An important aspect of determining the suitability of Yucca Mountain as a possible nuclear waste repository requires understanding the mechanical behavior of jointed rock-masses. To this end we have studied the frictional sliding between simulated rock joints in the laboratory using the technique of phase shifting moire interferometry. The models were made from stacks of Lexan plates and contained a central hole to induce slip between the plates when the models were loaded in compression. These preliminary results confirm the feasibility of the approach and show a clear evolution of slip as function of load

  4. Documentation of Hanford Site independent review of the Hanford Waste Vitrification Plant Preliminary Safety Analysis Report

    International Nuclear Information System (INIS)

    Herborn, D.I.

    1991-10-01

    The requirements for Westinghouse Hanford independent review of the Preliminary Safety Analysis Report (PSAR) are contained in Section 1.0, Subsection 4.3 of WCH-CM-4-46. Specifically, this manual requires the following: (1) Formal functional reviews of the HWVP PSAR by the future operating organization (HWVP Operations), and the independent review organizations (HWVP and Environmental Safety Assurance, Environmental Assurance, and Quality Assurance); and (2) Review and approval of the HWVP PSAR by the Tank Waste Disposal (TWD) Subcouncil of the Safety and Environmental Advisory Council (SEAC), which provides independent advice to the Westinghouse Hanford President and executives on matters of safety and environmental protection. 7 refs

  5. Multi-criteria ranking and receptor modelling of airborne fine particles at three sites in the Pearl River Delta region of China.

    Science.gov (United States)

    Friend, Adrian J; Ayoko, Godwin A; Guo, Hai

    2011-01-15

    The multi-criteria decision making methods, Preference Ranking Organization METHods for Enrichment Evaluation (PROMETHEE) and Graphical Analysis for Interactive Assistance (GAIA), and the two-way Positive Matrix Factorization (PMF) receptor model were applied to airborne fine particle compositional data collected at three sites in Hong Kong during two monitoring campaigns held from November 2000 to October 2001 and November 2004 to October 2005. PROMETHEE/GAIA indicated that the three sites were worse during the later monitoring campaign, and that the order of the air quality at the sites during each campaign was: rural site>urban site>roadside site. The PMF analysis on the other hand, identified 6 common sources at all of the sites (diesel vehicle, fresh sea salt, secondary sulphate, soil, aged sea salt and oil combustion) which accounted for approximately 68.8±8.7% of the fine particle mass at the sites. In addition, road dust, gasoline vehicle, biomass burning, secondary nitrate, and metal processing were identified at some of the sites. Secondary sulphate was found to be the highest contributor to the fine particle mass at the rural and urban sites with vehicle emission as a high contributor to the roadside site. The PMF results are broadly similar to those obtained in a previous analysis by PCA/APCS. However, the PMF analysis resolved more factors at each site than the PCA/APCS. In addition, the study demonstrated that combined results from multi-criteria decision making analysis and receptor modelling can provide more detailed information that can be used to formulate the scientific basis for mitigating air pollution in the region. Copyright © 2010 Elsevier B.V. All rights reserved.

  6. Preliminary evaluation of licensing issues associated with U. S. -sited CANDU-PHW nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    van Erp, J B

    1977-12-01

    The principal safety-related characteristics of current CANDU-PHW power plants are described, and a distinction between those characteristics which are intrinsic to the CANDU-PHW system and those that are not is presented. An outline is given of the main features of the Canadian safety and licensing approach. Differences between the U.S. and Canadian approach to safety and licensing are discussed. Some of the main results of the safety analyses, routinely performed for CANDU-PHW reactors, are presented. U.S.-NRC General Design Criteria are evaluated as regards their applicability to CANDU-PHW reactors; vice-versa the CANDU-PHW reactor is evaluated with respect to its conformance to the U.S.-NRC General Design Criteria. A number of design modifications are proposed to be incorporated into the CANDU-PHW reactor in order to facilitate its introduction into the U.S.

  7. Technical procedures for the implementation of cultural resource site studies, Deaf Smith County, Texas: Preliminary draft

    International Nuclear Information System (INIS)

    1987-01-01

    Cultural resources at the Deaf Smith County site will be identified, evaluated and managed through the implementation of studies detailed in the Site Study Plan for Cultural Resources. This technical procedure outlines the conduct of pedestrian survey and the documentation of identified cultural resources. The purpose of the field surveys is to identify and document cultural resources in the areas that will be affected by site characterization activities and to record the environmental setting of identified cultural resources. Three pedestrian surveys will cover 100 percent of the on-site and off-site project areas. Survey 1 will provide coverage of the Repository Surface Facility (RSF) area, which includes the Exploratory Shaft Facility (ESF) and two linear engineering design borehole (EDBH) seismic survey corridors. Survey 2 will provide coverage of a 39 km 2 (15 mi 2 ) area that includes the 23 km 2 (9 mi 2 ) Deaf Smith County site plus a 0.4 to 0.8 kM (1/4 to 1/2 mi) border area but excludes the area covered by Survey 1. Survey 3 will cover offsite geotechnical test areas, such as the locations of playa boreholes, deep playa wells, hydrologic tests, site foundation borings, and their access routes. The purpose of site documentation or recording is to address the project information needs for land use permits and approvals, engineering design support, and cultural resource evaluation for National Register of Historic Places eligibility. Site documentation will consist of gathering sufficient data on identified resources to complete Texas Natural Resource Information System (TNRIS). 7 refs., 3 figs

  8. Site descriptions for preliminary radiological assessments of low-level waste repositories

    International Nuclear Information System (INIS)

    Burgess, W.E.; Jones, C.H.; Sumerling, T.J.; Ashton, J.

    1988-07-01

    The environmental contexts of four sites, previously under investigation by UK Nirex Ltd. as potential locations for low-level waste disposal facilities, are described. Information on geographical setting, climate, surface hydrology, land use, agriculture, fisheries, geology and hydrogeology is presented. The geological and hydrogeological data are interpreted with the support of deterministic modelling of groundwater conditions. The routes by which radionuclides may migrate from the site are identified and reduced to 1D statistical descriptions suitable for use in probabilistic risk assessments. Additional data required to improve the assessment of the performance of the site are identified. (author)

  9. Work plan for preliminary investigation of organic constituents in ground water at the New Rifle site, Rifle, Colorado. Revision 2

    International Nuclear Information System (INIS)

    1996-01-01

    A special study screening for Appendix 9 (40 CFR Part 264) analytes identified the New Rifle site as a target for additional screening for organic constituents. Because of this recommendation and the findings in a recent independent technical review, the US Department of Energy (DOE) has requested that the Technical Assistance Contractor (TAC) perform a preliminary investigation of the potential presence of organic compounds in the ground water at the New Rifle Uranium Mill Tailings Remedial Action (UMTRA) Project site, Rifle, Colorado. From 1958 to 1972, organic chemicals were used in large quantities during ore processing at the New Rifle site, and it is possible that some fraction was released to the environment. Therefore, the primary objective of this investigation is to determine whether organic chemicals used at the milling facility are present in the ground water. The purpose of this document is to describe the work that will be performed and the procedures that will be followed during installation of ground water well points at the New Rifle site. The selection of analytes and the procedures for collecting ground water samples for analysis of organic constituents are also described

  10. Criteria for the development and use of the methodology for environmentally-acceptable fossil energy site evaluation and selection. Volume 2. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Eckstein, L.; Northrop, G.; Scott, R.

    1980-02-01

    This report serves as a companion document to the report, Volume 1: Environmentally-Acceptable Fossil Energy Site Evaluation and Selection: Methodology and Users Guide, in which a methodology was developed which allows the siting of fossil fuel conversion facilities in areas with the least environmental impact. The methodology, known as SELECS (Site Evaluation for Energy Conversion Systems) does not replace a site specific environmental assessment, or an environmental impact statement (EIS), but does enhance the value of an EIS by thinning down the number of options to a manageable level, by doing this in an objective, open and selective manner, and by providing preliminary assessment and procedures which can be utilized during the research and writing of the actual impact statement.

  11. Preliminary radiological readings on the old uraniferous mining site of Rophin (Puy-de-Dome)

    International Nuclear Information System (INIS)

    Chareyron, Bruno

    2012-01-01

    After a presentation of the site, of the objectives, limits and methodology of the measurement campaign, this document reports and comments the radiological measurements performed by the CRIIRAD on the old uranium mining site of Rophin and its surroundings (gamma radiation). It comments measurements performed 1 meter above the ground and on soils, and anomalies clearly related to past industrial activities. It comments the results of a radiological analysis performed on released waters (uranium 238, radon 222), and on sediments and soils

  12. GIS-based multi-criteria site selection for zebra mussel cultivation: Addressing end-of-pipe remediation of a eutrophic coastal lagoon ecosystem.

    Science.gov (United States)

    Bagdanavičiūtė, Ingrida; Umgiesser, Georg; Vaičiūtė, Diana; Bresciani, Mariano; Kozlov, Igor; Zaiko, Anastasija

    2018-04-11

    Farming of shellfish and seaweeds is a tested tool for mitigating eutrophication consequences in coastal environments, however as many other marine economic activities it should be a subject of marine spatial planning for designating suitable sites. The present study proposes site selection framework for provisional zebra mussel farming in a eutrophic lagoon ecosystem, aimed primarily at remediation purposes. GIS-based multi-criteria approach was applied, combining data from empirical maps, numerical models and remote sensing to estimate suitability parameters. Site selection and prioritisation of suitable areas considered 15 environmental and socio-economic criteria, which contributed to 4 optimisation models (settlement, growth and survival of mussels, environmental and socio-economic) and 3 predefined scenarios representing provisional goals of mussel cultivation: spat production, biomass production and bioremediation. The relative importance of each criterion was assessed utilizing the Analytical Hierarchy Process. Site suitability index was calculated and the final result of the site selection analysis was summarized for 3 scenarios and overall suitability map. Four suitability classes (unsuitable, least, moderately and most suitable) were applied, and 3 most suitable zones for provisional zebra mussel cultivation with 12 candidate sites were selected accordingly. The integrated approach presented in this study can be adjusted for designating zebra mussel farming sites in other estuarine lagoon ecosystems, or cultivation of other mussel species for bioremediation purposes. The analytical framework and the workflow designed in this study are also adoptable for addressing other aquaculture-related spatial planning issues. Copyright © 2018 Elsevier B.V. All rights reserved.

  13. Preliminary - discrete fracture network modelling of tracer migration experiments at the SCV site

    International Nuclear Information System (INIS)

    Dershowitz, W.S.; Wallmann, P.; Geier, J.E.; Lee, G.

    1991-09-01

    This report describes a numerical modelling study of solute transport within the Site Characterization and Validation (SCV) block at the Stripa site. The study was carried out with the FracMan/MAFIC package, utilizing statistics from stages 3 and 4 of the Stripa phase 3 Site Characterization and Validation project. Simulations were carried out to calibrate fracture solute transport properties against observations in the first stage of saline injection radar experiments. These results were then used to predict the performance of planned tracer experiments, using both particle tracking network solute transport, and pathways analysis approaches. Simulations were also carried out to predict results of the second stage of saline injection radar experiments. (au) (34 refs.)

  14. Preliminary results on food consumption rates for off-site dose calculation of nuclear power plants

    International Nuclear Information System (INIS)

    Lee, Gab Bock; Chung, Yang Geun; Bang, Sun Young; Kang, Duk Won

    2005-01-01

    The Internal dose by food consumption mostly account for radiological dose of public around nuclear power plants(NPP). But, food consumption rate applied to off-site dose calculation in Korea which is the result of field investigation around Kori NPP by the KAERI in 1988. is not reflected of the latest dietary characteristics. The Ministry of Health and Welfare Affairs has investigated the food and nutrition of nations every 3 years based on the Law of National Health Improvement. To update the food consumption rates of the maximum individual, the analysis of the national food investigation results and field surveys around nuclear power plant sites have been carried out

  15. A Novel Approach to Site Selection: Collaborative Multi-Criteria Decision Making through Geo-Social Network (Case Study: Public Parking

    Directory of Open Access Journals (Sweden)

    Zeinab Neisani Samani

    2018-03-01

    Full Text Available There are many potential factors that are involved in the decision making process of site selection, which makes it a challenging issue. This paper addresses the collaborative decision making concept through a geo-social network to predict site selection for public parking in Tehran, Iran. The presented approach utilized the analytic hierarchy process (AHP as a multi-criteria decision method (MCDM for weighting the criteria, which was completed in two stages; once by 50 experts, and then by three different levels of users, including 50 experts, 25 urban managers, and 150 pubic citizens, with respect to the case study area. The fuzzy majority method aggregates the archived results of AHP to determine the preferred locations that are suitable for public parking. The proposed method was implemented using a telegram bot platform. Two main advantages of the collaborative decision making scenario for public urban site selection are the fair distribution of the selected locations and the high satisfaction of users, which increased from 65% to 85%. This study presents an application for site selection based on multi-criteria decision making in a geo-social network context.

  16. Regional hydrogeological simulations for Forsmark - numerical modelling using CONNECTFLOW. Preliminary site description Forsmark area - version 1.2

    Energy Technology Data Exchange (ETDEWEB)

    Hartley, Lee; Cox, Ian; Hunter, Fiona; Jackson, Peter; Joyce, Steve; Swift, Ben [Serco Assurance, Risley (United Kingdom); Gylling, Bjoern; Marsic, Niko [Kemakta Konsult AB, Stockholm (Sweden)

    2005-05-01

    The Swedish Nuclear Fuel and Waste Management Company (SKB) carries out site investigations in two different candidate areas in Sweden with the objective of describing the in-situ conditions for a bedrock repository for spent nuclear fuel. The site characterisation work is divided into two phases, an initial site investigation phase (IPLU) and a complete site investigation phase (KPLU). The results of IPLU are used as a basis for deciding on a subsequent KPLU phase. On the basis of the KPLU investigations a decision is made as to whether detailed characterisation will be performed (including sinking of a shaft). An integrated component in the site characterisation work is the development of site descriptive models. These comprise basic models in three dimensions with an accompanying text description. Central in the modelling work is the geological model, which provides the geometrical context in terms of a model of deformation zones and the rock mass between the zones. Using the geological and geometrical description models as a basis, descriptive models for other geo-disciplines (hydrogeology, hydro-geochemistry, rock mechanics, thermal properties and transport properties) will be developed. Great care is taken to arrive at a general consistency in the description of the various models and assessment of uncertainty and possible needs of alternative models. Here, a numerical model is developed on a regional-scale (hundreds of square kilometres) to understand the zone of influence for groundwater flow that affects the Forsmark area. Transport calculations are then performed by particle tracking from a local-scale release area (a few square kilometres) to identify potential discharge areas for the site and using greater grid resolution. The main objective of this study is to support the development of a preliminary Site Description of the Forsmark area on a regional-scale based on the available data of 30 June 2004 and the previous Site Description. A more specific

  17. Preliminary evaluation of the Accident Response Mobile Manipulation System for accident site salvage operations

    International Nuclear Information System (INIS)

    Trujillo, J.M.; Morse, W.D.; Jones, D.P.

    1994-01-01

    This paper describes and evaluates operational experiences with the Accident Response Mobile Manipulation System (ARMMS) during simulated accident site salvage operations which might involve nuclear weapons. The ARMMS is based upon a teleoperated mobility platform with two Schilling Titan 7F Manipulators

  18. Preliminary studies of the total cation exchange capacity of sediments from two North Atlantic study sites

    International Nuclear Information System (INIS)

    Hydes, D.J.; Hill, N.C.; Clarke, H.; Carpenter, M.S.N.

    1983-01-01

    Initially four different methods of measuring total cation exchange capacity were compared. There were two chemical methods (ammonium saturation with displacement into seawater, and barium saturation followed by replacement with magnesium) and two radiochemical methods (sodium-22 and caesium-134 saturation). The barium-magnesium and sodium-22 methods were then applied to sediment samples from Core D10164Pound1K from the Nares Fracture Valley, and Core D10554Pound11K from the eastern flank of the Great Meteor Rise. The material at site 10164 is a pelagic clay whereas at site 10554 it is carbonate ooze. The total cation exchange capacities (T.C.E.C.) of samples from the two sites are similar when measured by the sodium-22 method, the mean for Core 10164 was 21.7 meq/100g and 24.4 meq/100g for Core 10554. However for Core 10554 the barium-magnesium method gives a mean of 42.8 meq/100g. The difference in T.C.E.C. measured by the two methods appears to be due to the high calcite content of core 10554 sediment. Measured exchange capacities are lower than in coastal sediments. In deep sea sediments organic matter either makes a very small contribution to the T.C.E.C. (core 10164) or actually blocks exchange sites (Core 10554). Amorphous oxides of iron and manganese contribute between 20 and 50% of the T.C.E.C. (author)

  19. Sludge treatment facility preliminary siting study for the sludge treatment project (A-13B)

    International Nuclear Information System (INIS)

    WESTRA, A.G.

    1999-01-01

    This study evaluates various sites in the 100 K area and 200 areas of Hanford for locating a treatment facility for sludge from the K Basins. Both existing facilities and a new standalone facility were evaluated. A standalone facility adjacent to the AW Tank Farm in the 200 East area of Hanford is recommended as the best location for a sludge treatment facility

  20. Occupational health and safety in the Moroccan construction sites: preliminary diagnosis

    Science.gov (United States)

    Tarik, Bakeli; Adil, Hafidi Alaoui

    2018-05-01

    Managing occupational health and safety on Moroccan construction sector represents the first step for projects' success. In fact, by avoiding accidents, all the related direct and indirect costs and delays can be prevented. That leads to an important question always asked by any project manager: what are the factors responsible for accidents? How can they be avoided? Through this research, the aim is to go through these questions, to contribute in occupational health and safety principles understanding, to identify construction accidentology and risk management opportunities and to approach the case of Moroccan construction sites by an accurate diagnosis. The approach is to make researchers, managers, stakeholders and deciders aware about the criticality of construction sites health and safety situation. And, to do the first step for a scientific research project in relation with health and safety in the Moroccan construction sector. For this, the paper will study the related state of art namely about construction sites accidents causation, and will focus on Reason's `Swiss cheese' model and its utilization for Moroccan construction sites health and safety diagnosis. The research will end with an estimation of an accidents fatality rate in the Moroccan construction sector and a benchmarking with the international rates. Finally, conclusions will be presented about the necessity of Occupational Health and Safety Management System (OHSMS) implementation, which shall cover all risk levels, and insure, at the same time, that the necessary defenses against accidents are on place.

  1. Preliminary thermal/thermomechanical analyses of the Site Characterization Plan's Conceptual Design for a repository containing horizontally emplaced waste packages at the Deaf Smith County site

    International Nuclear Information System (INIS)

    Ghantous, N.Y.; Raines, G.E.

    1987-10-01

    This report presents thermal/thermomechanical analyses of the Site Characterization Plan Conceptual Design for horizontal package emplacement at the Deaf Smith County site, Texas. The repository was divided into three geometric regions. Then two-dimensional finite-element models were set up to approximate the three-dimensional nature of each region. Thermal and quasistatic thermomechanical finite-element analyses were performed to evaluate the thermal/thermomechanical responses of the three regions. The exponential-time creep law was used to represent the creep behavior of salt rock. The repository design was evaluated by comparing the thermal/thermomechanical responses obtained for the three regions with interim performance constraints. The preliminary results show that all the performance constraints are met except for those of the waste package. The following factors were considered in interpreting these results: (1) the qualitative description of the analytical responses; (2) the limitations of the analyses; and (3) either the conclusions based on overall evaluation of limitations and analytical results or the conclusions based on the fact that the repository design may be evaluated only after further analyses. Furthermore, a parametric analysis was performed to estimate the effect of material parameters on the predicted thermal/thermomechanical response. 23 refs., 34 figs., 9 tabs

  2. Preliminary analysis of the cost and risk of transporting nuclear waste to potential candidate commercial repository sites

    International Nuclear Information System (INIS)

    Wilmot, E.L.; Madsen, M.M.; Cashwell, J.W.; Joy, D.S.

    1983-06-01

    This report documents preliminary cost and risk analyses that were performed in support of the Nuclear Waste Terminal Storage (NWTS) program. The analyses compare the costs and hazards of transporting wastes to each of five regions that contain potential candidate nuclear waste repository sites being considered by the NWTS program. These regions are: the Gulf Interior Region, the Permian Basin, the Paradox Basin, Yucca Mountain, and Hanford. Two fuel-cycle scenarios were analyzed: once-through and reprocessing. Transportation was assumed to be either entirely by truck or entirely by rail for each of the scenarios. The results from the risk analyses include those attributable to nonradiological causes and those attributable to the radioactive character of the wastes being transported. 17 references

  3. On-site transportation and handling of uranium-233 special nuclear material: Preliminary hazards and accident analysis. Final

    International Nuclear Information System (INIS)

    Solack, T.; West, D.; Ullman, D.; Coppock, G.; Cox, C.

    1995-01-01

    U-233 Special Nuclear Material (SNM) currently stored at the T-Building Storage Areas A and B must be transported to the SW/R Tritium Complex for repackaging. This SNM is in the form of oxide powder contained in glass jars which in turn are contained in heat sealed double polyethylene bags. These doubled-bagged glass jars have been primarily stored in structural steel casks and birdcages for approximately 20 years. The three casks, eight birdcages, and one pail/pressure vessel will be loaded onto a transport truck and moved over an eight day period. The Preliminary Hazards and Accident Analysis for the on-site transportation and handling of Uranium-233 Special Nuclear Material, documented herein, was performed in accordance with the format and content guidance of DOE-STD-3009-94, Preparation Guide for US Department of Energy Nonreactor Nuclear Facility Safety Analysis Reports, dated July 1994, specifically Chapter Three, Hazard and Accident Analysis. The Preliminary Hazards Analysis involved detailed walkdowns of all areas of the U-233 SNM movement route, including the T-Building Storage Area A and B, T-Building truck tunnel, and the roadway route. Extensive discussions were held with operations personnel from the Nuclear Material Control Group, Nuclear Materials Accountability Group, EG and G Mound Security and the Material Handling Systems Transportation Group. Existing documentation related to the on-site transportation of hazardous materials, T-Building and SW/R Tritium Complex SARs, and emergency preparedness/response documentation were also reviewed and analyzed to identify and develop the complete spectrum of energy source hazards

  4. Hydrogeological DFN modelling using structural and hydraulic data from KLX04. Preliminary site description Laxemar subarea - version 1.2

    Energy Technology Data Exchange (ETDEWEB)

    Follin, Sven [SF GeoLogic AB, Taeby (Sweden); Stigsson, Martin [Swedish Nuclear Fuel and Waste Management Co., Stockholm (Sweden); Svensson, Urban [Computer-aided Fluid Engineering AB, Norrkoeping (Sweden)

    2006-04-15

    SKB is conducting site investigations for a high-level nuclear waste repository in fractured crystalline rocks at two coastal areas in Sweden. The two candidate areas are named Forsmark and Simpevarp. The site characterisation work is divided into two phases, an initial site investigation phase (ISI) and a complete site investigation phase (CSI). The results of the ISI phase are used as a basis for deciding on the subsequent CSI phase. On the basis of the CSI investigations a decision is made as to whether detailed characterisation will be performed (including sinking of a shaft). An integrated component in the site characterisation work is the development of site descriptive models. These comprise basic models in three dimensions with an accompanying text description. Central in the modelling work is the geological model which provides the geometrical context in terms of a model of deformation zones and the less fractured rock mass between the zones. Using the geological and geometrical description models as a basis, descriptive models for other disciplines (surface ecosystems, hydrogeology, hydrogeochemistry, rock mechanics, thermal properties and transport properties) will be developed. Great care is taken to arrive at a general consistency in the description of the various models and assessment of uncertainty and possible needs of alternative models. The main objective of this study is to support the development of a hydrogeological DFN model (Discrete Fracture Network) for the Preliminary Site Description of the Laxemar area on a regional-scale (SDM version L1.2). A more specific objective of this study is to assess the propagation of uncertainties in the geological DFN modelling reported for L1.2 into the groundwater flow modelling. An improved understanding is necessary in order to gain credibility for the Site Description in general and the hydrogeological description in particular. The latter will serve as a basis for describing the present

  5. Hydrogeological DFN modelling using structural and hydraulic data from KLX04. Preliminary site description Laxemar subarea - version 1.2

    International Nuclear Information System (INIS)

    Follin, Sven; Stigsson, Martin; Svensson, Urban

    2006-04-01

    SKB is conducting site investigations for a high-level nuclear waste repository in fractured crystalline rocks at two coastal areas in Sweden. The two candidate areas are named Forsmark and Simpevarp. The site characterisation work is divided into two phases, an initial site investigation phase (ISI) and a complete site investigation phase (CSI). The results of the ISI phase are used as a basis for deciding on the subsequent CSI phase. On the basis of the CSI investigations a decision is made as to whether detailed characterisation will be performed (including sinking of a shaft). An integrated component in the site characterisation work is the development of site descriptive models. These comprise basic models in three dimensions with an accompanying text description. Central in the modelling work is the geological model which provides the geometrical context in terms of a model of deformation zones and the less fractured rock mass between the zones. Using the geological and geometrical description models as a basis, descriptive models for other disciplines (surface ecosystems, hydrogeology, hydrogeochemistry, rock mechanics, thermal properties and transport properties) will be developed. Great care is taken to arrive at a general consistency in the description of the various models and assessment of uncertainty and possible needs of alternative models. The main objective of this study is to support the development of a hydrogeological DFN model (Discrete Fracture Network) for the Preliminary Site Description of the Laxemar area on a regional-scale (SDM version L1.2). A more specific objective of this study is to assess the propagation of uncertainties in the geological DFN modelling reported for L1.2 into the groundwater flow modelling. An improved understanding is necessary in order to gain credibility for the Site Description in general and the hydrogeological description in particular. The latter will serve as a basis for describing the present

  6. WSSRAP [Weldon Spring Site Remedial Action Project] quarry preliminary engineering report

    International Nuclear Information System (INIS)

    1990-01-01

    The removal, transport, and temporary storage of radiologically and chemically contaminated bulk waste from the Weldon Spring Quarry will be accomplished by dividing the work into three subcontract packages. The major portion of the work will come under the bulk waste excavation package; construction of a temporary storage area (TSA) at the Weldon Spring Chemical Plant and of a haul road between the quarry and the TSA comprise the other two packages. Cost estimates to complete the removal range from $5 million to $9.4 million due to a high degree of uncertainty regarding both the productivity of the excavating equipment and the effectiveness of planned dewatering efforts. Quarry wastes will be substantially dewatered and the water treated before discharge. Waste will be excavated in three phases, using conventional construction equipment, with preliminary sorting of waste at the quarry before transport to the TSA. Special attention will be given to controlling the spread of contamination by careful monitoring and control of surface and groundwater drainage and of particulate and radiological contamination of the air. 6 refs., 21 figs., 8 tabs

  7. Preliminary analysis of some waters from the confined aquifers underlying the Hanford site

    International Nuclear Information System (INIS)

    Deju, R.A.

    1978-09-01

    This report presents results of analyses available at this time from waters from some wells sampled in or near the Hanford Site. The analyses of these wells were done for various purposes and are consolidated to help define the nature of the waters found within the Columbia Plateau basaltic sequence. Results of the analyses show the waters from the unconfined aquifers underlying the Hanford Site are characterized by a high calcium--magnesium content. These waters can be described as calcium--magnesium--bicarbonate-type. Waters from deeper basaltic confined aquifers are primarily of the sodium bicarbonate type. Two waters sampled from the Grande Ronde Formation from Rattlesnake Hills Exploratory Well Number 1 are slightly different and can be described as sodium--calcium--bicarbonate--sulfate--chloride-type. Age-dating results for these water samples lead to the conclusions that waters from the confined aquifers were entrapped 15,000 to 23,000 years ago

  8. Preliminary site description: Groundwater flow simulations. Simpevarp area (version 1.1) modelled with CONNECTFLOW

    International Nuclear Information System (INIS)

    Hartley, Lee; Worth, David; Gylling, Bjoern; Marsic, Niko; Holmen, Johan

    2004-08-01

    The main objective of this study is to assess the role of known and unknown hydrogeological conditions for the present-day distribution of saline groundwater at the Simpevarp and Laxemar sites. An improved understanding of the paleo-hydrogeology is necessary in order to gain credibility for the Site Descriptive Model in general and the Site Hydrogeological Description in particular. This is to serve as a basis for describing the present hydrogeological conditions as well as predictions of future hydrogeological conditions. This objective implies a testing of: geometrical alternatives in the structural geology and bedrock fracturing, variants in the initial and boundary conditions, and parameter uncertainties (i.e. uncertainties in the hydraulic property assignment). This testing is necessary in order to evaluate the impact on the groundwater flow field of the specified components and to promote proposals of further investigations of the hydrogeological conditions at the site. The general methodology for modelling transient salt transport and groundwater flow using CONNECTFLOW that was developed for Forsmark has been applied successfully also for Simpevarp. Because of time constraints only a key set of variants were performed that focussed on the influences of DFN model parameters, the kinematic porosity, and the initial condition. Salinity data in deep boreholes available at the time of the project was too limited to allow a good calibration exercise. However, the model predictions are compared with the available data from KLX01 and KLX02 below. Once more salinity data is available it may be possible to draw more definite conclusions based on the differences between variants. At the moment though the differences should just be used understand the sensitivity of the models to various input parameters

  9. Preliminary experiments for measuring Kd values for cesium and strontium. To be used in site evaluations

    International Nuclear Information System (INIS)

    Benischek, I.; Hess, V.; Metzker, E.

    1992-03-01

    In an underground dump not only technolgical barriers but also the natural geological formations are efficient in withholding radionuclides. Sites are to be chosen where the rocks have good sorption properties and where transportation due to various chemical interactions should be minimal. Minerals obtained from deep drilling - granodiorite, mylonite and granit gneis - were investigated. The liquid phase (cement leaching water) contained different amounts of cesium 137 and strontium 85. Details of the experiments and results are given

  10. The preliminary study on the alluvial stratigraphy of Peinan archaeological site, Taiwan

    Science.gov (United States)

    Yang, Hsiaochin; Chen, Wenshan; Yeh, Changkeng

    2015-04-01

    Many of the activities of prehistoric people who lived in Taiwan were concentrated around river terrace environments and seldom in alluvial environments which are resulting from the rapid tectonic uplift and high erosion rate of the late Cenozoic mountain belt. However, the Peinan archaeological site, one of the most important Neolithic sites in Taiwan because of the great amount of slate slab coffins and nephrite artifacts unearthed, is located at the bottom of Peinan Hill which is formed by the activity of Lichi and Luyeh Faults. According to the radioactive carbon dating results, the Peinan alluvial fan used as cemetery was lasted over 3,700 years (5700-2000 yr BP) but the related cultural formation was only lasted 400 years (3500-3100 yr BP). What have happened to the prehistoric people? As the stratigraphic record allows archaeologists to ascertain the effects of geological processes on the preservation of the archaeological record, determining which parts of the archaeological records are absent, which have potentially been preserved, and how fragmentary are the preserved portions of the records. The limitations that geologic processes impose on the archaeological record must be recognized and understood before meaningful interpretations of prehistory can be made. Therefore, the reconstruction of the landscape and stratigraphic records in archaeological site not only provides the paleo-environmental context but also helps to explain changes that occurred to human cultures over time.

  11. Preliminary investigation Area 12 fleet operations steam cleaning discharge area Nevada Test Site

    International Nuclear Information System (INIS)

    1996-07-01

    This report documents the characterization activities and findings of a former steam cleaning discharge area at the Nevada Test Site. The former steam cleaning site is located in Area 12 east of Fleet Operations Building 12-16. The characterization project was completed as a required condition of the ''Temporary Water Pollution Control Permit for the Discharge From Fleet Operations Steam Cleaning Facility'' issued by the Nevada Division of Environmental Protection. The project objective was to collect shallow soil samples in eight locations in the former surface discharge area. Based upon field observations, twelve locations were sampled on September 6, 1995 to better define the area of potential impact. Samples were collected from the surface to a depth of approximately 0.3 meters (one foot) below land surface. Discoloration of the surface soil was observed in the area of the discharge pipe and in localized areas in the natural drainage channel. The discoloration appeared to be consistent with the topographically low areas of the site. Hydrocarbon odors were noted in the areas of discoloration only. Samples collected were analyzed for bulk asbestos, Toxicity Characteristic Leaching Procedure (TCLP) metals, total petroleum hydrocarbons (TPHs), volatile organic compounds (VOCs), semi-volatile organic compounds (Semi-VOCs), and gamma scan

  12. Preliminary data report of investigations conducted at the Salmon Site, Lamar County, Mississippi

    International Nuclear Information System (INIS)

    1994-04-01

    The US Department of Energy (DOE) conducted ecological studies at the Salmon Site (SS), Lamar County, Mississippi, from the middle of June 1992 to the end of April 1993. The studies are part of the Remedial Investigation and Feasibility Study (RI/FS) being conducted by the DOE. The RI/FS is the methodology under the Comprehensive Environmental Response, Compensation, and Liability Act of 1980, as amended by the Superfund Amendments and Reauthorization Act of 1986 (CERCLA/SARA) for evaluating hazardous waste sites on the National Priorities List (NPL). The Salmon Site is not listed on the NPL but DOE has voluntarily elected to conduct the evaluation of the SS in accordance with CERCLA/SARA. As part of the remedial investigation, baseline human health and ecological risk assessments will be conducted. These baseline risk assessments will evaluate the potential impact on human health and the environment if remedial actions are not conducted, identify locations where additional information needs to be collected, help determine whether remedial actions are necessary, and provide justification for performing remedial actions. This report describes the sampling activities conducted between February and April 1993 to aid in evaluating the possible environmental impacts at the SS tailored to the specific circumstances and conditions found there. The initial investigations included identification of the flora and fauna in and around the SS, with particular emphasis on identifying sensitive environments, endangered species and their habitats, and those species consumed by humans or found in human food chains

  13. Preliminary characterization of ceramics from the Lago Grande archaeological site in the central Amazon by INAA

    International Nuclear Information System (INIS)

    Hazenfratz, Roberto; Munita, Casimiro S.; Neves, Eduardo G.; Oliveira, Paulo M.S.; Toyota, Rosimeiri G.

    2009-01-01

    The macroscopic characteristics of archaeological ceramics, such as the surface decoration and shape, are used as cultural and chronological indicators of ancient people. The combination of stylistic-typological studies with archaeometric analysis, as provenance studies, has been considered of great importance in Archaeology. The purpose of this paper is to contribute to the understanding of the pre-colonial Amazonian occupations. Inside this context, fifty ceramic fragments from the Lago Grande archaeological site were analyzed by INAA in order to characterize its elemental composition. The results were treated with multivariate statistics: Cluster, Principal Components and Discriminant Analysis. The results obtained by these three methods were compared in an effort to achieve some correlation with the archaeological context. It was stated the existence of two different groups of artifacts. They probably regard to the main ceramic phases found in the site excavation: Paredao and Manacapuru. Once confirmed by other archaeological analyses, these results could corroborate an exchange net among the former inhabitants of Lago Grande and other sites in the neighborhood. (author)

  14. Bedrock transport properties. Preliminary site description Simpevarp subarea - version 1.2

    Energy Technology Data Exchange (ETDEWEB)

    Byegaard, Johan; Gustavsson, Eva [Geosigma AB, Uppsala (Sweden); Tullborg, Eva-Lena [Terralogica AB, Graabo (Sweden); Berglund, Sten [Swedish Nuclear Fuel and Waste Management Co., Stockholm (Sweden)

    2005-06-01

    This report presents the site descriptive model of transport properties developed as a part of the Simpevarp 1.2 site description. The main parameters included in the model, referred to as retardation parameters, are the matrix porosity and diffusivity, and the matrix sorption coefficient K{sub d}. The model is based on the presently available site investigation data, mainly obtained from laboratory investigations of core samples from boreholes within the Simpevarp subarea, and on data from previous studies at the Aespoe Hard Rock Laboratory (Aespoe HRL). The modelling is a first attempt, based on limited data, to obtain a description of the retardation parameters. Further refinement of the model is foreseen when more data becomes available for future versions of the Simpevarp site description. The modelling work included descriptions of rock mass geology, the fractures and deformation zones, the hydrogeochemistry and also the available results from the site specific porosity, sorption and diffusivity measurements. The description of the transport related aspects of the data and models presented by other modelling disciplines is an important part of the transport description. In accordance with the strategy for the modelling of transport properties, the results are presented as a 'retardation model', in which a summary of the transport data for the different geological compartments is given. Concerning the major rock types, Aevroe granite, quartz monzodiorite and fine-grained dioritoid are identified as the rock types dominating the main rock domains identified and described in the site descriptive model of the bedrock geology. However, relatively large parts of the rock consist of altered rock and the open fracture frequency appears to be correlated to the altered/oxidised parts of the rock. This implies that transport in open fractures to a large extent takes place in the altered parts of the rock. For the fracture mineralogy, it is found that the

  15. Structural acceptance criteria for the evaulation of existing double-shell waste storage tanks located at the Hanford site, Richland, Washington

    International Nuclear Information System (INIS)

    Julyk, L.J.; Day, A.D.; Dyrness, A.D.; Moore, C.J.; Peterson, W.S.; Scott, M.A.; Shrivastava, H.P.; Sholman, J.S.; Watts, T.N.

    1995-09-01

    The structural acceptance criteria contained herein for the evaluation of existing underground double-shell waste storage tanks located at the Hanford Site is part of the Life Management/Aging Management Program of the Tank Waste Remediation System. The purpose of the overall life management program is to ensure that confinement of the waste is maintained over the required service life of the tanks. Characterization of the present condition of the tanks, understanding and characterization of potential degradation mechanisms, and development of tank structural acceptance criteria based on previous service and projected use are prerequisites to assessing tank integrity, to projecting the length of tank service, and to developing and applying prudent fixes or repairs. The criteria provided herein summarize the requirements for the analysis and structural qualification of the existing double-shell tanks for continued operation. Code reconciliation issues and material degradation under aging conditions are addressed. Although the criteria were developed for double-shell tanks, many of the provisions are equally applicable to single-shell tanks. However, the criteria do not apply to the evaluation of tank appurtenances and buried piping

  16. Significance of radon exposures in developing cleanup criteria for radium-contaminated soil at the Weldon Spring Site

    International Nuclear Information System (INIS)

    Blunt, D.L.; Peterson, J.M.; Hillman, D.J.

    1993-10-01

    The Weldon Spring site, located in St. Charles County, Missouri, is included on the National Priorities List (NPL) of the US Environmental Protection Agency (EPA), and the US Department of Energy (DOE) is currently conducting cleanup activities at the site. This paper discusses the significance of radon exposures that may result from radium-contaminated soil and the approach currently being taken at the Weldon Spring site to address this issue

  17. Hydrogeochemical evaluation. Preliminary site description Laxemar subarea - version 1.2

    International Nuclear Information System (INIS)

    Laaksoharju, Marcus

    2006-04-01

    Siting studies for SKB's programme of deep geological disposal of nuclear fuel waste currently involves the investigation of two locations, Simpevarp and Forsmark, on the eastern coast of Sweden to determine their geological, hydrogeochemical and hydrogeological characteristics. Present work completed has resulted in Model version 1.2 for Laxemar subarea which represents the third evaluation of the available Simpevarp area groundwater analytical data collected up to November, 2004. Model version 1.2 focusses on improving the methodology and tools used for evaluating the hydrochemistry combined with a sensitivity and uncertainty analysis of the available data. The major goal has been to consolidate groundwater geochemical understanding and the models used at the site. The complex groundwater evolution and patterns at Simpevarp are a result of many factors such as: a) the present-day topography and proximity to the Baltic Sea, b) past changes in hydrogeology related to glaciation/deglaciation, land uplift and repeated marine/lake water regressions/transgressions, and c) organic or inorganic alteration of the groundwater composition caused by microbial processes or water/rock interactions. The sampled groundwaters reflect to various degrees processes relating to modern or ancient water/rock interactions and mixing. The groundwater flow regimes at Laxemar/Simpevarp are considered local and extend down to depths of around 600-1,000 m depending on local topography. Close to the Baltic Sea coastline where topographical variation is small, groundwater flow penetration to depth will subsequently be less marked. In contrast, the Laxemar subarea is characterised by higher topography resulting in a much more dynamic groundwater circulation which appears to extend to 1,000 m depth in the vicinity of borehole KLX02. The marked differences in the groundwater flow regimes between the Laxemar and Simpevarp are reflected in the groundwater chemistry where four major hydrochemical

  18. Hydrogeochemical evaluation. Preliminary site description Laxemar subarea - version 1.2

    Energy Technology Data Exchange (ETDEWEB)

    Laaksoharju, Marcus (ed.) [Geopoint AB, Stockholm (Sweden)

    2006-04-15

    Siting studies for SKB's programme of deep geological disposal of nuclear fuel waste currently involves the investigation of two locations, Simpevarp and Forsmark, on the eastern coast of Sweden to determine their geological, hydrogeochemical and hydrogeological characteristics. Present work completed has resulted in Model version 1.2 for Laxemar subarea which represents the third evaluation of the available Simpevarp area groundwater analytical data collected up to November, 2004. Model version 1.2 focusses on improving the methodology and tools used for evaluating the hydrochemistry combined with a sensitivity and uncertainty analysis of the available data. The major goal has been to consolidate groundwater geochemical understanding and the models used at the site. The complex groundwater evolution and patterns at Simpevarp are a result of many factors such as: a) the present-day topography and proximity to the Baltic Sea, b) past changes in hydrogeology related to glaciation/deglaciation, land uplift and repeated marine/lake water regressions/transgressions, and c) organic or inorganic alteration of the groundwater composition caused by microbial processes or water/rock interactions. The sampled groundwaters reflect to various degrees processes relating to modern or ancient water/rock interactions and mixing. The groundwater flow regimes at Laxemar/Simpevarp are considered local and extend down to depths of around 600-1,000 m depending on local topography. Close to the Baltic Sea coastline where topographical variation is small, groundwater flow penetration to depth will subsequently be less marked. In contrast, the Laxemar subarea is characterised by higher topography resulting in a much more dynamic groundwater circulation which appears to extend to 1,000 m depth in the vicinity of borehole KLX02. The marked differences in the groundwater flow regimes between the Laxemar and Simpevarp are reflected in the groundwater chemistry where four major

  19. Description of surface systems. Preliminary site description Simpevarp sub area - Version 1.2

    Energy Technology Data Exchange (ETDEWEB)

    Lindborg, Tobias [ed.

    2005-03-01

    Swedish Nuclear Fuel and Waste Management Co is currently conducting site characterisation in the Simpevarp area. The area is divided into two subareas, the Simpevarp and the Laxemar subarea. The two subareas are surrounded by a common regional model area, the Simpevarp area. This report describes both the regional area and the subareas. This report is an interim version (model version 1.2) of the description of the surface systems at the Simpevarp area, and should be seen as a background report to the site description of the Simpevarp area, version 1.2, SKB-R--05-08. The basis for this description is quality-assured field data available in the SKB SICADA and GIS databases, together with generic data from the literature. The Surface system, here defined as everything above the bedrock, comprises a number of separate disciplines (e.g. hydrology, geology, topography, oceanography and ecology). Each discipline has developed descriptions and models for a number of properties that together represent the site description. The current methodology for developing the surface system description and the integration to ecosystem models is documented in a methodology strategy report SKB-R--03-06. The procedures and guidelines given in that report were followed in this report. Compared with version 1.1 of the surface system description SKB-R--04-25, this report presents considerable additional features, especially in the ecosystem description (Chapter 4) and in the description of the surface hydrology (Section 3.4). A first attempt has also been made to connect the flow of matter (carbon) between the different ecosystems into an overall ecosystem model at a landscape level. A summarised version of this report is also presented in SKB-R--05-08 together with geological-, hydrogeological-, transport properties-, thermal properties-, rock mechanics- and hydrogeochemical descriptions.

  20. Ponded infiltration tests at the Box Canyon site: data report and preliminary analysis

    International Nuclear Information System (INIS)

    Cook, Paul; Faybishenko, Boris; Freifeld, Barry; Jacobsen, Janet; Lee, Ki Ha; Salve, Rohit; Zawislanski, Peter

    1998-01-01

    We discuss the design and present the main results of a two-week ponded infiltration test conducted in 1996 at the Box Canyon site near the Idaho National Engineering and Environmental Laboratory. To investigate liquid flow and chemical transport in fractured basalt, the following types of instruments were installed in boreholes: tensiometers, suction lysimeters, thermistors, time domain reflectrometry probes, and electrical resisitivity probes. These probes were installed using an innovative technology of borehole instrumentation and completion using polyurethane foam injection. The probes were attached to plastic packers that were inflated using the polyurethane foam, and then the space between packers was back-filled with the foam in order to ensure the isolation of the instruments at different depths. Polyurethane foam showed great promise in enabling rapid, cost-effective installation of sensors and probes in fractured rock. A ponded infiltration test was conducted from 8/27/96 to 9/9/96, by maintaining water to an average depth of 23 cm in a rectangular infiltration pond. Within the 7 x 8 m pond, nine local infiltrometers (0.25 m diameter) were-installed to determine local values of the water flux. A slug of conservative tracer (KM) was added to the pond on 9/2/96, yielding a tracer concentration in the pond of approximately 3 g/L. The water supply to the pond was halted for two days so that the tracer concentration in the pond water would remain essentially constant. Thereafter, the water supply was re-established to maintain a constant water level. Installation procedures and measurement results for each type of probe are presented, along with a description of the data acquisition system. The attachments include a description of the calibration and testing of instrumentation. The data files can be found at the FTP site zenitMnel/ or the Web site http://www- esd.lbl.gov/ERT/inel/inel.htrnl

  1. Preliminary hydrogeologic investigation of the Maxey Flats radioactive waste burial site, Fleming County, Kentucky

    Science.gov (United States)

    Zehner, Harold H.

    1979-01-01

    Burial trenches at the Maxey Flats radioactive waste burial site , Fleming County, Ky., cover an area of about 0.03 square mile, and are located on a plateau, about 300 to 400 feet above surrounding valleys. Although surface-water characteristics are known, little information is available regarding the ground-water hydrology of the Maxey Flats area. If transport of radionuclides from the burial site were to occur, water would probably be the principal mechanism of transport by natural means. Most base flow in streams around the burial site is from valley alluvium, and from the mantle of regolith, colluvium, and soil partially covering adjacent hills. Very little base flow is due to ground-water flow from bedrock. Most water in springs is from the mantle, rather than from bedrock. Rock units underlying the Maxey Flats area are, in descending order, the Nancy and Farmers Members of the Borden Formation, Sunbury, Bedford, and Ohio Shales, and upper part of the Crab Orchard Formation. These units are mostly shales, except for the Farmers Member, which is mostly sandstone. Total thickness of the rocks is about 320 feet. All radioactive wastes are buried in the Nancy Member. Most ground-water movement in bedrock probably occurs in fractures. The ground-water system at Maxey Flats is probably unconfined, and recharge occurs by (a) infiltration of rainfall into the mantle, and (b) vertical, unsaturated flow from the saturated regolith on hilltops to saturated zones in the Farmers Member and Ohio Shale. Data are insufficient to determine if saturated zones exist in other rock units. The upper part of the Crab Orchard Formation is probably a hydrologic boundary, with little ground-water flow through the formation. (USGS)

  2. Description of surface systems. Preliminary site description Simpevarp sub area - Version 1.2

    International Nuclear Information System (INIS)

    Lindborg, Tobias

    2005-03-01

    Swedish Nuclear Fuel and Waste Management Co is currently conducting site characterisation in the Simpevarp area. The area is divided into two subareas, the Simpevarp and the Laxemar subarea. The two subareas are surrounded by a common regional model area, the Simpevarp area. This report describes both the regional area and the subareas. This report is an interim version (model version 1.2) of the description of the surface systems at the Simpevarp area, and should be seen as a background report to the site description of the Simpevarp area, version 1.2, SKB-R--05-08. The basis for this description is quality-assured field data available in the SKB SICADA and GIS databases, together with generic data from the literature. The Surface system, here defined as everything above the bedrock, comprises a number of separate disciplines (e.g. hydrology, geology, topography, oceanography and ecology). Each discipline has developed descriptions and models for a number of properties that together represent the site description. The current methodology for developing the surface system description and the integration to ecosystem models is documented in a methodology strategy report SKB-R--03-06. The procedures and guidelines given in that report were followed in this report. Compared with version 1.1 of the surface system description SKB-R--04-25, this report presents considerable additional features, especially in the ecosystem description (Chapter 4) and in the description of the surface hydrology (Section 3.4). A first attempt has also been made to connect the flow of matter (carbon) between the different ecosystems into an overall ecosystem model at a landscape level. A summarised version of this report is also presented in SKB-R--05-08 together with geological-, hydrogeological-, transport properties-, thermal properties-, rock mechanics- and hydrogeochemical descriptions

  3. Crystallization and preliminary crystallographic studies of human septin 1 with site-directed mutations

    International Nuclear Information System (INIS)

    Hu, Hao; Yu, Wen-bo; Li, Shu-xing; Ding, Xiang-ming; Yu, Long; Bi, Ru-Chang

    2006-01-01

    The homogeneity of septin 1 has been improved by site-directed mutation of serine residues and only a small alteration in the secondary structure is observed to arise from the mutations. Crystals of the septin 1 mutant were grown and diffraction data were collected to 2.5 Å resolution. Septin 1 is a member of an evolutionarily conserved family of GTP-binding and filament-forming proteins named septins, which function in diverse processes including cytokinasis, vesicle trafficking, apoptosis, remodelling of the cytoskeleton, infection, neurodegeneration and neoplasia. Human septin 1 has been expressed and purified, but suffers from severe aggregation. Studies have shown that septin 1 with site-directed mutations of five serine residues (Ser19, Ser206, Ser307, Ser312 and Ser315) has a much lower degree of aggregation and better structural homogeneity and that the mutations cause only slight perturbations in the secondary structure of septin 1. This septin 1 mutant was crystallized and diffraction data were collected to 2.5 Å resolution. The space group is P422, with unit-cell parameters a = b = 106.028, c = 137.852 Å

  4. Crystallization and preliminary crystallographic studies of human septin 1 with site-directed mutations

    Energy Technology Data Exchange (ETDEWEB)

    Hu, Hao [Institute of Biophysics, Chinese Academy of Sciences, Beijing 100101 (China); Yu, Wen-bo [State Key Laboratory of Genetic Engineering, Institute of Genetics, School of Life Sciences, Fudan University, Shanghai 200433 (China); Li, Shu-xing [Institute of Biophysics, Chinese Academy of Sciences, Beijing 100101 (China); Ding, Xiang-ming; Yu, Long [State Key Laboratory of Genetic Engineering, Institute of Genetics, School of Life Sciences, Fudan University, Shanghai 200433 (China); Bi, Ru-Chang [Institute of Biophysics, Chinese Academy of Sciences, Beijing 100101 (China)

    2006-02-01

    The homogeneity of septin 1 has been improved by site-directed mutation of serine residues and only a small alteration in the secondary structure is observed to arise from the mutations. Crystals of the septin 1 mutant were grown and diffraction data were collected to 2.5 Å resolution. Septin 1 is a member of an evolutionarily conserved family of GTP-binding and filament-forming proteins named septins, which function in diverse processes including cytokinasis, vesicle trafficking, apoptosis, remodelling of the cytoskeleton, infection, neurodegeneration and neoplasia. Human septin 1 has been expressed and purified, but suffers from severe aggregation. Studies have shown that septin 1 with site-directed mutations of five serine residues (Ser19, Ser206, Ser307, Ser312 and Ser315) has a much lower degree of aggregation and better structural homogeneity and that the mutations cause only slight perturbations in the secondary structure of septin 1. This septin 1 mutant was crystallized and diffraction data were collected to 2.5 Å resolution. The space group is P422, with unit-cell parameters a = b = 106.028, c = 137.852 Å.

  5. Hydrogeochemical evaluation for Simpevarp model version 1.2. Preliminary site description of the Simpevarp area

    International Nuclear Information System (INIS)

    Laaksoharju, Marcus

    2004-12-01

    Siting studies for SKB's programme of deep geological disposal of nuclear fuel waste currently involves the investigation of two locations, Simpevarp and Forsmark, to determine their geological, hydrogeochemical and hydrogeological characteristics. Present work completed has resulted in Model version 1.2 which represents the second evaluation of the available Simpevarp groundwater analytical data collected up to April, 2004. The deepest fracture groundwater samples with sufficient analytical data reflected depths down to 1.7 km. Model version 1.2 focusses on geochemical and mixing processes affecting the groundwater composition in the uppermost part of the bedrock, down to repository levels, and eventually extending to 1000 m depth. The groundwater flow regimes at Laxemar/Simpevarp are considered local and extend down to depths of around 600-1000 m depending on local topography. The marked differences in the groundwater flow regimes between Laxemar and Simpevarp are reflected in the groundwater chemistry where four major hydrochemical groups of groundwaters (types A-D) have been identified: TYPE A: This type comprises dilute groundwaters ( 3 type present at shallow ( 300 m) levels at Simpevarp, and at even greater depths (approx. 1200 m) at Laxemar. At Simpevarp the groundwaters are mainly Na-Ca-Cl with increasingly enhanced Br and SO 4 with depth. At Laxemar they are mainly Ca-Na-Cl also with increasing enhancements of Br and SO 4 with depth. Main reactions involve ion exchange (Ca). At both sites a glacial component and a deep saline component are present. At Simpevarp the saline component may be potentially non marine and/or non-marine/old Littorina marine in origin; at Laxemar it is more likely to be non-marine in origin. TYPE D: This type comprises reducing highly saline groundwaters (> 20 000 mg/L Cl; to a maximum of ∼70 g/L TDS) and only has been identified at Laxemar at depths exceeding 1200 m. It is mainly Ca-Na-Cl with higher Br but lower SO 4 compared

  6. Preliminary results of the first scientific Drilling on Lake Baikal, Buguldeika site, southeastern Siberia

    Science.gov (United States)

    Williams, Douglas F.; Colman, S.; Grachev, M.; Hearn, P.; Horie, Shoji; Kawai, T.; Kuzmin, Mikhail I.; Logachov, N.; Antipin, V.; Bardardinov, A.; Bucharov, A.; Fialkov, V.; Gorigljad, A.; Tomilov, B.; Khakhaev, B.N.; Kochikov, S.; Logachev, N.; Pevzner, L.A.; Karabanov, E.B.; Mats, V.; Baranova, E.; Khlystov, O.; Khrachenko, E.; Shimaraeva, M.; Stolbova, E.; Efremova, S.; Gvozdkov, A.; Kravchinski, A.; Peck, J.; Fileva, T.; Kashik, S.; Khramtsova, T.; Kalashnikova, I.; Rasskazova, T.; Tatarnikova, V.; Yuretich, Richard; Mazilov, V.; Takemura, K.; Bobrov, V.; Gunicheva, T.; Haraguchi, H.; Ito, S.; Kocho, T.; Markova, M.; Pampura, V.; Proidakova, O.; Ishiwatari, R.; Sawatari, H.; Takeuchi, A.; Toyoda, K.; Vorobieva, S.; Ikeda, A.; Marui, A.; Nakamura, T.; Ogura, K.; Ohta, Takeshi; King, J.; Sakai, H.; Yokoyama, T.; Hayashida, A.; Bezrukova, E.; Fowell, S.; Fujii, N.; Letunova, P.; Misharina, V.; Miyoshi, N.; Chernyaeva, G.; Ignatova, I.; Likhoshvai, E.; Granina, L.; Levina, O.; Dolgikh, P.; Lazo, F.; Lutskaia, N.; Orem, W.; Wada, E.; Yamada, K.; Yamada, S.; Callander, E.; Golobokoval, L.; Shanks, W. C. Pat; Dorofeeva, R.; Duchkov, A.

    1997-01-01

    The Baikal Drilling Project (BDP) is a multinational effort to investigate the paleoclimatic history and tectonic evolution of the Baikal sedimentary basin during the Late Neogene. In March 1993 the Baikal drilling system was successfuly deployed from a barge frozen into position over a topographic high, termed the Buguldeika saddle, in the southern basin of Lake Baikal. The BDP-93 scientific team, made up of Russian, American and Japanese scientists, successfully recovered the first long (>100 m) hydraulic piston cores from two holes in 354 m of water. High quality cores of 98 m (Hole 1) and 102 m (Hole 2), representing sedimentation over the last 500,000 years, were collected in 78 mm diameter plastic liners with an average recovery of 72% and 90%, respectively. Magnetic susceptibility logging reveals an excellent hole-to-hole correlation. In this report the scientific team describes the preliminary analytical results from BDP-93 hole 1 cores. Radiocarbon dating by accelerator mass spectrometry provides an accurate chronology for the upper portion of Hole 1. Detailed lithologic characteristics, rock magnetic properties and inorganic element distributions show a significant change to the depositional environment occuring at 50 m subbottom depth, approximately 250,000 BP. This change may be due to uplift and rotation of the horst block in the Buguldeika saddle. The sedimentary section above 50 m is pelitic with varve-like laminae, whereas the section below 50 m contains a high proportion of sand and gravel horizons often organized into turbidite sequences. Accordingly, high resolution seismic records reveal a change in sonic velocity at this depth. It is inferred that sedimentation prior to 250 ka BP was from the west via the Buguldeika river system. After 250 ka BP the Buguldeika saddle reflects an increase in hemipelagic sediments admixed with fine-grained material from the Selenga River drainage basin, east of Lake Baikal. Variations in the spore

  7. A preliminary study of archaeological ceramic from the Sao Paulo II, Brazil, archaeological site by Instrumental Neutron Activation Analysis (INAA)

    International Nuclear Information System (INIS)

    Ribeiro, Rogerio B.; Munita, Casimiro S.; Oliveira, Paulo M.S.; Neves, Eduardo G.; Tamahara, Eduardo K.

    2011-01-01

    The determination of trace elements plays an important role in the characterization of archaeological ceramics. It is well established that ceramics can be grouped based on similarities/dissimilarities derived from chemical data. Different analytical methods can be applied to determine the sample composition. Instrumental neutron activation analysis (INAA) is the method preferred because present several advantages in relation to the other techniques. In this work, the elements determined were As, K, La, Lu, Na, Nd, Sb, Sm, U, Yb, Ba, Ce, Co, Cr, Cs, I, Fe, Hf, Rb, Sc, Ta , Tb, Th and Zn to carry out a preliminary chemical characterization in 44 ceramic samples from Sao Paulo II archaeological site by INAA. The site is located in Coari city, 363 km from Manaus, Amazonas state (AM). The elementary concentration results were studied using multivariate statistical methods. The similarity/dissimilarity among the samples was studied by means of discriminant analysis. The compositions group classification was done through cluster analysis, showing the formation of the three distinct groups of the ceramics. (author)

  8. Preliminary geoarchaeological data from a Senegambian megalithic world heritage site (Wanar, Senegal).

    Science.gov (United States)

    Stern, Mathilde; Rigaud, Antoine; Landry, David; Ballouche, Aziz

    2017-04-01

    The Senegambian megalithic complex spread over a territory of 250 km from east to west and 120 to 150 km from north to south. It consists of various monumental forms, especially erected stones circles. At the regional Senegambian scale the excavated sites suggest dates between 7th and 16th century AD, maby older. The exceptional concentration of the alignments and the originality of the forms ("lyre" stones, bifid stones, disc decorations, associated with other monuments, e.g. burial mounds) motivated the inscription of four sites of Senegal and Gambia as World Heritage by UNESCO, like the site of Wanar in Senegal, in the watershed of the Bao Bolon, a tributary of the Gambia River (whc.unesco.org/en/list/1226). However, very little is known about the natural environment of these spectacular monumental manifestations, nor about the socio-economic context of their edification and the surrounding landscapes. Since 2005, archaeological excavations are carried out every year on the necropolis of Wanar. Such research contributes to enrich the socio-cultural knowledge of the Senegambian megalithism, phenomenon associated with the Protohistory (wanar-excavations.jimdo.com). Geoarchaeological studies (geomorphological and palaeo-biogeographical) currently in progress at Wanar aim to reconstruct palaeoenvironments and landscapes contemporary of the monument construction, in order to answer a series of questions: In which landscape context have these populations developed? What were their relations with their environment? How did they fit into their territory, and how did they adapt to environmental changes? The dated material from two cores shows that the sedimentary records cover an extended timespan which include the Senegalese protohistory and previous periods (up to 5000 cal. BP). First sedimentological results describe the hydrosedimentary functioning of the Wanar watershed during the period contemporary with the megalithic phenomenon. Palaeoclimatic signals and

  9. Preliminary studies on the Marcoule site, using a wind-tunnel

    International Nuclear Information System (INIS)

    Chassany, J.Ph.; Salaun-Penquer, G.

    1961-01-01

    The tests were carried out in the 3.30 x 2.20 subsonic elliptical wind-tunnel of the Marseille Institute of fluid mechanics, on a 1/1000 scale model measuring 3 m x 3 m. The aerodynamic field developing above the site, made visible by ammonium, hydro-chlorate fumes, and the residues were observed and filmed by means of a synchronised cine-camera with stroboscopic lighting for 4 wind directions. The fall-out from the various waste products was obtained from a spraying of lead acetate solution on the model and hydrogen sulphide emissions. The zones of maximum pollution can be determined from a study of the film taken during the blackening of the spots. (author) [fr

  10. Preliminary Compositional Evidence of Provenance of Ceramics from Hatahara Archaeological Site, Central Amazonia

    Directory of Open Access Journals (Sweden)

    K. P. Nunes

    2013-01-01

    Full Text Available One hundred twenty four ceramic fragments and six clay samples from the Hatahara archaeological site in Amazonas state, Brazil, were analyzed using instrumental neutron activation analysis, INAA, to determine the concentration of twenty chemical elements: Ce, Co, Cr, Cs, Eu, Fe, Hf, K, La, Lu, Na, Nd, Rb, Sc, Ta, Tb, Th, U, Yb, and Zn. The dataset was submitted to multivariate statistical analysis. The classification was done by cluster analysis and discriminant analysis. The results demonstrated the occurrence of four different groups of ceramics, which represent three archaeological phases: Paredão, Manacapuru, and Guarita. This data is consistent with previous traditional petrographic examination of the ceramic samples. Based on probability measures, the great majority of the ceramics are considered to be local in origin.

  11. Natural science research of the Bulgar fortified settlement site (preliminary results

    Directory of Open Access Journals (Sweden)

    Golyeva Alexandra A.

    2014-06-01

    Full Text Available The article presents the first results of the comprehensive scientific research conducted on the Bulgar fortified settlement site in 2011. Samples for analysis were selected in the form of series of vertical columns from excavation walls. The species of trees used in the construction, the composition of the mud bricks and the bonding mortar, as well as the genesis of individual cultural layers have been identified. It has been found out that the settlement development and functioning had been reciprocating in nature: periods of intense habitation of its individual sections were followed by short stages of desolation. In all investigated soil columns with the cultural layers there are streaks consisting solely of phytoliths and cuticle casts. A possible explanation of the phenomenon may be that the plot was covered with layers of manure of significant length and capacity. This conclusion is debatable and requires further research.

  12. A COPRAS-F base multi-criteria group decision making approach for site selection of wind farm

    Directory of Open Access Journals (Sweden)

    Nikhil Chandra Chatterjee

    2013-01-01

    Full Text Available Today global warming is on the rise and the natural resources are getting consumed at a faster rate. Power consumption has increased many folds to cater the human need. Thus renewable energy resources are the only option available at this juncture. Wind energy is one of the renewable energy. Location selection for wind farm takes an important role on power generation. However, the location selection is a complex multicriteria problem due to the criteria factors which are conflicting in nature as well as uncertain. The process becomes more complex when a group of decision makers are involved in decision making. In the present study, a COPRAS (COmplex PRoportional ASsessment based multi-criteria decision-making (MCDM methodology is done under fuzzy environment with the help of multiple decision makers. More specifically, this study is aimed to focus the applicability of COPRAS-F as a strategic decision making tools to handle the group decision-making problems.

  13. The Italian bat roost project: a preliminary inventory of sites and conservation perspectives

    Directory of Open Access Journals (Sweden)

    Gruppo Italiano di Ricerca sui Chirotter GIRC

    2005-01-01

    Full Text Available Abstract The Italian bat roost project, launched by the Italian Chiroptera Research Group (GIRC, aims to develop a constantly updated national database of bat roosts. Short-term objectives are to inventory roosts and identify the most important ones from a conservation perspective, in order to set priorities for management actions. Published records and field data from 1990 onwards are filed. To date, the database contains 1243 records from 750 roosts, covering 352 10x10 km UTM grid-cells. Among roosts, 167 were used for hibernation (S roosts, 244 for breeding (R roosts and 431 as either temporary roosts or for unknown needs, not verified or not considered in the survey (X roosts. Roosting sites occurred in buildings (45.1%, caves (35.3%, artificial underground sites (10.3%, trees (5.5%, bridges (2.1%, bat boxes (1.3% and rocky cliffs (0.4%. At least 29 species were found, and the number of roosts per species ranged between 1 and 261. S and/or R roosts fulfilling certain combinations of number of species and individuals or having at least 50 individuals of species cited in Annex II of the 92/43/EEC Directive (excluding Miniopterus schreibersii, adding Myotis punicus were classified as sites of special conservation interest. When meeting at least one such conditions, type X roosts that were not classified as either S or R, were considered potential sites of special conservation interest, for which further data collection is recommended. In all, 97 roosts of special conservation interest were identified: 30 S roosts, 60 R roosts and 7 roosts selected for both hibernation and breeding. 20 X roosts were identified as potential sites of special conservation interest. For at least 93.7% of roosts, factors potentially harming the bats were documented, particularly people access to the roost, and renovation of buildings used as a roost. In almost two thirds of such cases it was judged that conservation was not ensured

  14. Hydrogeochemical evaluation for Simpevarp model version 1.2. Preliminary site description of the Simpevarp area

    Energy Technology Data Exchange (ETDEWEB)

    Laaksoharju, Marcus (ed.) [Geopoint AB, Stockholm (Sweden)

    2004-12-01

    Siting studies for SKB's programme of deep geological disposal of nuclear fuel waste currently involves the investigation of two locations, Simpevarp and Forsmark, to determine their geological, hydrogeochemical and hydrogeological characteristics. Present work completed has resulted in Model version 1.2 which represents the second evaluation of the available Simpevarp groundwater analytical data collected up to April, 2004. The deepest fracture groundwater samples with sufficient analytical data reflected depths down to 1.7 km. Model version 1.2 focusses on geochemical and mixing processes affecting the groundwater composition in the uppermost part of the bedrock, down to repository levels, and eventually extending to 1000 m depth. The groundwater flow regimes at Laxemar/Simpevarp are considered local and extend down to depths of around 600-1000 m depending on local topography. The marked differences in the groundwater flow regimes between Laxemar and Simpevarp are reflected in the groundwater chemistry where four major hydrochemical groups of groundwaters (types A-D) have been identified: TYPE A: This type comprises dilute groundwaters (< 1000 mg/L Cl; 0.5-2.0 g/L TDS) of Na-HCO{sub 3} type present at shallow (<200 m) depths at Simpevarp, but at greater depths (0-900 m) at Laxemar. At both localities the groundwaters are marginally oxidising close to the surface, but otherwise reducing. Main reactions involve weathering, ion exchange (Ca, Mg), surface complexation, and dissolution of calcite. Redox reactions include precipitation of Fe-oxyhydroxides and some microbially mediated reactions (SRB). Meteoric recharge water is mainly present at Laxemar whilst at Simpevarp potential mixing of recharge meteoric water and a modern sea component is observed. Localised mixing of meteoric water with deeper saline groundwaters is indicated at both Laxemar and Simpevarp. TYPE B: This type comprises brackish groundwaters (1000-6000 mg/L Cl; 5-10 g/L TDS) present at

  15. A COPRAS-F base multi-criteria group decision making approach for site selection of wind farm

    OpenAIRE

    Nikhil Chandra Chatterjee; Goutam Kumar Bose

    2013-01-01

    Today global warming is on the rise and the natural resources are getting consumed at a faster rate. Power consumption has increased many folds to cater the human need. Thus renewable energy resources are the only option available at this juncture. Wind energy is one of the renewable energy. Location selection for wind farm takes an important role on power generation. However, the location selection is a complex multicriteria problem due to the criteria factors which are conflicting in nature...

  16. InterTechnology Corporation proposed criteria and recommendations for selection of PON non-residential demonstration sites

    Energy Technology Data Exchange (ETDEWEB)

    None

    1976-12-01

    This report has been prepared with the objective of providing ERDA with recommended procedures for implementing the strategies set forth in the Systems Level Plan which are considered essential to the success of the National Demonstration Program. In order to logically develop these recommendations, this report is divided into three sections: A. Overview of the Demonstration Program to date. B. Essential Overall Program Strategies. C. Candidate Screening and Selection Criteria. (WDM)

  17. Design criteria applicable to the environmental restoration of sites affected by uranium mining activities in the past

    International Nuclear Information System (INIS)

    Carboneras, P.; Sanchez, M.

    1993-01-01

    In this paper the authors discuss the basic aspects to be considered while evaluating different alternatives to perform environmental restoration of sites affected by naturally occurring radionuclides, enhanced by human actions, as is the case in some old uranium mining activities. The discussion is confined to sites where radiation hazards had existed forever (sites with uranium deposits) and where the mining activities have introduced several factors modifying the initial situation, leading to the now existing one, requiring intervention as decided by the relevant authorities, in accordance with recommendations of ICRP60

  18. Design criteria applicable to the environmental restoration of sites affected by uranium mining activities in the past

    Energy Technology Data Exchange (ETDEWEB)

    Carboneras, P. [ENRESA, Madrid (Spain); Sanchez, M. [INITEC, Madrid (Spain)

    1993-12-31

    In this paper the authors discuss the basic aspects to be considered while evaluating different alternatives to perform environmental restoration of sites affected by naturally occurring radionuclides, enhanced by human actions, as is the case in some old uranium mining activities. The discussion is confined to sites where radiation hazards had existed forever (sites with uranium deposits) and where the mining activities have introduced several factors modifying the initial situation, leading to the now existing one, requiring intervention as decided by the relevant authorities, in accordance with recommendations of ICRP60.

  19. Development of methods and criteria for a standardized evaluation of contaminated sites and abandoned waste disposal sites particularly concerning their ground water contamination potential. Pt. 1. Final Report

    International Nuclear Information System (INIS)

    Kerndorff, H.; Schleyer, R.; Arneth, J.D.; Struppe, T.; Milde, G.

    1994-01-01

    Contaminated sites should be evaluated to such an extend, that nearly all risks for man and environment can be safely estimated. An assessment for such sites is presented which combines a substance-specific and a site-specific evaluation. It is a standardized path-specific concept in which - as an example - the contamination path ''waste - groundwater - drinking-water'' is investigated and evaluated in detail. Path-specific main contaminants are established on a statistic basis and ranked according to normalized evaluation numbers of 1-100. Their toxicity potential is calculated for which a particular and standardized method was developed. Main contaminants having a high toxicity potential are called priority contaminants. For the most important exposure/usage on this contamination path, the drinking-water catchment, hygienic and toxicologic based standards are presented. Together with site-specific conditions and the also path-specific and normalized transfer/persistency potential of the priority contaminants it is possible to come to a site- and usage/exposure-specific evaluation of individual sites. (orig.) [de

  20. Thermal modelling. Preliminary site description. Forsmark area - version 1.2

    Energy Technology Data Exchange (ETDEWEB)

    Sundberg, Jan; Back, Paer-Erik; Bengtsson, Anna; Laendell, Maerta [Geo Innova AB, Linkoeping (Sweden)

    2005-08-01

    This report presents the thermal site descriptive model for the Forsmark area, version 1.2. The main objective of this report is to present the thermal modelling work where data has been identified, quality controlled, evaluated and summarised in order to make an upscaling to lithological domain level possible. The thermal conductivity at canister scale has been modelled for two different lithological domains (RFM029 and RFM012, both dominated by granite to granodiorite (101057)). A main modelling approach has been used to determine the mean value of the thermal conductivity. Two alternative/complementary approaches have been used to evaluate the spatial variability of the thermal conductivity at domain level. The thermal modelling approaches are based on the lithological model for the Forsmark area, version 1.2 together with rock type models constituted from measured and calculated (from mineral composition) thermal conductivities. Results indicate that the mean of thermal conductivity is expected to exhibit a small variation between the different domains, 3.46 W/(mxK) for RFM012 to 3.55 W/(mxK) for RFM029. The spatial distribution of the thermal conductivity does not follow a simple model. Lower and upper 95% confidence limits are based on the modelling results, but have been rounded of to only two significant figures. Consequently, the lower limit is 2.9 W/(mxK), while the upper is 3.8 W/(mxK). This is applicable to both the investigated domains. The temperature dependence is rather small with a decrease in thermal conductivity of 10.0% per 100 deg C increase in temperature for the dominating rock type. There are a number of important uncertainties associated with these results. One of the uncertainties considers the representative scale for the canister. Another important uncertainty is the methodological uncertainties associated with the upscaling of thermal conductivity from cm-scale to canister scale. In addition, the representativeness of rock samples is

  1. Preliminary results of studies of the Valea Morilor Upper Palaeolithic site (Chisinau, Republic of Moldova) : A new camp of mammoth hunters

    NARCIS (Netherlands)

    Obada, Teodor; van der Plicht, Johannes; Markova, Anastasia; Prepelitsa, Afanasie

    2012-01-01

    Preliminary results are presented from the studies of a newly found Paleolithic site - Valea Morilor (Chisingu, Republic of Moldova). The excavations produced unquestionable evidence of mammoth hunting (Mammuthus primigenius Blumenbach, 1799). Excavations of 2009-2010 opened an area of 1264 m(2).

  2. Preliminary evaluation of techniques for transforming regional climate model output to the potential repository site in support of Yucca Mountain future climate synthesis

    International Nuclear Information System (INIS)

    Church, H.W.; Zak, B.D.; Behl, Y.K.

    1995-06-01

    The report describes a preliminary evaluation of models for transforming regional climate model output from a regional to a local scale for the Yucca Mountain area. Evaluation and analysis of both empirical and numerical modeling are discussed which is aimed at providing site-specific, climate-based information for use by interfacing activities. Two semiempirical approaches are recommended for further analysis

  3. Thermal modelling. Preliminary site description Simpevarp subarea - version 1.2

    Energy Technology Data Exchange (ETDEWEB)

    Sundberg, Jan; Back, Paer-Erik; Bengtsson, Anna; Laendell, Maerta [Geo Innova AB, Linkoeping (Sweden)

    2005-08-15

    This report presents the thermal site descriptive model for the Simpevarp subarea, version 1.2. The main objective of this report is to present the thermal modelling work where data has been identified, quality controlled, evaluated and summarised in order to make an upscaling to lithological domain level possible. The thermal conductivity at possible canister scale has been modelled for four different lithological domains (RSMA01 (Aevroe granite), RSMB01 (Fine-grained dioritoid), RSMC01 (mixture of Aevroe granite and Quartz monzodiorite), and RSMD01 (Quartz monzodiorite)). A main modelling approach has been used to determine the mean value of the thermal conductivity. Three alternative/complementary approaches have been used to evaluate the spatial variability of the thermal conductivity at domain level. The thermal modelling approaches are based on the lithological model for the Simpevarp subarea, version 1.2 together with rock type models constituted from measured and calculated (from mineral composition) thermal conductivities. For one rock type, the Aevroe granite (501044), density loggings within the specific rock type has also been used in the domain modelling in order to consider the spatial variability within the Aevroe granite. This has been possible due to the presented relationship between density and thermal conductivity, valid for the Aevroe granite. Results indicate that the mean of thermal conductivity is expected to exhibit only a small variation between the different domains, from 2.62 W/(m.K) to 2.80 W/(m.K). The standard deviation varies according to the scale considered and for the canister scale it is expected to range from 0.20 to 0.28 W/(m.K). Consequently, the lower confidence limit (95% confidence) for the canister scale is within the range 2.04-2.35 W/(m.K) for the different domains. The temperature dependence is rather small with a decrease in thermal conductivity of 1.1-3.4% per 100 deg C increase in temperature for the dominating rock

  4. Preliminary Performance Assessment for the Waste Management Area C at the Hanford Site in Southeast Washington

    International Nuclear Information System (INIS)

    Bergeron, Marcel P.; Singleton, Kristin M.; Eberlein, Susan J.

    2015-01-01

    A performance assessment (PA) of Single-Shell Tank (SST) Waste Management Area C (WMA C) located at the U.S. Department of Energy's (DOE) Hanford Site in southeastern Washington is being conducted to satisfy the requirements of the Hanford Federal Facility Agreement and Consent Order (HFFACO), as well as other Federal requirements and State-approved closure plans and permits. The WMP C PA assesses the fate, transport, and impacts of radionuclides and hazardous chemicals within residual wastes left in tanks and ancillary equipment and facilities in their assumed closed configuration and the subsequent risks to humans into the far future. The part of the PA focused on radiological impacts is being developed to meet the requirements for a closure authorization under DOE Order 435.1 that includes a waste incidental to reprocessing determination for residual wastes remaining in tanks, ancillary equipment, and facilities. An additional part of the PA will evaluate human health and environmental impacts from hazardous chemical inventories in residual wastes remaining in WMA C tanks, ancillary equipment, and facilities needed to meet the requirements for permitted closure under RCRA.

  5. Thermal modelling. Preliminary site description Simpevarp subarea - version 1.2

    International Nuclear Information System (INIS)

    Sundberg, Jan; Back, Paer-Erik; Bengtsson, Anna; Laendell, Maerta

    2005-08-01

    This report presents the thermal site descriptive model for the Simpevarp subarea, version 1.2. The main objective of this report is to present the thermal modelling work where data has been identified, quality controlled, evaluated and summarised in order to make an upscaling to lithological domain level possible. The thermal conductivity at possible canister scale has been modelled for four different lithological domains (RSMA01 (Aevroe granite), RSMB01 (Fine-grained dioritoid), RSMC01 (mixture of Aevroe granite and Quartz monzodiorite), and RSMD01 (Quartz monzodiorite)). A main modelling approach has been used to determine the mean value of the thermal conductivity. Three alternative/complementary approaches have been used to evaluate the spatial variability of the thermal conductivity at domain level. The thermal modelling approaches are based on the lithological model for the Simpevarp subarea, version 1.2 together with rock type models constituted from measured and calculated (from mineral composition) thermal conductivities. For one rock type, the Aevroe granite (501044), density loggings within the specific rock type has also been used in the domain modelling in order to consider the spatial variability within the Aevroe granite. This has been possible due to the presented relationship between density and thermal conductivity, valid for the Aevroe granite. Results indicate that the mean of thermal conductivity is expected to exhibit only a small variation between the different domains, from 2.62 W/(m.K) to 2.80 W/(m.K). The standard deviation varies according to the scale considered and for the canister scale it is expected to range from 0.20 to 0.28 W/(m.K). Consequently, the lower confidence limit (95% confidence) for the canister scale is within the range 2.04-2.35 W/(m.K) for the different domains. The temperature dependence is rather small with a decrease in thermal conductivity of 1.1-3.4% per 100 deg C increase in temperature for the dominating rock

  6. Preliminary Performance Assessment for the Waste Management Area C at the Hanford Site in Southeast Washington

    Energy Technology Data Exchange (ETDEWEB)

    Bergeron, Marcel P. [Washington River Protection Solutions LLC, Richland, WA (United States); Singleton, Kristin M. [Washington River Protection Solutions LLC, Richland, WA (United States); Eberlein, Susan J. [Washington River Protection Solutions LLC, Richland, WA (United States)

    2015-01-07

    A performance assessment (PA) of Single-Shell Tank (SST) Waste Management Area C (WMA C) located at the U.S. Department of Energy's (DOE) Hanford Site in southeastern Washington is being conducted to satisfy the requirements of the Hanford Federal Facility Agreement and Consent Order (HFFACO), as well as other Federal requirements and State-approved closure plans and permits. The WMP C PA assesses the fate, transport, and impacts of radionuclides and hazardous chemicals within residual wastes left in tanks and ancillary equipment and facilities in their assumed closed configuration and the subsequent risks to humans into the far future. The part of the PA focused on radiological impacts is being developed to meet the requirements for a closure authorization under DOE Order 435.1 that includes a waste incidental to reprocessing determination for residual wastes remaining in tanks, ancillary equipment, and facilities. An additional part of the PA will evaluate human health and environmental impacts from hazardous chemical inventories in residual wastes remaining in WMA C tanks, ancillary equipment, and facilities needed to meet the requirements for permitted closure under RCRA.

  7. Preliminary analysis of an hydrogen generator system based on nuclear energy in the Laguna Verde site

    International Nuclear Information System (INIS)

    Flores y Flores, A.; Francois L, J.L.

    2003-01-01

    The shortage of fossil fuels in the next future, as well as the growing one demand of energetics and the high cost of the production of alternating fuels, it forces us to take advantage of to the maximum the fossil fuel with the one which we count and to look for the form of producing alternating fuels at a low cost and better even if these supply sources are reliable and non pollutants. It is intended a solution to the shortage of fuel; to use the thermal energy liberated of some appropriate nuclear reactor to be able to obtain a fuel but clean and relatively cheap as it is the hydrogen. In the first place the methods were looked for to produce hydrogen using thermal energy, later it was analyzed the temperature liberated by the existent nuclear reactors as well as the advanced designs, according to this liberated temperature settled down that the methods but feasible to produce hydrogen its were the one of reformed with water stream of the natural gas (methane) and the other one of the S-I thermochemical cycle, and the nuclear reactors that give the thermal energy for this production they are those of gas of high temperature. Once established the processes and the appropriate reactors, it was analyzed the site of Laguna Verde, with relationship to the free space to be able to place the reactor and the plant producer of hydrogen, as well as the direction in which blow the dominant winds and the near towns to the place, it was carried out an analysis of some explosion of tanks that could store hydrogen and the damage that its could to cause depending from the distance to which its were of the fire. Finally it was carried out an evaluation of capital and of operation costs for those two methods of hydrogen production. (Author)

  8. Preliminary results from EMERSITO, a rapid response network for site-effect studies

    Directory of Open Access Journals (Sweden)

    Paola Bordoni

    2012-10-01

    Full Text Available On May 20, 2012, at 02:03 UTC, a Ml 5.9 reverse-fault earthquake occurred in the Emilia-Romagna region, northern Italy, at a hypocentral depth of 6.3 km (http://iside.rm.ingv.it/, close to the cities of Modena and Ferrara in the plain of the Po River. The epicenter was near the village of Finale Emilia where macroseismic intensity was assessed at 7 EMS98 [Tertulliani et al. 2012, this issue], while the closest accelerometric station, MRN, located less than 20 km west-ward at Mirandola (Figure 1 recorded peaks of ground accelerations of about 300 cm/s2 (www.protezionecivile.gov.it/resources/cms/documents/Report_DPC_1_Emilia_EQSd.pdf. The mainshock triggered liquefaction phenomena a few kilometers eastwards of the epicenter, around the village of San Carlo. On the same day, two other shocks of Ml 5.1 followed (02:07, 13:18 GMT; http://iside.rm.ingv.it/. On May 29, 2012, at 07:00 UTC another Ml 5.8 earthquake hit the region (http://iside.rm.ingv.it/, with the epicenter close to the village of Mirandola (Figure 1. Three other strong aftershocks occurred afterwards, of Ml 5.3 (May 29, at 10:55, Ml 5.2 (May 29, at 11:00 and Ml 5.1 (June 3, at 19:20. For a detailed description of the seismic sequence, see Moretti et al. [2012], Scognamiglio et al. [2012], and Massa et al. [2012], in this issue. The Emilia seismic sequence resulted in 25 casualties, several of whom were among the workers in the many factories that collapsed during working hours, and there was extensive damage to monuments, public buildings, industrial sites, and private homes. […

  9. The Future Through the Past: The Use of Analog Sites for Design Criteria and Long Term Performance Assessment of Evapotranspiration Landfill Covers

    Energy Technology Data Exchange (ETDEWEB)

    Shafer, D. S.; Miller, J. J.; Young, M. H.; Edwards, S. C.; Rawlinson, S. E.

    2002-02-26

    There is growing support for using evapotranspiration (ET) covers for closure of low-level waste (LLW) and other types of waste disposal sites, particularly in the lower latitude arid regions of the western United States. At the Nevada Test Site (NTS), monolayer ET covers are the baseline technology for closure of LLW and mixed LLW cells. To better predict the long-term performance of monolayer ET covers, as well as to identify design criteria that will potentially improve their performance, the properties of, and processes occurring on, analog sites for ET covers on the NTS are being studied. The project is funded through the Subsurface Contaminants Focus Area of the U.S. Department of Energy. Four analog sites on the NTS have been selected to predict performance of ET covers over a 1,000-year compliance period. Two sites are relatively recently disturbed (within the last 50 years) and have been selected to evaluate processes and changes on ET covers for the early period after active cover maintenance is discontinued. Two other sites, late to mid-Holocene in age, are intended as analogs for the end of the compliance period (1,000 years or more); both surfaces are abandoned alluvial/colluvial deposits. The history of the early post-institutional control analog sites are being evaluated by an archaeologist to help determine when the sites were last disturbed or modified, and the mode of disturbance to help set baseline conditions. Similar to other ''landforms,'' ET covers will evolve over time because of pedogenic, biotic, and climatic processes. Properties of analog sites that could affect ET water balance performance will be evaluated to help understand ET cover performance over time.

  10. Thermal modelling. Preliminary site description Laxemar subarea - version 1.2

    Energy Technology Data Exchange (ETDEWEB)

    Sundberg, Jan; Wrafter, John; Back, Paer-Erik; Laendell, Maerta [Geo Innova AB, Linkoeping (Sweden)

    2006-02-15

    This report presents the thermal site descriptive model for the Laxemar subarea, version 1.2. The main objective of this report is to present the thermal modelling work where data has been identified, quality controlled, evaluated and summarised in order to make an upscaling to lithological domain level possible. The thermal conductivity at canister scale has been modelled for five different lithological domains: RSMA (Aevroe granite), RSMBA (mixture of Aevroe granite and fine-grained dioritoid), RSMD (quartz monzodiorite), RSME (diorite/gabbro) and RSMM (mix domain with high frequency of diorite to gabbro). A base modelling approach has been used to determine the mean value of the thermal conductivity. Four alternative/complementary approaches have been used to evaluate the spatial variability of the thermal conductivity at domain level. The thermal modelling approaches are based on the lithological domain model for the Laxemar subarea, version 1.2 together with rock type models based on measured and calculated (from mineral composition) thermal conductivities. For one rock type, Aevroe granite (501044), density loggings have also been used in the domain modelling in order to evaluate the spatial variability within the Aevroe granite. This has been possible due to an established relationship between density and thermal conductivity, valid for the Aevroe granite. Results indicate that the means of thermal conductivity for the various domains are expected to exhibit a variation from 2.45 W/(m.K) to 2.87 W/(m.K). The standard deviation varies according to the scale considered, and for the 0.8 m scale it is expected to range from 0.17 to 0.29 W/(m.K). Estimates of lower tail percentiles for the same scale are presented for all five domains. The temperature dependence is rather small with a decrease in thermal conductivity of 1.1-5.3% per 100 deg C increase in temperature for the dominant rock types. There are a number of important uncertainties associated with these

  11. Valuation of provisional and cultural services of a Ramsar site: A preliminary study on Rudrasagar lake, India

    Directory of Open Access Journals (Sweden)

    Moitree Taran

    2017-01-01

    Full Text Available Rudrasagar lake, a Ramsar site in India offers a variety of ecosystem services. The contribution of Rudrasagar lake to the society has not been estimated so far. The preliminary study aims to provide an economic valuation of the provisional and cultural services of the Rudrasagar lake. Official records of revenue collected by the Tourism Department of Tripura and a socio- economic survey was the source of information used in the economic valuation of the lake. The main provisional services provided by the lake are food (aquatic plants and fishes, fuel wood and timber whereas, the cultural services provided were boat raiding and tourism due to its historical importance. The provisioning and cultural services provided by the Rudrasagar lake are 40810 US$ and 33929.33 US$ per year respectively during the period of 2010-2015. The main threats to the wetland identified are increasing silt loads due to deforestation, expansion of agricultural land and land conversion due to population pressure. To alleviate the anthropogenic stress on the lake, better monitoring, planning and management are essential. By proper conservation and management it will be possible to enjoy the provisional and cultural services of the lake in a sustainable way.

  12. Conceptual modeling framework to support development of site-specific selenium criteria for Lake Koocanusa, Montana, U.S.A., and British Columbia, Canada

    Science.gov (United States)

    Jenni, Karen E.; Naftz, David L.; Presser, Theresa S.

    2017-10-16

    The U.S. Geological Survey, working with the Montana Department of Environmental Quality and the British Columbia Ministry of the Environment and Climate Change Strategy, has developed a conceptual modeling framework that can be used to provide structured and scientifically based input to the Lake Koocanusa Monitoring and Research Working Group as they consider potential site-specific selenium criteria for Lake Koocanusa, a transboundary reservoir located in Montana and British Columbia. This report describes that modeling framework, provides an example of how it can be applied, and outlines possible next steps for implementing the framework.

  13. Regional hydrogeological simulations. Numerical modelling using ConnectFlow. Preliminary site description Simpevarp sub area - version 1.2

    Energy Technology Data Exchange (ETDEWEB)

    Hartley, Lee; Hoch, Andrew; Hunter, Fiona; Jackson, Peter [Serco Assurance, Risley (United Kingdom); Marsic, Niko [Kemakta Konsult, Stockholm (Sweden)

    2005-02-01

    objective of this study is to support the development of a preliminary Site Description of the Simpevarp area on a regional-scale based on the available data of August 2004 (Data Freeze S1.2) and the previous Site Description. A more specific objective of this study is to assess the role of known and unknown hydrogeological conditions for the present-day distribution of saline groundwater in the Simpevarp area on a regional-scale. An improved understanding of the paleo-hydrogeology is necessary in order to gain credibility for the Site Description in general and the hydrogeological description in particular. This is to serve as a basis for describing the present hydrogeological conditions on a local-scale as well as predictions of future hydrogeological conditions. Other key objectives were to identify the model domain required to simulate regional flow and solute transport at the Simpevarp area and to incorporate a new geological model of the deformation zones produced for Version S1.2.Another difference with Version S1.1 is the increased effort invested in conditioning the hydrogeological property models to the fracture boremap and hydraulic data. A new methodology was developed for interpreting the discrete fracture network (DFN) by integrating the geological description of the DFN (GeoDFN) with the hydraulic test data from Posiva Flow-Log and Pipe-String System double-packer techniques to produce a conditioned Hydro-DFN model. This was done in a systematic way that addressed uncertainties associated with the assumptions made in interpreting the data, such as the relationship between fracture transmissivity and length. Consistent hydraulic data was only available for three boreholes, and therefore only relatively simplistic models were proposed as there isn't sufficient data to justify extrapolating the DFN away from the boreholes based on rock domain, for example. Significantly, a far greater quantity of hydro-geochemical data was available for calibration in the

  14. Preliminary reactive geochemical transport simulation study on CO2 geological sequestration at the Changhua Coastal Industrial Park Site, Taiwan

    Science.gov (United States)

    Sung, R.; Li, M.

    2013-12-01

    Mineral trapping by precipitated carbonate minerals is one of critical mechanisms for successful long-term geological sequestration (CGS) in deep saline aquifer. Aquifer acidification induced by the increase of carbonic acid (H2CO3) and bicarbonate ions (HCO3-) as the dissolution of injected CO2 may induce the dissolution of minerals and hinder the effectiveness of cap rock causing potential risk of CO2 leakage. Numerical assessments require capabilities to simulate complicated interactions of thermal, hydrological, geochemical multiphase processes. In this study, we utilized TOUGHREACT model to demonstrate a series of CGS simulations and assessments of (1) time evolution of aquifer responses, (2) migration distance and spatial distribution of CO2 plume, (3) effects of CO2-saline-mineral interactions, and (4) CO2 trapping components at the Changhua Costal Industrial Park (CCIP) Site, Taiwan. The CCIP Site is located at the Southern Taishi Basin with sloping and layered heterogeneous formations. At this preliminary phase, detailed information of mineralogical composition of reservoir formation and chemical composition of formation water are difficult to obtain. Mineralogical composition of sedimentary rocks and chemical compositions of formation water for CGS in deep saline aquifer from literatures (e.g. Xu et al., 2004; Marini, 2006) were adopted. CGS simulations were assumed with a constant CO2 injection rate of 1 Mt/yr at the first 50 years. Hydrogeological settings included porosities of 0.103 for shale, 0.141 for interbedding sandstone and shale, and 0.179 for sandstone; initial pore pressure distributions of 24.5 MPa to 28.7 MPa, an ambient temperature of 70°C, and 0.5 M of NaCl in aqueous solution. Mineral compositions were modified from Xu et al. (2006) to include calcite (1.9 vol. % of solid), quartz (57.9 %), kaolinite (2.0 %), illite (1.0 %), oligoclase (19.8 %), Na-smectite (3.9 %), K-feldspar (8.2 %), chlorite (4.6 %), and hematite (0.5 %) and were

  15. PRELIMINARY DATA REPORT: HUMATE INJECTION AS AN ENHANCED ATTENUATION METHOD AT THE F-AREA SEEPAGE BASINS, SAVANNAH RIVER SITE

    Energy Technology Data Exchange (ETDEWEB)

    Millings, M.

    2013-09-16

    A field test of a humate technology for uranium and I-129 remediation was conducted at the F-Area Field Research Site as part of the Attenuation-Based Remedies for the Subsurface Applied Field Research Initiative (ABRS AFRI) funded by the DOE Office of Soil and Groundwater Remediation. Previous studies have shown that humic acid sorbed to sediments strongly binds uranium at mildly acidic pH and potentially binds iodine-129 (I-129). Use of humate could be applicable for contaminant stabilization at a wide variety of DOE sites however pilot field-scale tests and optimization of this technology are required to move this technical approach from basic science to actual field deployment and regulatory acceptance. The groundwater plume at the F-Area Field Research Site contains a large number of contaminants, the most important from a risk perspective being strontium-90 (Sr-90), uranium isotopes, I-129, tritium, and nitrate. Groundwater remains acidic, with pH as low as 3.2 near the basins and increasing to the background pH of approximately 5at the plume fringes. The field test was conducted in monitoring well FOB 16D, which historically has shown low pH and elevated concentrations of Sr-90, uranium, I-129 and tritium. The field test included three months of baseline monitoring followed by injection of a potassium humate solution and approximately four and half months of post monitoring. Samples were collected and analyzed for numerous constituents but the focus was on attenuation of uranium, Sr-90, and I-129. This report provides background information, methodology, and preliminary field results for a humate field test. Results from the field monitoring show that most of the excess humate (i.e., humate that did not sorb to the sediments) has flushed through the surrounding formation. Furthermore, the data indicate that the test was successful in loading a band of sediment surrounding the injection point to a point where pH could return to near normal during the study

  16. Boundary conditions for pathways, safety analysis and basic criteria for low-level radiation waste site selection

    International Nuclear Information System (INIS)

    Saverot, P.

    1994-01-01

    There are three successive periods in the life of a disposal facility: the operating period, the institutional control period and the unrestricted site access period. The purpose of safety analysis of the disposal facility is to ensure that the radiological impacts for each period in the life of the facility are acceptable under all circumstances. Founded on a deterministic approach, this analysis leads to a determination of the maximum quantity of each radionuclide present in the facility at the beginning of the institutional control period in order for the impacts to be considered acceptable. Safety analysis involves the calculation of the radiological impacts of a given radiological inventory under a selected scenario, from all plausible scenarios of radionuclide migration to the environment in both normal and accident conditions, and taking into account other specified variables. The calculation itself involves an assessment of the quantities of radionuclides that could be released to the environment under the specific scenario selected and following identified pathways, and a determination of the resultant exposure, both internal and external, to the public. An iterative approach is used in the performance of pathways analyses. If the pathways analyses result in unacceptable radiological impacts, either the radiological inventory of the site is reduced or barrier characteristics not previously factored into the analysis are taken into account. New pathways analyses are then performed until the results are within the acceptable range. Once accepted by the safety authorities, the radiological inventory becomes the radiological capacity, which is the approved quantities of specific radionuclides that may be disposed of at the site. The following elaborates on the boundary conditions used in safety analyses and describes the types of pathways analyses performed for a LLW disposal facility

  17. Using the Multi-Criteria AHP for the Optimal Selection of Site Location and Wastewater Collection System The Case Study of Varzeghan

    Directory of Open Access Journals (Sweden)

    Hassan talebi

    2015-11-01

    Full Text Available This study investigates the use of multi-criteria decision making in waste management and selection of the site location and proper wastewater collection and processing system in Varzeqan Town. Moreover, the effect of the decision-making method employed on ranking the final alternatives will be evaluated. Different factors are involved in the selection of wastewater treatment construction sites. These factors, in turn, not only depend on the special location and time the decision is made but also have their own weights in the final decision. In this study, the environmental conditions in the study area are initially investigated to select one site from among five different alternatives proposed for the construction of the facility using the AHP method. Also, the AHP method is used to evaluate and select the suitable collection and treatment method from among the four non-conventional options including Septic Tank Effluent Gravity, Septic Tank Effluent Pressure, Vacuum Sewerage System, and Simplified Sewerage for this region based on the special geographical and geotechnical conditions. The results indicate that the barren lands between Varzeghan Town and Dizaj Safar Ali Village are the best site for constructing the treatment facility and that the simplified sewarge system is the best collection system for the region.

  18. Solid Waste Management in Greater Shillong Planning Area (GSPA) Using Spatial Multi-Criteria Decision Analysis for Site Suitability Assessment

    Science.gov (United States)

    Mipun, B. S.; Hazarika, R.; Mondal, M.; Mukhopadhyay, S.

    2015-04-01

    In Shillong city the existing solid waste management system is mobile waste bins (72%). About 12 percent burn the waste generated by them. Door to door collection is about 5 percent. Over 2 percent households throw the wastes in the open space. Another 9 percent households throw their wastes into the waste bins located in the neighbourhood. The local headman takes care about half of the household's wastes, while Municipality takes care about 34 percent households. About 10 percent households are ignorant about the collection and disposal of wastes. Some NGO's takes care about 5 percent household's wastes. Awareness about segregation of waste into organic and non-bio degradable waste is 64 percent and a significant numbers do the segregation. In Shillong Municipality Board (SMB) area collects 45.91% (78.42 MT) waste, outside SMB area collection is 32.61% (45.99 MT) and entire GSPA the percentage of garbage collected is 41percent. The only dumping ground in GSPA is Marten, Mawiong, and the capacity to hold garbage is decreasing due to limited landfill. The sanitary landfill site is 5.0 acres that it is not enough to meet the demand. Out of he total area 170.69 sq. km. (GSPA) only 25.67% is most suitable and 18.58% is unsuitable to set up a new landfill area. Eastern part of the GSPA, is most suitable, which fulfils the entire criterion adopted in this study. In this the best-stated criterion are land cover (vacant space), slope (2000m) and elevation (1300-1500m). The eastern part of the GSPA is most suitable landfill location.

  19. The representation of patient experience and satisfaction in physician rating sites. A criteria-based analysis of English- and German-language sites

    Directory of Open Access Journals (Sweden)

    Strech Daniel

    2010-12-01

    Full Text Available Abstract Background Information on patient experience and satisfaction with individual physicians could play an important role for performance measures, improved health care and health literacy. Physician rating sites (PRSs bear the potential to be a widely available source for this kind of information. However, patient experience and satisfaction are complex constructs operationalized by multiple dimensions. The way in which PRSs allow users to express and rate patient experience and satisfaction could likely influence the image of doctors in society and the self-understanding of both doctors and patients. This study examines the extent to which PRSs currently represent the constructs of patient experience and satisfaction. Methods First, a systematic review of research instruments for measuring patient experience and satisfaction was conducted. The content of these instruments was analyzed qualitatively to create a comprehensive set of dimensions for patient experience and patient satisfaction. Second, PRSs were searched for systematically in English-language and German-language search engines of Google and Yahoo. Finally, we classified every structured question asked by the different PRS using the set of dimensions of patient experience and satisfaction. Results The qualitative content analysis of the measurement instruments produced 13 dimensions of patient experience and satisfaction. We identified a total of 21 PRSs. No PRSs represented all 13 dimensions of patient satisfaction and experience with its structured questions. The 3 most trafficked English-language PRS represent between 5 and 6 dimensions and the 3 most trafficked German language PRSs between 8 and 11 dimensions The dimensions for patient experience and satisfaction most frequently represented in PRSs included diversely operationalized ones such as professional competence and doctor-patient relationship/support. However, other less complex but nevertheless important dimensions

  20. Toxicity of ammonia, cadmium, and nitrobenzene to four local fishes in the Liao River, China and the derivation of site-specific water quality criteria.

    Science.gov (United States)

    Liu, Zhihong; Li, Xiaojun; Tai, Peidong; Sun, Lizong; Yuan, Honghong; Yang, Xiaonan

    2018-01-01

    Water quality criteria (WQC) are considered to be an effective management tool for protecting aquatic environments. To derive site-specific WQC for an area, local data based on local species are essential to improve the applicability of WQC derived. Due to the paucity of local fish data available for the development of site-specific WQC for the Liao River, China, four local and widespread fishes (Pseudorasbora parva, Abbottina liaoningensis, Ctenogobius giurinus, and Misgurnus anguillicaudatus) were chosen to test their sensitivities to ammonia, cadmium and nitrobenzene. These compounds are common and regularly-measured pollutants in Chinese rivers. In addition to the published data for species resident in the Liao River, site-specific WQC for the three chemicals were derived using both a log-logistic species sensitivity distribution (SSD) and the method recommended by the USEPA, in line with current best practice, which were then compared with Chinese national WQC. It was found that A. liaoningensis was the most sensitive, followed, in order, by P. parva, C. giurinus and M. anguillicaudatus was the least sensitive, and this trend was the same to all three chemicals tested. When comparing the SSD derived solely from previously-published data with that including our data on local fish, there were significant differences identified among parameters describing the SSD curves for ammonia and nitrobenzene and significant differences were detected for site-specific WQC derived for all of the three chemicals. Based on the dataset with local fish data taxa, site-specific WQC of Liao River for ammonia, cadmium, and nitrobenzene were derived to be 20.53mg/L (at a pH of 7.0 and temperature of 20°C), 3.76μg/L (at a hardness of 100mg/L CaCO 3 ), and 0.49mg/L, respectively. Using the same deriving method for each chemical, the national Chinese WQC were higher than site-specific WQC derived in this study for ammonia (national WQC of 25.16mg/L) and nitrobenzene (national WQC

  1. Proceedings of the twenty-fourth water reactor safety information meeting. Volume 3: PRA and HRA; Probabilistic seismic hazard assessment and seismic siting criteria

    International Nuclear Information System (INIS)

    Monteleone, S.

    1997-02-01

    This three-volume report contains papers presented at the Twenty-Fourth Water Reactor Safety Information Meeting held at the Bethesda Marriott Hotel, Bethesda, Maryland, October 21--23, 1996. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included papers presented by researchers from Czech Republic, Finland, France, Japan, Norway, Russia and United Kingdom. This volume is divided into the following sections: PRA and HRA and probabilistic seismic hazard assessment and seismic siting criteria. Selected papers are indexed separately for inclusion in the Energy Science and Technology Database

  2. Proceedings of the twenty-fourth water reactor safety information meeting. Volume 3: PRA and HRA; Probabilistic seismic hazard assessment and seismic siting criteria

    Energy Technology Data Exchange (ETDEWEB)

    Monteleone, S. [comp.] [Brookhaven National Lab., Upton, NY (United States)

    1997-02-01

    This three-volume report contains papers presented at the Twenty-Fourth Water Reactor Safety Information Meeting held at the Bethesda Marriott Hotel, Bethesda, Maryland, October 21--23, 1996. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included papers presented by researchers from Czech Republic, Finland, France, Japan, Norway, Russia and United Kingdom. This volume is divided into the following sections: PRA and HRA and probabilistic seismic hazard assessment and seismic siting criteria. Selected papers are indexed separately for inclusion in the Energy Science and Technology Database.

  3. Manual for calculating critical loads of heavy metals for soils and surface waters; preliminary guidelines for environmental quality criteria, calculation methods and input data

    NARCIS (Netherlands)

    Vries, de W.; Bakker, D.J.

    1996-01-01

    Methodologies are described for calculating critical loads of lead, cadmium, copper, zinc, nickel, chromium and mercury for soils and surface waters. The aspects which are discussed are: selection of a computation model, determination of environmental-quality criteria for the metals, collection of

  4. Diagnostics of Sacroiliitis According to ASAS Criteria: A Comparative Evaluation of Conventional Radiographs and MRI in Patients with a Clinical Suspicion of Spondyloarthropathy. Preliminary Results

    International Nuclear Information System (INIS)

    Sudoł-Szopińska, Iwona; Kwiatkowska, Brygida; Włodkowska-Korytkowska, Monika; Matuszewska, Genowefa; Grochowska, Elżbieta

    2015-01-01

    The objective of this study was a comparative evaluation of radiography and MRI in the diagnostics of sacroiliitis in patients with a clinical diagnosis of spondyloartropathy, according to the current ASAS criteria. Sacroiliac joints radiograms and MRI were conducted in 101 consecutive patients, aged 19–71 yrs (mean age: 40.6 yrs). The patients were referred by a senior rheumatologist, with symptoms of the chronic back pain. The sacroiliac joints were assessed on AP radiograms of the pelvis according to the modified New York criteria for ankylosing spondylitis. MRI was performed to look for active and chronic inflammatory lesions. Of 14 patients with radiographic sacroiliitis according to modified New York criteria, only 50% had sacroiliitis on MRI. The sensitivity and specificity of conventional radiography were 22% and 94% and of MRI were 71% and 90%. Cohen’s kappa coefficient was κ=0.0187, agreement of radiograms and MRI was 58%. Among 86 patients displaying no sacroiliitis on radiograms, MRI showed sacroiliitis in 34 patients (39.5%). Positive predictive value was 0.429, negative predictive value was 0.605. MRI allowed to diagnose sacroiliitis in 39,5 % of patients in preradiographic stage. MRI ruled out the presence of active inflammatory lesions in 60.4% of patients with sacroiliitis on radiograms according to modified New York criteria

  5. Expression, purification, crystallization and preliminary X-ray analysis of wild-type and of an active-site mutant of glyceraldehyde-3-phosphate dehydrogenase from Campylobacter jejuni

    International Nuclear Information System (INIS)

    Tourigny, David S.; Elliott, Paul R.; Edgell, Louise J.; Hudson, Gregg M.; Moody, Peter C. E.

    2010-01-01

    The cloning, expression, purification, crystallization and preliminary X-ray analysis of wild-type and of an active-site mutant of C. jejuni glyceraldehyde-3-phosphate dehydrogenase is reported. The genome of the enteric pathogen Campylobacter jejuni encodes a single glyceraldehyde-3-phosphate dehydrogenase that can utilize either NADP + or NAD + as coenzymes for the oxidative phosphorylation of glyceraldehyde-3-phosphate to 1,3-diphosphoglycerate. Here, the cloning, expression, purification, crystallization and preliminary X-ray analysis of both the wild type and an active-site mutant of the enzyme are presented. Preliminary X-ray analysis revealed that in both cases the crystals diffracted to beyond 1.9 Å resolution. The space group is shown to be I4 1 22, with unit-cell parameters a = 90.75, b = 90.75, c = 225.48 Å, α = 90.46, β = 90.46, γ = 222.79°; each asymmetric unit contains only one subunit of the tetrameric enzyme

  6. Hydroelectric generating site signage

    Energy Technology Data Exchange (ETDEWEB)

    Bentley, K [British Columbia Hydro, Vancouver, BC (Canada)

    1997-04-01

    Recreational sites have been developed at several BC Hydro reservoirs. These sites are visited by approximately 800,000 people annually and therefore, require consistent control measures to ensure public safety and to restrict public access to hazardous areas. BC Hydro is in the process of establishing a province-wide standard in which layout, colour, description of hazards, BC Hydro identity and sign placement would follow an established set of criteria. Proposed signs would consist of a pictograph and a printed warning below. Preliminary designs for 16 of the signs were presented. 16 figs.

  7. Management and Data Management Plan for Remedial Investigation at Fort George G. Meade Landfill and Preliminary Assessment/Site Investigation at the Former Gaithersburg NIKE Control and Launch Areas

    National Research Council Canada - National Science Library

    Edwards, D

    1989-01-01

    Work assignments under this contract will include a Preliminary Assessment/Site Investigation at the former Gaithersburg NIKE Control and Launch Areas and a Remedial Investigation at the Fort Meade...

  8. Preliminary evaluation of the use of the greater confinement disposal concept for the disposal of Fernald 11e(2) byproduct material at the Nevada Test Site

    International Nuclear Information System (INIS)

    Cochran, J.R.; Brown, T.J.; Stockman, H.W.; Gallegos, D.P.; Conrad, S.H.; Price, L.L.

    1997-09-01

    This report documents a preliminary evaluation of the ability of the greater confinement disposal boreholes at the Nevada Test Site to provide long-term isolation of radionuclides from the disposal of vitrified byproduct material. The byproduct material is essentially concentrated residue from processing uranium ore that contains a complex mixture of radionuclides, many of which are long-lived and present in concentrations greater than 100,000 picoCuries per gram. This material has been stored in three silos at the fernald Environmental Management Project since the early 1950s and will be vitrified into 6,000 yd 3 (4,580 m 3 ) of glass gems prior to disposal. This report documents Sandia National Laboratories' preliminary evaluation for disposal of the byproduct material and includes: the selection of quantitative performance objectives; a conceptual model of the disposal system and the waste; results of the modeling; identified issues, and activities necessary to complete a full performance assessment

  9. Storage of radioactive wastes in geological formations. Technical criteria for site selection. Report by the work-group chaired by Professor Goguel

    International Nuclear Information System (INIS)

    Goguel, Jean; Candes, Pierre; Izabel, Cecile; Autran, Albert; Barthoux, Alain; Baudin, Guy; Devillers, Christian; Habib, Pierre; Lafuma, Jacques; Lefevre, Jean; Peaudecerf, Pierre; Pradel, Jacques; Salle, Claude; Treuil, Michel; Lebrun, Patrick; Tissier, Marie-Solange

    1985-06-01

    This document is the result of a prospective mission on the long term storage of radioactive wastes containing long-period emitters (wastes of B and C categories), and notably on a definitive storage in deep continental geological formations. After a presentation of hypotheses (brief description of the storage concept, main safety principles, objectives in terms of radiological safety, safety options, time-related considerations), the authors addressed the following issues: safety before closing during the exploitation period, and safety after closure (after backfilling and sealing of all underground cavities). For the first issue, they discuss the impacts of works on safety and thermal effects during exploitation. For the second issue, they discuss the site natural hydro-geological context, the disturbances brought by the storage (access of water to the storage, and return of water into the biosphere), and the influence of external factors (geological phenomena, human intrusion). Then, the authors make recommendations regarding reconnaissance programs and studies for the selection and qualification of a site. They finally propose technical criteria and main recommendations for site selection. Appendices propose a list of hearings, a presentation of the storage concept, a report on the impact of works, a report on the presence of mineralisation in granite massifs, reports on radiological consequences of intrusions in salt formations and in granite massif containing storage of radioactive wastes or vitrified wastes, a report on the characterization of unsteady parts of the French continental construction, a presentation of the evolution of climate and icings, and a study of seismic movements in the case of deep storages

  10. Verification study on technology for preliminary investigation for HLW geological disposal. Part 2. Verification of surface geophysical prospecting through establishing site descriptive models

    International Nuclear Information System (INIS)

    Kondo, Hirofumi; Suzuki, Koichi; Hasegawa, Takuma; Goto, Keiichiro; Yoshimura, Kimitaka; Muramoto, Shigenori

    2012-01-01

    The Yokosuka demonstration and validation project using Yokosuka CRIEPI site has been conducted since FY 2006 as a cooperative research between NUMO (Nuclear Waste Management Organization of Japan) and CRIEPI. The objectives of this project are to examine and to refine the basic methodology of the investigation and assessment of properties of geological environment in the stage of Preliminary Investigation for HLW geological disposal. Within Preliminary Investigation technologies, surface geophysical prospecting is an important means of obtaining information from deep geological environment for planning borehole surveys. In FY 2010, both seismic prospecting (seismic reflection and vertical seismic profiling methods) for obtaining information about geological structure and electromagnetic prospecting (magneto-telluric and time domain electromagnetic methods) for obtaining information about resistivity structure reflecting the distribution of salt water/fresh water boundary to a depth of over several hundred meters were conducted in the Yokosuka CRIEPI site. Through these surveys, the contribution of geophysical prospecting methods in the surface survey stage to improving the reliability of site descriptive models was confirmed. (author)

  11. Remedial action plan and site design for stabilization of the inactive uranium mill tailings sites at Slick Rock, Colorado. Attachment 3, Ground water hydrology report: Preliminary final

    Energy Technology Data Exchange (ETDEWEB)

    1994-03-04

    The US Environmental Protection Agency (EPA) has established health and environmental protection regulations to correct and prevent ground water contamination resulting from processing activities at inactive uranium milling sites (52 FR 36000 (1987)). According to the Uranium Mill Tailings Radiation Control Act (UMTRCA) of 1978, 42 USC {section}7901 et seq., the US Department of Energy (DOE) is responsible for assessing the inactive uranium processing sites. The DOE has determined that for Slick Rock, this assessment shall include hydrogeologic site characterization for two separate uranium processing sites, the Union Carbide (UC) site and the North Continent (NC) site, and for the proposed Burro Canyon disposal site. The water resources protection strategy that describes how the proposed action will comply with the EPA ground water protection standards is presented in Attachment 4. The following site characterization activities are discussed in this attachment: Characterization of the hydrogeologic environment, including hydrostratigraphy, ground water occurrence, aquifer parameters, and areas of recharge and discharge. Characterization of existing ground water quality by comparison with background water quality and the maximum concentration limits (MCL) of the proposed EPA ground water protection standards. Definition of physical and chemical characteristics of the potential contaminant source, including concentration and leachability of the source in relation to migration in ground water and hydraulically connected surface water. Description of local water resources, including current and future use, availability, and alternative supplies.

  12. Comparison of two threshold detection criteria methodologies for determination of probe positivity for intraoperative in situ identification of presumed abnormal 18F-FDG-avid tissue sites during radioguided oncologic surgery.

    Science.gov (United States)

    Chapman, Gregg J; Povoski, Stephen P; Hall, Nathan C; Murrey, Douglas A; Lee, Robert; Martin, Edward W

    2014-09-13

    Intraoperative in situ identification of (18)F-FDG-avid tissue sites during radioguided oncologic surgery remains a significant challenge for surgeons. The purpose of our study was to evaluate the 1.5-to-1 ratiometric threshold criteria method versus the three-sigma statistical threshold criteria method for determination of gamma detection probe positivity for intraoperative in situ identification of presumed abnormal (18)F-FDG-avid tissue sites in a manner that was independent of the specific type of gamma detection probe used. From among 52 patients undergoing appropriate in situ evaluation of presumed abnormal (18)F-FDG-avid tissue sites during (18)F-FDG-directed surgery using 6 available gamma detection probe systems, a total of 401 intraoperative gamma detection probe measurement sets of in situ counts per second measurements were cumulatively taken. For the 401 intraoperative gamma detection probe measurement sets, probe positivity was successfully met by the 1.5-to-1 ratiometric threshold criteria method in 150/401 instances (37.4%) and by the three-sigma statistical threshold criteria method in 259/401 instances (64.6%) (P < 0.001). Likewise, the three-sigma statistical threshold criteria method detected true positive results at target-to-background ratios much lower than the 1.5-to-1 target-to-background ratio of the 1.5-to-1 ratiometric threshold criteria method. The three-sigma statistical threshold criteria method was significantly better than the 1.5-to-1 ratiometric threshold criteria method for determination of gamma detection probe positivity for intraoperative in situ detection of presumed abnormal (18)F-FDG-avid tissue sites during radioguided oncologic surgery. This finding may be extremely important for reshaping the ongoing and future research and development of gamma detection probe systems that are necessary for optimizing the in situ detection of radioisotopes of higher-energy gamma photon emissions used during radioguided oncologic surgery.

  13. Analysis and evaluation of the Gorleben site characteristics. Report on the working package 2. Preliminary safety analysis Gorleben

    International Nuclear Information System (INIS)

    Kukla, Peter; Pechnig, Renate; Urai, Janos

    2011-10-01

    The report on analysis and evaluation of the Gorleben site characteristics covers the following chapters: Site characteristics on the hydrology of the cover rock: hydrology and hydraulic properties, geothermal studies, ground water properties and motion, model calculations. Site characteristics on geology of the cover and adjoining rock: borehole explorations, geologic development, 3D geometry of the salt dome Gorleben, geologic development of the salt structure Gorleben. Site characteristics on the saliniferous formation: geophysical exploration, modeling of the internal structure of the salt dome Gorleben, fluids in the salt dome Gorleben. Geotechnical studies at the site: geothermal studies, hydraulic data on the saliniferous formation, thermal model calculations, geomechanical in-situ measurements, mechanical and transport properties, thermo-mechanical modeling. Summarized evaluation of the site characteristics and further research requirement.

  14. Preliminary site description Laxemar stage 2.1. Feedback for completion of the site investigation including input from safety assessment and repository engineering

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-09-15

    The Laxemar subarea is the focus for the complete site investigations in the Simpevarp area. The south and southwestern parts of the subarea (the so-called 'focused area') have been designated for focused studies during the remainder of the site investigations. This area, some 5.3 square kilometres in size, is characterised on the surface by an arc shaped body of quartz monzodiorite gently dipping to the north, flanked in the north and south by Aevroe granite. The current report documents work conducted during stage 2.1 of the site-descriptive modelling of the Laxemar subarea. The primary objective of the work performed is to provide feedback to the site investigations at Laxemar to ensure that adequate and timely data and information are obtained during the remaining investigation stage. The work has been conducted in cooperation with the site investigation team at Laxemar and representatives from safety assessment and repository engineering. The principal aim of this joint effort has been to safeguard that adequate data are collected that resolve the remaining issues/uncertainties which are of importance for repository layout and long-term safety. The proposed additional works presented in this report should be regarded as recommended additions and/or modifications in relation to the CSI programme published early 2006. The overall conclusion of the discipline-wise review of critical issues is that the CSI programme overall satisfies the demands to resolve the remaining uncertainties. This is interpreted to be partly a result of the close interaction between the site modelling team, site investigation team and the repository engineering teams, which has been in operation since early 2005. In summary, the performed interpretations and modelling have overall confirmed the version 1.2 results. The exception being Hydrogeology where the new Laxemar 2.1 borehole data suggest more favourable conditions in the south and west parts of the focused area compared

  15. Preliminary site description Laxemar stage 2.1. Feedback for completion of the site investigation including input from safety assessment and repository engineering

    International Nuclear Information System (INIS)

    2006-09-01

    The Laxemar subarea is the focus for the complete site investigations in the Simpevarp area. The south and southwestern parts of the subarea (the so-called 'focused area') have been designated for focused studies during the remainder of the site investigations. This area, some 5.3 square kilometres in size, is characterised on the surface by an arc shaped body of quartz monzodiorite gently dipping to the north, flanked in the north and south by Aevroe granite. The current report documents work conducted during stage 2.1 of the site-descriptive modelling of the Laxemar subarea. The primary objective of the work performed is to provide feedback to the site investigations at Laxemar to ensure that adequate and timely data and information are obtained during the remaining investigation stage. The work has been conducted in cooperation with the site investigation team at Laxemar and representatives from safety assessment and repository engineering. The principal aim of this joint effort has been to safeguard that adequate data are collected that resolve the remaining issues/uncertainties which are of importance for repository layout and long-term safety. The proposed additional works presented in this report should be regarded as recommended additions and/or modifications in relation to the CSI programme published early 2006. The overall conclusion of the discipline-wise review of critical issues is that the CSI programme overall satisfies the demands to resolve the remaining uncertainties. This is interpreted to be partly a result of the close interaction between the site modelling team, site investigation team and the repository engineering teams, which has been in operation since early 2005. In summary, the performed interpretations and modelling have overall confirmed the version 1.2 results. The exception being Hydrogeology where the new Laxemar 2.1 borehole data suggest more favourable conditions in the south and west parts of the focused area compared with the

  16. Site study plan for Upper Aquifer Hydrology Clusters, Deaf Smith County Site, Texas: Surface-based geotechnical field program: Preliminary draft

    International Nuclear Information System (INIS)

    1988-01-01

    As part of site characterization studies, at the Deaf Smith County site, Texas, 15 wells at 5 locations will be completed in the Ogallala Formation and Dockum Group. The purposes of the wells, which are called Upper Aquifer (2) establish background hydrologic and water quality conditions, (3) provide analysis, (4) monitor responses of the shallow hydrologic system to site activities and nearby pumpage for irrigation, (5) collect water samples from both saturated and unsaturated materials to help define recharge rates and ground-water flow patterns, (6) monitor variations on water quality, and (7) define ground-water resources near the site. The test wells will be installed during a 14-month period starting about 1-1/2 years after site characterization activities begin. The Technical Field Services Contractor is responsible for conducting the field program of drilling and testing. Samples and data will be handled and reported in accordance with established Salt Repository Project procedures. A quality assurance program will assure that activities affecting quality are performed correctly and that the appropriate documentation is maintained. 44 refs., 19 figs., 5 tabs

  17. Plutonium storage criteria

    Energy Technology Data Exchange (ETDEWEB)

    Chung, D. [Scientech, Inc., Germantown, MD (United States); Ascanio, X. [Dept. of Energy, Germantown, MD (United States)

    1996-05-01

    The Department of Energy has issued a technical standard for long-term (>50 years) storage and will soon issue a criteria document for interim (<20 years) storage of plutonium materials. The long-term technical standard, {open_quotes}Criteria for Safe Storage of Plutonium Metals and Oxides,{close_quotes} addresses the requirements for storing metals and oxides with greater than 50 wt % plutonium. It calls for a standardized package that meets both off-site transportation requirements, as well as remote handling requirements from future storage facilities. The interim criteria document, {open_quotes}Criteria for Interim Safe Storage of Plutonium-Bearing Solid Materials{close_quotes}, addresses requirements for storing materials with less than 50 wt% plutonium. The interim criteria document assumes the materials will be stored on existing sites, and existing facilities and equipment will be used for repackaging to improve the margin of safety.

  18. An alternative method to record rising temperatures during dental implant site preparation: a preliminary study using bovine bone

    Directory of Open Access Journals (Sweden)

    Domenica Laurito

    2010-12-01

    Full Text Available Overheating is constantly mentioned as a risk factor for bone necrosis that could compromise the dental implant primary stability. Uncontrolled thermal injury can result in a fibrous tissue, interpositioned at the implant-bone interface, compromising the long-term prognosis. The methods used to record temperature rise include either direct recording by thermocouple instruments or indirect estimating by infrared thermography. This preliminary study was carried out using bovine bone and a different method of temperatures rising estimation is presented. Two different types of drills were tested using fluoroptic thermometer and the effectiveness of this alternative temperature recording method was evaluated.

  19. Preliminary evaluation of licensing issues associated with U.S.-sited CANDU-PHW nuclear power plants

    International Nuclear Information System (INIS)

    van Erp, J.B.

    1977-12-01

    The principal safety-related characteristics of current CANDU-PHW power plants are described, and a distinction between those characteristics which are intrinsic to the CANDU-PHW system and those that are not is presented. An outline is given of the main features of the Canadian safety and licensing approach. Differences between the U.S. and Canadian approach to safety and licensing are discussed. Some of the main results of the safety analyses, routinely performed for CANDU-PHW reactors, are presented. U.S.-NRC General Design Criteria are evaluated as regards their applicability to CANDU-PHW reactors; vice-versa the CANDU-PHW reactor is evaluated with respect to its conformance to the U.S.-NRC General Design Criteria. A number of design modifications are proposed to be incorporated into the CANDU-PHW reactor in order to facilitate its introduction into the U.S

  20. Site selection experience for a new low-level radioactive waste storage/disposal facility at the Savannah River Plant

    International Nuclear Information System (INIS)

    Towler, O.A.; Cook, J.R.; Helton, B.D.

    1985-10-01

    Preliminary performance criteria and site selection guides specific to the Savannah River Plant, were developed for a new low-level radioactive waste storage/disposal facility. These site selection guides were applied to seventeen potential sites identified at SRP. The potential site were ranked based on how well they met a set of characteristics considered important in site selection for a low-level radioactive waste disposal facility. The characteristics were given a weighting factor representing its relative importance in meeting site performance criteria. A candidate site was selected and will be the subject of a site characterization program

  1. MX Siting Investigation. Preliminary Biological and Cultural Resources Inventory and Environmental Evaluation of the Proposed Operational Base Sites in Coyote Spring Valley and the Milford-Beryl Area.

    Science.gov (United States)

    1981-03-20

    Stanleya pinriata (desert prince- plume) Stanleya sp. X CACTACEAE Echinocereus engelmannii (Engel- X X X X X X mann echinocereus) Ferocactus acanthodes...TABLE 3-3 (Cont.) Site Number Species 1 2 3 4 5 6 7 8 9 CACTACEAE (Cont.) Ferocactus sp X X X X *Neolloydia sp. X *-Opuntia basilaris (beavertail X X

  2. Health assessment for Newcastle Abandoned Container Site, Newcastle, Delaware, Region 3. CERCLIS No. DED058980442. Preliminary report

    International Nuclear Information System (INIS)

    1988-01-01

    The Newcastle Abandoned Container site is listed on the National Priorities List. On February 28, 1986, radioactive, corrosive, and toxic materials, and a large number of containers filled with unknown material, were inventoried, containerized, and removed. On-site contamination consists of polychlorinated biphenyls, trichloroethylene, creosote, chloroform, and di-n-butylphthalate in soil; and tetrachloroethylene, acetone, xylene, trichlorofluoromethane, trichloroethylene, and tris(betachloroisopropyl)phosphate in groundwater. The site is considered to be of potential public health concern because of the risk to human health caused by the possibility of exposure to hazardous substances via groundwater. The potential for contamination of the lower aquifer should be investigated

  3. Preliminary assessment of nuclear waste transportation cost and risk for operation of the first repository at candidate sites

    International Nuclear Information System (INIS)

    Peterson, R.W.; McSweeney, T.I.; Varadarajan, R.V.; Wilmot, E.L.; Cashwell, J.W.; Joy, D.S.

    1983-01-01

    To support the selection of the first commercial nuclear waste repository site in 1987, environmental analyses of five candidate site locations are currently being performed. The five locations are in the Gulf Interior Region, the Permian Basin, the Paradox Basin, Yucca Mountain and the Hanford reservation. Costs and operational risks associated with the transportation of nuclear wastes to a single repository located in these regions have been calculated for a life-cycle of 26 years

  4. Remedial action plan and site design for stabilization of the inactive uranium mill tailings sites at Slick Rock, Colorado: Remedial Action Selection Report. Preliminary final

    Energy Technology Data Exchange (ETDEWEB)

    1994-03-01

    This proposed remedial action plan incorporates the results of detailed investigation of geologic, geomorphic, and seismic conditions at the proposed disposal site. The proposed remedial action will consist of relocating the uranium mill tailings, contaminated vicinity property materials, demolition debris, and windblown/waterborne materials to a permanent repository at the proposed Burro Canyon disposal cell. The proposed disposal site will be geomorphically stable. Seismic design parameters were developed for the geotechnical analyses of the proposed cell. Cell stability was analyzed to ensure long-term performance of the disposal cell in meeting design standards, including slope stability, settlement, and liquefaction potential. The proposed cell cover and erosion protection features were also analyzed and designed to protect the RRM (residual radioactive materials) against surface water and wind erosion. The location of the proposed cell precludes the need for permanent drainage or interceptor ditches. Rock to be used on the cell top-, side-, and toeslopes was sized to withstand probable maximum precipitation events.

  5. Use of site specific data from Aespoe - preliminary results from the on-going safety analysis SR 97

    International Nuclear Information System (INIS)

    Stroem, A.; Selroos, J.O.; Andersson, Johan

    1998-01-01

    This paper discusses an on-going safety assessment study of SKB as well as the use of field data from Aespoe for obtaining input parameters for flow and radionuclide transport modelling in the geosphere. In the on-going Safety Assessment study SR 97, three individual sites in Sweden are used for exemplifying site specific conditions on overall repository performance. Thus, models capable of reproducing site specific characteristics are utilised. This is primarily obtained by implementing the geologic structural models in suitable conceptual models for groundwater flow on both regional and local scales. The models for flow incorporate observed and/or inferred water conducting features as well as other site-specific characteristics necessary for realistic descriptions of flow at the sites. The flow modelling thus aims at realism; the results obtained for present day conditions should not in any serious aspect conflict with observations at the site. Agreement between observed and modelled entities provides confidence in that a sound understanding of the site is obtained. Aespoe is one of the three sites providing site-specific conditions in SR 97. Transport is subsequently modelled using a stream tube approach where the 'travel times', for non-sorbing species, and discharge locations of a set of one-dimensional stream tubes are obtained from particle tracking in the flow model. The resulting distribution of 'travel times' in a single model realisation reflects the spatial variability and spatial extent of the repository, whereas the ensemble travel time distribution (over several realisations) for a given canister location reflects the uncertainty in travel time. The actual transport paths used in the transport modelling are thus dependent on site specific information such as e.g. existence of water conductive features. Other input parameters to the transport model are based on more generic and/or conservative arguments. However, the goal in a safety assessment

  6. Site study plan for Exploratory shaft facilities design foundation boreholes (shaft surface facility foundation borings), Deaf Smith County Site, Texas: Surface-based geotechnical field program: Preliminary draft

    International Nuclear Information System (INIS)

    1987-12-01

    This site study plan describes the Exploratory Shaft Facilities (ESF) Design Foundation Boreholes field activities to be conducted during early stages of Site Characterization at the Deaf Smith County, Texas, site. The field program has been designed to provide data useful in addressing information/data needs resulting from federal/state/local regulations, and repository program requirements. Approximately 50 foundation boreholes will be drilled within the ESP location to provide data necessary for design of the ESF and to satisfy applicable shaft permitting requirements. Soils and subsurface rock will be sampled as the foundation boreholes are advanced. Soil samples or rock core will be taken through the Blackwater Draw and Ogallala Formations and the Dockum Group. Hydrologic testing will be performed in boreholes that penetrates the water table. In-situ elastic properties will be determined from both the soil strata and rock units along the length of the boreholes. Field methods/tests are chosen that provide the best or only means of obtaining the required data. The Salt Repository Project (SRP) Networks specify the schedule under which the program will operate. Drilling will not begin until after site ground water baseline conditions have been established. The Technical Field Services Contractor is responsible for conducting the field program of drilling and testing. Samples and data will be handled and reported in accordance with established SRP procedures. A quality assurance program will be utilized to assure that activities affecting quality are performed correctly and that the appropriate documentation is maintained. 25 refs., 10 figs., 6 tabs

  7. Preliminary results on the search for new Late Glacial rock shelter-sites in the Federal State of Hesse

    DEFF Research Database (Denmark)

    Sauer, Florian Rudolf

    The multidisciplinary project “Apocalypse Then? The Laacher See volcanic eruption, Deep Environmental History and Europe’s Geo-cultural Heritage” at Aarhus University aims to investigate the influence of the catastrophic Late Glacial volcanic eruption on the lifeways of foragers 13.000 years ago....... One of the major work packages is the discovery of new sites which can provide Late Palaeolithic strata in the context of volcanic ash deposits. Previous tephrochronological research has demonstrated that neither open-air nor deep cave sites harbour great potential for discovering in situ volcanic ash...... of Bettenroder Berg in Lower Saxony which provide rich ABP (Arch-backed point-technocomplex) finds covered by Laacher-See Tephra (see Grote 1994). For the state of Hesse in Central Germany a database of ca. 800 potential rock shelters is forming the basis for the search for new sites in the medial zone...

  8. Intraoperative detection of 18F-FDG-avid tissue sites using the increased probe counting efficiency of the K-alpha probe design and variance-based statistical analysis with the three-sigma criteria

    International Nuclear Information System (INIS)

    Povoski, Stephen P; Chapman, Gregg J; Murrey, Douglas A; Lee, Robert; Martin, Edward W; Hall, Nathan C

    2013-01-01

    Intraoperative detection of 18 F-FDG-avid tissue sites during 18 F-FDG-directed surgery can be very challenging when utilizing gamma detection probes that rely on a fixed target-to-background (T/B) ratio (ratiometric threshold) for determination of probe positivity. The purpose of our study was to evaluate the counting efficiency and the success rate of in situ intraoperative detection of 18 F-FDG-avid tissue sites (using the three-sigma statistical threshold criteria method and the ratiometric threshold criteria method) for three different gamma detection probe systems. Of 58 patients undergoing 18 F-FDG-directed surgery for known or suspected malignancy using gamma detection probes, we identified nine 18 F-FDG-avid tissue sites (from amongst seven patients) that were seen on same-day preoperative diagnostic PET/CT imaging, and for which each 18 F-FDG-avid tissue site underwent attempted in situ intraoperative detection concurrently using three gamma detection probe systems (K-alpha probe, and two commercially-available PET-probe systems), and then were subsequently surgical excised. The mean relative probe counting efficiency ratio was 6.9 (± 4.4, range 2.2–15.4) for the K-alpha probe, as compared to 1.5 (± 0.3, range 1.0–2.1) and 1.0 (± 0, range 1.0–1.0), respectively, for two commercially-available PET-probe systems (P < 0.001). Successful in situ intraoperative detection of 18 F-FDG-avid tissue sites was more frequently accomplished with each of the three gamma detection probes tested by using the three-sigma statistical threshold criteria method than by using the ratiometric threshold criteria method, specifically with the three-sigma statistical threshold criteria method being significantly better than the ratiometric threshold criteria method for determining probe positivity for the K-alpha probe (P = 0.05). Our results suggest that the improved probe counting efficiency of the K-alpha probe design used in conjunction with the three

  9. Intraoperative detection of ¹⁸F-FDG-avid tissue sites using the increased probe counting efficiency of the K-alpha probe design and variance-based statistical analysis with the three-sigma criteria.

    Science.gov (United States)

    Povoski, Stephen P; Chapman, Gregg J; Murrey, Douglas A; Lee, Robert; Martin, Edward W; Hall, Nathan C

    2013-03-04

    Intraoperative detection of (18)F-FDG-avid tissue sites during 18F-FDG-directed surgery can be very challenging when utilizing gamma detection probes that rely on a fixed target-to-background (T/B) ratio (ratiometric threshold) for determination of probe positivity. The purpose of our study was to evaluate the counting efficiency and the success rate of in situ intraoperative detection of (18)F-FDG-avid tissue sites (using the three-sigma statistical threshold criteria method and the ratiometric threshold criteria method) for three different gamma detection probe systems. Of 58 patients undergoing (18)F-FDG-directed surgery for known or suspected malignancy using gamma detection probes, we identified nine (18)F-FDG-avid tissue sites (from amongst seven patients) that were seen on same-day preoperative diagnostic PET/CT imaging, and for which each (18)F-FDG-avid tissue site underwent attempted in situ intraoperative detection concurrently using three gamma detection probe systems (K-alpha probe, and two commercially-available PET-probe systems), and then were subsequently surgical excised. The mean relative probe counting efficiency ratio was 6.9 (± 4.4, range 2.2-15.4) for the K-alpha probe, as compared to 1.5 (± 0.3, range 1.0-2.1) and 1.0 (± 0, range 1.0-1.0), respectively, for two commercially-available PET-probe systems (P < 0.001). Successful in situ intraoperative detection of 18F-FDG-avid tissue sites was more frequently accomplished with each of the three gamma detection probes tested by using the three-sigma statistical threshold criteria method than by using the ratiometric threshold criteria method, specifically with the three-sigma statistical threshold criteria method being significantly better than the ratiometric threshold criteria method for determining probe positivity for the K-alpha probe (P = 0.05). Our results suggest that the improved probe counting efficiency of the K-alpha probe design used in conjunction with the three-sigma statistical

  10. Preliminary geological study in kabupaten Pamekasan area to support the selection of candidate site of nuclear desalination plant

    International Nuclear Information System (INIS)

    Ngadenin; Lilik Subiantoro; Kurnia Setiawan Widana

    2014-01-01

    The area around the southern coast Pamekasan is one of the candidates for the alternatives location of nuclear desalination plant site. In 1949 around Sampang Madura ever tectonic earthquake measuring 5 on the Richter scale with its epicenter on land. Tectonic earthquake with epicenter on land is likely related to the presence of active faults on the Madura island. Location prospective nuclear desalination plant site should be away or free of active faults. The study aimed to obtain geological information and find out the characteristics of tectonics including active fault to support site studies of nuclear desalination plant on the island of Madura. The method used is the geological mapping scale, 1 : 50,000. Lithology in the area along the south coast district Pamekasan is alluvium Holocene age and conglomerate units of Pleistocene age. There were no indications of active faults in the region. Candidates site at this location is less attractive in terms of geotechnical foundation as can be ascertained bedrock will be found sufficient in that building construction will require expensive. (author)

  11. Preliminary accident analysis of Loss of Off-Site Power and In-Box LOCA for the CFETR helium cooled solid breeder blanket

    Energy Technology Data Exchange (ETDEWEB)

    Lian, Qiang; Cui, Shijie [School of Nuclear Science and Technology, Xi’an Jiaotong University, Xi’an, 710049 (China); Shaanxi Key Lab. of Advanced Nuclear Energy and Technology, Xi’an Jiaotong University, Xi’an, 710049 (China); Tian, Wenxi, E-mail: wxtian@mail.xjtu.edu.cn [School of Nuclear Science and Technology, Xi’an Jiaotong University, Xi’an, 710049 (China); Shaanxi Key Lab. of Advanced Nuclear Energy and Technology, Xi’an Jiaotong University, Xi’an, 710049 (China); Zhang, Jing; Zhang, Dalin; Su, G.H. [School of Nuclear Science and Technology, Xi’an Jiaotong University, Xi’an, 710049 (China); Shaanxi Key Lab. of Advanced Nuclear Energy and Technology, Xi’an Jiaotong University, Xi’an, 710049 (China)

    2017-05-15

    Highlights: • The CFETR HCSB blanket has been investigated using RELAP5. • Loss of Off-Site Power is investigated. • The parametric analyses during In-Box LOCA are investigated. • The HCSB blanket for CFETR is designed with sufficient decay heat removal capability. - Abstract: As one of three candidate tritium breeding blanket concepts for Chinese Fusion Engineering Test Reactor (CFETR), a conceptual structure of helium cooled solid breeder (HCSB) blanket was recently proposed. In this paper, the preliminary thermal-hydraulic and safety analyses of the typical outboard equatorial blanket module (No.12) have been carried out using RELAP5/Mod3.4 code. Two design basis accidents are investigated based on the steady-state initialization, including Loss of Off-Site Power and In-Box Loss of Coolant Accident (LOCA). The differences between circulator coast down and circulator rotor locked under Loss of Off-Site Power are compared. Regarding the In-Box LOCA, the influences of different break sizes and locations are thoroughly analyzed based on a relatively accurate modeling method of the heat structures in sub-modules. The analysis results show that the blanket and the combined helium cooling system (HCS) are designed with sufficient decay heat removal capability for both accidents, which can preliminarily verify the feasibility of the conceptual design. The research work can also provide an important reference for parameter optimization of the blanket and its HCS in the next stage.

  12. Preliminary report on the hydrogeology of a low-level radioactive waste disposal site near Sheffield, Illinois

    Science.gov (United States)

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

    1980-01-01

    The Sheffield low-level radioactive-waste disposal site is located on 20 acres of rolling terrain about 3 miles southwest of Sheffield, Illinois. Twenty-one trenches were constructed and filled with radioactive waste from August 1967 through April 1978. Forty-three test wells were installed by the U.S. Geological Survey on and adjacent to the site. Continuous cores were collected from 36 wells to help in defining the subsurface geology. The wells have been used for water sample collection and to monitor water-level changes. A tunnel, 6.5 feet in diameter by 290 feet in length, was constructed beneath four burial trenches to provide access for collection of hydrologic and geologic data. Pennsylvanian shale and mudstone deposits are overlain by Pleistocene glacial deposits consisting of the Teneriffe Silt, Glasford Formation, Roxana Silt, Peoria Loess, Parkland Sand, Cahokia Alluvium, and Henry Formation. Three till units of the Glasford Formation, the Hulick Till Member, the Radnor Till Member, and Till A have been identified on the site. Stratigraphic position indicates that the Hulick Till Member and Till A are probably variations of the same till. A continuous pebbly sand deposit, classified as part of the Toulon Member, extends across the middle of the site and continues off site on the northeast and southwest corners. Because of its relatively high hydraulic conductivity, this deposit will be a controlling factor in shallow groundwater movement and in any radionuclide migration. Ground water at the site is derived through infiltration of precipitation and as underflow from adjacent highlands. Precipitation averages 35 inches per year, 1 or 2 inches of which probably recharge the ground water. Runoff is estimated to be 12 to 15 inches per year and evapotranspiration about 20 inches. The fluctuation of water levels has been about 2.5 feet in hilltop wells, 3.6 feet in sidehill wells, and 5.9 feet in valley wells. Hydraulic conductivity of the materials comprising

  13. Alaska Open-File Report 127 Assessment of Thermal Springs Sites in Southern Southeastern Alaska - Preliminary Results and Evaluation

    Energy Technology Data Exchange (ETDEWEB)

    Motyka, Roman J.; Moorman, Mary A.; Reeder, John W.

    1980-06-01

    Information has been gathered on 13 reported thermal-spring sites, 12 in southern Southeastern Alaska and one in western British Columbia. Five of the reported sites could not be substantiated by DGGS. The eight known thermal spring sites are associated with grainitic terrain and, except for Baker Island Hot Springs, occur within or near intensively fractured Cretaceous-age pluons of the Coast Range Batholith. Thermal-spring surface temperatures range from 21 C (Twin Lakes) to 91.5 C (Bailey Bay). The greatest discharge occurs at Chief Shakes hot springs (450 1pm). Bell Island Hot Springs, which has about a 100-1 pm discharge and a 70 C temperature, has had the most development. Two previously unreported thermal-spring sites, Barnes Lake warm springs and Bradfield hot springs, have a low rate of discharge and respective surface temperatures of about 25 and 54 C. The known thermal springs probably originate from circulation of meteoric waters through deep-seated fracture and fault systems. The chemical constituents of the alkali-sulfate to alkali-chloride thermal waters are probably derived from interaction of the deeply circulating meteoric waters with the granitic wall rocks. Chemical geothermometry suggests subsurface temperatures of 55 to 151 C. If waters are being heated solely by conduction from wall rocks, circulation depths must be about 1.5 to 5 km, assuming geothermal gradients of 30 to 50 C/km. Variations in temperature, discharge, and chemistry were noted at several thermal springs for which previous records are available. A major decrease in silica and potassium concentrations at Chief Shakes hot springs is suggested by comparing recent analyses of water chemistry to Waring's (1917) original analysis. The rate of discharge at Bell Island Hot Springs may have increased by a factor of two since Waring's visit to the springs. Subsurface reservoirs associated with thermal springs in southern Southeastern Alaska are of low temperature and are

  14. Preliminary results of absolute and high-precision gravity measurements at the Nevada Test Site and vicinity, Nevada

    International Nuclear Information System (INIS)

    Zumberge, M.A.; Harris, R.N.; Oliver, H.W.; Sasagawa, G.S.; Ponce, D.A.

    1988-01-01

    Absolute gravity measurements were made at 4 sites in southern Nevada using the absolute gravity free-fall apparatus. Three of the sites are located on the Nevada Test Site at Mercury, Yucca Pass, and in northern Jackass Flats. The fourth site is at Kyle Canyon ranger station near Charleston Park where observed gravity is 216.19 mGal lower than at Mercury. Although there is an uncertainty of about 0.02 mGal in the absolute measured values, their gravity differences are considered accurate to about 0.03 mGal. Therefore, the absolute measurements should provide local control for the calibration of gravity meters between Mercury and Kyle Canyon ranger station to about 1 to 2 parts in 10,000. The average gravity differences between Mercury and Kyle Canyon obtained using LaCoste and Romberg gravity meters is 216.13 mGal, 0.06 mGal lower, or 3 parts in 10,000 lower than using the absolute gravity meter. Because of the discrepancy between the comparison of the absolute and relative gravity meters, more absolute and relative gravity control in southern Nevada, as well as the Mt. Hamilton area where the LaCoste and Romberg instruments were calibrated, is needed. Multiple gravity meter ties were also made between each of the four absolute stations to nearby base stations located on bedrock. These stations were established to help monitor possible real changes in gravity at the absolute sites that could result from seasonal variations in the depth to the water table or other local mass changes. 8 refs., 16 figs., 7 tabs

  15. Radiological consequence analysis. Report on the work package 10. Preliminary safety analysis for the site Gorleben; Radiologische Konsequenzanalyse. Bericht zum Arbeitspaket 10. Vorlaeufige Sicherheitsanalyse fuer den Standort Gorleben

    Energy Technology Data Exchange (ETDEWEB)

    Larue, Juergen; Baltes, Bruno; Fischer, Heidemarie; Frieling, Gerd; Kock, Ingo; Navarro, Martin; Seher, Holger

    2013-02-15

    Work package 10 of the preliminary safety analysis for the site Gorleben concerns the analysis of release scenarios and the radiological consequences. The report includes the description of the applied methodology, the concept for the mathematical description of scenarios, the variety of scenarios for the radiological consequence analysis with the definition of the reference scenario. The database for the calculation covers geology and hydrology, the final repository concept and the process of the final disposal system. The used models were the one-phase transport model MARINE and the two-phase transport model TOUGH2. The report summarizes the results including an evaluation of the realization of the demonstration concept with respect to solution transport, fluid transport, robustness of the modeling results and analogy discussion to other disposal variants (i.e. borehole disposal and storage of transport or storage casks).

  16. Geochemical analysis of the sealing system. Technical Report to work package 9.1.2. Preliminary safety case of the Gorleben site (VSG)

    Energy Technology Data Exchange (ETDEWEB)

    Xie, Mingliang; Herbert, Horst-Juergen

    2012-02-15

    The geochemical reaction simulation of ground water and brines with sealing materials for a proposed repository at the Gorleben site is a task under the framework of the VSG project. The calculations presented in this report are aimed to provide a preliminary evaluation of the geochemical stability of three potential engineering barrier materials foreseen in the shaft sealing system in case of groundwater and brine intrusion. The long-term stability of these materials is a key issue for the sealing function of the shaft seals. This is governed by many factors such as geotechnical, hydraulic and geochemical processes. In order to better understand the potential effect of geochemical processes on the long-term properties of these sealing materials, geochemical simulations of the potential interactions between groundwater and brine and shaft sealing materials were performed.

  17. Wood-waste fuelled indirectly-fired gas turbine cogeneration plant for sawmill applications. Phase 2. Site-specific preliminary engineering and financial analysis

    Energy Technology Data Exchange (ETDEWEB)

    1988-03-01

    The use of conventional steam/electricity cogeneration systems is not generally economical at the sawmill scale of operation. This paper describes an evaluation of a wood-waste fueled and, indirectly, gas fired turbine cogeneration plant aimed at developing a cost-effective wood-waste fired power generation and dry kiln heating system for sawmill applications. A preliminary engineering design and financial analysis of the system was prepared for a demonstration site in British Columbia. A number of alternative system configurations were identified and preliminary engineering designs prepared for each. In the first option , wood wastes combusted in a wet cell hot gas generator powered a 600 kW turbine, and produced 7,000 kW for the drying kilns. The second option provided the same electrical and heat output but used a down-fired suspension burner unit fuelled by clean, dried sawdust, together with an integral air heater heat exchanger. The third option represented a commercial-scale configuration with an electrical output of 1,800 kW, and sufficient heat output for the dry kilns. A financial analyis based on a computerized feasibility model was carried out on the last two options. Low electricity rates in British Columbia combined with the small scale of a demonstration project provide an inadequate rate of return at the site without substantial outside support. At a commercial scale of operation and with the higher electricity prices that exist outside of British Columbia the financial analysis indicates that the incremental investment in the electric generation portion of the system provides very attractive rates of return for the 3 options. 11 figs., 10 tabs.

  18. A joint Russian-American field test at the Chelyabinsk-65 (Mayak) Site: Test description and preliminary results

    International Nuclear Information System (INIS)

    Wollenberg, H.; Tsang, C.F.; Frangos, W.

    1995-05-01

    In September 1994, a Russian-American team conducted hydrogeological, geochemical, geophysical, and radiometric measurements in the territory of the Mayak Production Association. The primary purpose of these operations was to examine the groundwater plume moving from Lake Karachai toward the river. Activities encompassed isolation of hydrologic intervals in two wells and production of water from these intervals, to compare isolated versus open-well sampling methods; surface and soil-water sampling, accompanying radiometric measurements and subsequent chemical analyses; and electrical resistivity profiling in areas of expected contrasting resistivity. Preliminary results indicate that (1) 60 Co and 137 Cs are present in small concentrations in water of the Mishelyak River, (2) analyses of water samples collected by a downhole sampler and of water produced from packed-off intervals agree within limits of laboratory accuracy, attesting to the efficacy of the sampling methods presently used by the Russian workers; and (3) strong contrasts occur between the electrical resistivities of soil and bedrock. Further collaborative work is strongly recommended, and should include more detailed isolation of intervals in wells by multi-packer installations, to better determine the geochemical and hydrological characteristics of the Karachai-Mishelyak system; deployment of a broader soil-water and soil sampling array; a more detailed examination of the distribution and concentration of radionuclides by high-resolution field gamma spectrometry; and a detailing of the area's electrical resistivity setting, using a mobile electromagnetic measurement system

  19. Preliminary Analysis of Night-time Aerosol Optical Depth Retrievals at a Rural, Near-urban Site in Southern Canada

    International Nuclear Information System (INIS)

    Baibakov, K.; O'Neill, N. T.; Firanski, B.; Strawbridge, K.

    2009-01-01

    In the summer of 2007, a SPSTAR03 starphotometer was installed at Egbert, Canada (44 deg. 13' N, 79 deg. 45' W, alt 264 m) and a continuous series of initial measurements was performed between August 26 and September 19. Several sunphotometry parameters such as the aerosol optical depth (AOD) and the 'fine' and 'coarse' optical depths were extracted from the SPSTAR03 extinction spectra. The SPSTAR03 data was analyzed in conjunction with sunphotometry and zenith-pointing lidar data acquired during the same time period. Preliminary results show coarse continuity between the day- and night time AOD values (with the mean difference between the measured and the interpolated values being 0.05) as well as a qualitative correlation between the 'fine' and 'coarse' optical depths and the normalized lidar backscatter coefficient profiles. It was also found that the spectra produced with the differential two-star measurement method were sensitive to non-horizontally homogeneous differences in the line-of-sight conditions of both stars. The one-star method helps to reduce the uncertainties but requires the determination of a calibration constant.

  20. Preliminary access routes and cost study analyses for seven potentially acceptable salt sites: Final report, October 1984

    International Nuclear Information System (INIS)

    1987-02-01

    This report analyzes highway and railroad access to seven potentially acceptable salt repository sites: Richton Dome and Cypress Creek Dome in Mississippi, Vacherie Dome in Louisiana, Swisher County and Deaf Smith County in Texas, and Davis Canyon and Lavender Canyon in utah. The objectives of the study were to investigate the routing of reasonable access corridors to the sites, describe major characteristics of each route, and estimate the costs for constructing or upgrading highways and railroads. The routes used in the analysis are not necessarily recommended or preferred over other routes, nor do they represent an implied final selection. Detailed engineering studies must be performed for the Davis Canyon and Lavender Canyon highway access before the analyzed routes can be considered to be viable. 20 refs., 7 figs., 3 tabs

  1. Preliminary report on coal pile, coal pile runoff basins, and ash basins at the Savannah River Site: effects on groundwater

    Energy Technology Data Exchange (ETDEWEB)

    Palmer, E. [Westinghouse Savannah River Company, AIKEN, SC (United States)

    1997-04-28

    Coal storage piles, their associated coal pile runoff basins and ash basins could potentially have adverse environmental impacts, especially on groundwater. This report presents and summarizes SRS groundwater and soil data that have been compiled. Also, a result of research conducted on the subject topics, discussions from noted experts in the field are cited. Recommendations are made for additional monitor wells to be installed and site assessments to be conducted.

  2. Field Demonstration of Ground-Source Integrated Heat Pump Part I. Technology and Field Demo System/Site Descriptions, and Preliminary Summer/Fall Performance Analysis for One Site

    Energy Technology Data Exchange (ETDEWEB)

    Baxter, Van D. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Munk, Jeffrey D. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Gehl, Anthony C. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

    2016-02-01

    The field study is planned to continue through the 2016 cooling season with the draft final project report due by September 30, 2016. This report provides a description of both installations and preliminary 2015 cooling and fall season performance results for the Knoxville site. For the August 18 through December 14 period, the Knoxville site GS-IHP provided 53.6% total source energy savings compared to a baseline electric RTU/heat pump and electric WH. Peak demand savings ranged from 33% to 59% per month. Energy cost savings of 53.1% have been achieved to date with more than half of that coming from reduced demand charges. Data on installation and maintenance costs are being collected and will be combined with total test period energy savings data for a payback analysis to be included in the project final report. The GS-IHP also saved a significant amount of carbon emissions. The total emission savings for the Knoxville site for the August-December 2015 period were ~0.8 metric tons. If trading for carbon credits ever becomes a reality, additional cost savings would be realized.

  3. Strategy for long-term 3D cloud-resolving simulations over the ARM SGP site and preliminary results

    Science.gov (United States)

    Lin, W.; Liu, Y.; Song, H.; Endo, S.

    2011-12-01

    Parametric representations of cloud/precipitation processes continue having to be adopted in climate simulations with increasingly higher spatial resolution or with emerging adaptive mesh framework; and it is only becoming more critical that such parameterizations have to be scale aware. Continuous cloud measurements at DOE's ARM sites have provided a strong observational basis for novel cloud parameterization research at various scales. Despite significant progress in our observational ability, there are important cloud-scale physical and dynamical quantities that are either not currently observable or insufficiently sampled. To complement the long-term ARM measurements, we have explored an optimal strategy to carry out long-term 3-D cloud-resolving simulations over the ARM SGP site using Weather Research and Forecasting (WRF) model with multi-domain nesting. The factors that are considered to have important influences on the simulated cloud fields include domain size, spatial resolution, model top, forcing data set, model physics and the growth of model errors. The hydrometeor advection that may play a significant role in hydrological process within the observational domain but is often lacking, and the limitations due to the constraint of domain-wide uniform forcing in conventional cloud system-resolving model simulations, are at least partly accounted for in our approach. Conventional and probabilistic verification approaches are employed first for selected cases to optimize the model's capability of faithfully reproducing the observed mean and statistical distributions of cloud-scale quantities. This then forms the basis of our setup for long-term cloud-resolving simulations over the ARM SGP site. The model results will facilitate parameterization research, as well as understanding and dissecting parameterization deficiencies in climate models.

  4. Synthesis and Preliminary Characterization of a PPE-Type Polymer Containing Substituted Fullerenes and Transition Metal Ligation Sites

    Directory of Open Access Journals (Sweden)

    Corinne A. Basinger

    2015-01-01

    Full Text Available A substituted fullerene was incorporated into a PPE-conjugated polymer repeat unit. This subunit was then polymerized via Sonogashira coupling with other repeat units to create polymeric systems approaching 50 repeat units (based on GPC characterization. Bipyridine ligands were incorporated into some of these repeat units to provide sites for transition metal coordination. Photophysical characterization of the absorption and emission properties of these systems shows excited states located on both the fullerene and aromatic backbone of the polymers that exist in a thermally controlled equilibrium. Future work will explore other substituted polyaromatic systems using similar methodologies.

  5. Crystallization and preliminary crystallographic studies of an active-site mutant hydantoin racemase from Sinorhizobium meliloti CECT4114

    International Nuclear Information System (INIS)

    Martínez-Rodríguez, Sergio; González-Ramírez, Luis Antonio; Clemente-Jiménez, Josefa María; Rodríguez-Vico, Felipe; Las Heras-Vázquez, Francisco Javier; Gavira, Jose Antonio; García-Ruiz, Juan Ma.

    2007-01-01

    Crystals of an active-site mutated hydantoin racemase from S. meliloti have been obtained in the presence and absence of d,l-5-isopropyl-hydantoin and characterized by X-ray diffraction. A recombinant active-site mutant of hydantoin racemase (C76A) from Sinorhizobium meliloti CECT 4114 (SmeHyuA) has been crystallized in the presence and absence of the substrate d,l-5-isopropyl hydantoin. Crystals of the SmeHyuA mutant suitable for data collection and structure determination were grown using the counter-diffusion method. X-ray data were collected to resolutions of 2.17 and 1.85 Å for the free and bound enzymes, respectively. Both crystals belong to space group R3 and contain two molecules of SmeHyuA per asymmetric unit. The crystals of the free and complexed SmeHyuA have unit-cell parameters a = b = 85.43, c = 152.37 Å and a = b = 85.69, c = 154.38 Å, crystal volumes per protein weight (V M ) of 1.94 and 1.98 Å 3 Da −1 and solvent contents of 36.7 and 37.9%, respectively

  6. Classifying urban meteorological stations sites by 'local climate zones': Preliminary results for the city of Novi Sad (Serbia

    Directory of Open Access Journals (Sweden)

    Savić Stevan

    2013-01-01

    Full Text Available Conventional approach in the investigation of urban climate of Novi Sad has been done through simple urban-rural air temperature differences. These inter-urban air temperature differences showed how much is city warmer than its surroundings, so-called urban heat island (UHI effect. Temperature differences exist inside the city as well. To get to know the intensity of these intra-urban temperature differences, installation of meteorological stations in different parts of the city or mobile measurements are needed. In 2012 started IPA HUSRB project made by Department of Climatology and Landscape Ecology (University of Szeged and Faculty of Sciences (University of Novi Sad. The main goal of this project is the development and installation of wireless urban meteorological network (temperature and relative humidity sensors in Szeged and Novi Sad. Before the deployment of sensors, necessary metadata about each potential urban meteorological station site needs to be collected. Field work, collected metadata and Stewart and Oke climate-based classification system from 2012 were used for defining the potential urban meteorological stations sites on the territory of the city of Novi Sad (Serbia and its surroundings.

  7. Repository operational criteria analysis

    International Nuclear Information System (INIS)

    Hageman, J.P.; Chowdhury, A.H.

    1992-08-01

    The objective of the ''Repository Operational Criteria (ROC) Feasibility Studies'' (or ROC task) was to conduct comprehensive and integrated analyses of repository design, construction, and operations criteria in 10 CFR Part 60 regulations, considering the interfaces and impacts of any potential changes to those regulations. The study addresses regulatory criteria related to the preclosure aspects of the geologic repository. The study task developed regulatory concepts or potential repository operational criteria (PROC) based on analysis of a repository's safety functions and other regulations for similar facilities. These regulatory concepts or PROC were used as a basis to assess the sufficiency and adequacy of the current criteria in 10 CFR Part 60. Where the regulatory concepts were same as current operational criteria, these criteria were referenced. The operations criteria referenced or the PROC developed are given in this report. Detailed analyses used to develop the regulatory concepts and any necessary PROC for those regulations that may require a minor change are also presented. The results of the ROC task showed a need for further analysis and possible major rule change related to the design bases of a geologic repository operations area, siting, and radiological emergency planning

  8. Criteria CSR

    OpenAIRE

    Vovk, V.; Zateyshikova, O.

    2014-01-01

    In the article the theoretical aspects regarding criteria for assessing CSR proposed by A. Carroll, including: economic, legal, ethical, philanthropic. Based on this, it is proposed to characterize these criteria with respect to the interested parties (stakeholders), including: investors, shareholders suppliers, customers, employees, society and the state. This will make a qualitative assessment of the presence and depth using social responsibility in the company, as well as determine the ext...

  9. Preliminary Performance Assessment for Disposal of APT and CLWR/TEF Wastes at SRS

    International Nuclear Information System (INIS)

    Wilhite, E.L.

    1998-01-01

    This section provides the descriptive information for understanding the analyses presented in this preliminary performance assessment. This section addresses the approach taken in the PA, provides a general description of the Savannah River Site E-Area low-level waste facility, and discusses the performance criteria used for evaluating performance

  10. Preliminary study on the relationship between trends of tree-ring δ 13C series and site conditions

    International Nuclear Information System (INIS)

    Chen Tuo; Qin Dahe; Liu Xiaohong; Ren Jiawen

    2001-01-01

    The long-term trends of tree-ring δ 13 C series, taken respectively from Qilian of Qinghai and Zhaosu and Aleitai of xinjiang were compared. The results showed that a similar trend existed between Qilian series and Zhaosu series, while there was a significant difference between them and Aleitai series. The authors' analysis indicated that the site difference of the trends of tree-ring δ 13 C series was mainly associated with 'canopy effects' of tree growth. It is suggested that tree samples should be selected from sparse forests or the sampled tree foliage high above the whole canopy when the history of δ 13 C of atmospheric CO 2 was reconstructed by tree-ring series

  11. Can multi-criteria analysis models support the site selection for a repository for heat-generating waste?; Koennen multikriterielle Analysemodelle die Standortauswahl fuer ein Endlager fuer Waerme entwickelnde Abfaelle unterstuetzen?

    Energy Technology Data Exchange (ETDEWEB)

    Gutberlet, Daniela [DMT GmbH und Co.KG, Essen (Germany). Geschaeftsentwicklung Nukleare Entsorgung

    2015-07-01

    The decision for or against a potential site for a nuclear waste repository is highly complex and requires decision-makers to consider multiple assessment criteria. The complexity of each site and its characteristics, and the differing opinions among members of the public and advocacy groups mean t hat conflicts of interest are likely to arise. In this paper, the author suggests that multi-criteria analysis models could be used to provide methodological support during the selection process. The models can map these types of decision situations and suggest coherent solutions with relatively little formal effort. They allow users to compare different opt ions simultaneously and ensure that t heir decision-making Is conscious rather than arbitrary.

  12. IRSN's opinion on criteria retained by the ANDRA for choosing a 'zone of interest for deepened investigation' (ZIRA, zone d'interet pour la reconnaissance approfondie) for the HA-MAVL-Site de Meuse/Haute-Marne project

    International Nuclear Information System (INIS)

    2009-12-01

    Within the context of selection of a site for a future deep storage for high- and intermediate-level activity and long life wastes, this report comments the various results of geological investigations and characterizations performed on this site during the past years. It notices that the most recent results (2007 and 2008) do not put previous conclusions (2005) into question. It recalls the required geological characteristics for such a storage site and compares them with the site characteristics. The IRSN agrees with the technical criteria adopted by the ANDRA for the choice of a zone of interest for a deepened investigation, and more particularly for this particular zone located on the territory of both French departments of Meuse and Haute-Marne

  13. Description of climate, surface hydrology, and near-surface hydrogeology. Preliminary site description. Forsmark area - version 1.2

    Energy Technology Data Exchange (ETDEWEB)

    Johansson, Per-Olof [Artesia Grundvattenkonsult AB, Stockholm (Sweden); Werner, Kent [SWECO VIAK AB/Golder Associates AB, Stockholm (Sweden); Bosson, Emma; Berglund, Sten [Swedish Nuclear Fuel and Waste Management Co., Stockholm (Sweden); Juston, John [DBE Sweden, Uppsala (Sweden)

    2005-06-15

    The Swedish Nuclear Fuel and Waste Management Company (SKB) is conducting site investigations at two different locations, the Forsmark and Simpevarp areas, with the objective of siting a geological repository for spent nuclear fuel. The results from the investigations at the sites are used as a basic input to the development of Site Descriptive Models (SDM). The SDM shall summarise the current state of knowledge of the site, and provide parameters and models to be used in further analyses within Safety Assessment, Repository Design and Environmental Impact Assessment. The present report is a background report describing the meteorological conditions and the modelling of surface hydrology and near-surface hydrogeology in support of the Forsmark version 1.2 SDM based on the data available in the Forsmark 1.2 'data freeze' (July 31, 2004). The groundwater is very shallow, with groundwater levels within one meter below ground as an annual mean for almost all groundwater monitoring wells. Also, the annual groundwater level amplitude is less than 1.5 m for most wells. The shallow groundwater levels mean that there is a strong interaction between evapotranspiration, soil moisture and groundwater. In the modelling, surface water and near-surface groundwater divides are assumed to coincide. The small-scale topography implies that many local, shallow groundwater flow systems are formed in the Quaternary deposits, overlaying more large-scale flow systems associated with groundwater flows at greater depths. Groundwater level time series from wells in till and bedrock within the same areas show a considerably higher groundwater level in the till than in the bedrock. The observed differences in levels are not fully consistent with the good hydraulic contact between overburden and bedrock indicated by the hydraulic tests in the Quaternary deposits. However, the relatively lower groundwater levels in the bedrock may be caused by the horizontal to sub-horizontal highly

  14. Totally extraperitoneal (TEP) bilateral hernioplasty using the Single Site® robotic da Vinci platform (DV-SS TEP): description of the technique and preliminary results.

    Science.gov (United States)

    Cestari, A; Galli, A C; Sangalli, M N; Zanoni, M; Ferrari, M; Roviaro, G

    2017-06-01

    Laparoendoscopic single site totally extraperitoneal (TEP) hernia repair showed to be a feasible alternative to conventional laparoscopic hernia repair; nevertheless single site surgery, with the loss of instruments triangulation can be a demanding procedure. To overcome those hurdles, the Single Site® (SS) platform of the da Vinci (DV) Si robotic system enables to perform surgical procedures through a 25-mm skin incision, with a stable 3D vision and restoring an adequate triangulation of the surgical instruments. We present in details the technique and the preliminary results of DV-SS TEP, to our knowledge the first cases reported in literature. In March 2016, three consecutive male patients (mean age 46.6 years-mean BMI 25.3) with bilateral symptomatic inguinal hernia were submitted to DV-SS TEP in our institutions. Feasibility, codification of the technique, operative time and perioperative outcomes were recorded. All the procedures were completed as scheduled, with no conversion to other techniques. Mean operative time was 98.6 min, ranging between 155 and 55 min, reflecting the learning curve of the operating room team on this new procedure. No intraoperative or postoperative complications were experienced and all the patients were discharged within 24 h after surgery. Patients reported satisfactory postoperative course, with no recurrence of inguinal hernia and satisfaction in cosmetic result at 6-month follow-up. DV-SS TEP inguinal hernia repair showed to be feasible and effective surgical option for bilateral groin hernia repair. Patients' outcome was uneventful, with optimal cosmetic results. Further studies comparing this innovative technique to TEP or LESS TEP should be promoted.

  15. The flora and fauna of a proposed wind turbine site near Royal Road, Prince Edward County, Ontario : preliminary screening of the natural environment

    Energy Technology Data Exchange (ETDEWEB)

    Holder, M.; Leggett, A. [Jacques Whitford Environment Ltd., Markham, ON (Canada)

    2002-07-15

    Calgary based Vision Quest Windelectric has been given zoning approval to install a 22 MW windfarm in Ontario's Prince Edward County. Following a preliminary screening to determine the effect of the windfarm on the natural environment, the Royal Road Windfarm will be developed in stages with up to 32 turbines. Jacques Whitford Environment Ltd. conducted an environmental study which showed that an exploratory wind turbine in the area is not likely to cause major adverse impacts on local fauna and flora. The proposed location of the wind turbine is not in an important bird area (IBA). An IBA is defined as a site providing essential habitat for one of more species of breeding or non-breeding birds. In 1999, Vision Quest initiated a program to examine bird interactions with wind turbines in southern Alberta. It was shown that most species choose flight paths to avoid turbines. The Royal Road site hosts rare alvars which are naturally open landscapes found in shallow soils on flat limestones. The alvars are subject to seasonal drought and flooding and have specific types of vegetation and animals. Since the exploratory wind turbine will be placed outside the IBA area, its impact on birds will be minimized, and it will have minimal effect on migrant, breeding and wintering birds. It was recommended that monitoring take place at the site during the first year of operation. It is also presumed that the wind turbine will not have any impact on mammals, reptiles and amphibians, or insects. However, it was recommended that more information be gathered on bat movement in the area. If placed appropriately, the wind turbine is not expected to impact on rare plants. It was emphasized that in the past, Vision Quest Windelectric has conducted environmental screening activities, and has acted on recommendations to place wind turbines in locations where environmental impact will be minimized. 26 refs., 5 tabs., 2 figs., 2 appendices.

  16. Preliminary report on the geology and geophysics of drill hole UE25a-1, Yucca Mountain, Nevada Test Site

    International Nuclear Information System (INIS)

    Spengler, R.W.; Muller, D.C.; Livermore, R.B.

    1979-01-01

    A subsurface geologic study in connection with the Nevada Nuclear Waste Storage Investigations has furnished detailed stratigraphic and structural information about tuffs underlying northeastern Yucca Mountain on the Nevada Test Site. Drill hole UE25a-1 penetrated thick sequences of nonwelded to densely welded ash-flow and bedded tuffs of Tertiary age. Stratigraphic units that were identified from the drill-hole data include the Tiva Canyon and Topopah Spring Members of the Paintbrush Tuff, tuffaceous beds of Calico Hills, and the Prow Pass and Bullfrog Members of the Crater Flat Tuff. Structural analysis of the core indicated densely welded zones to be highly fractured. Many fractures show near-vertical inclinations and are commonly coated with secondary silica, manganese and iron oxides, and calcite. Five falt zones were recognized, most of which occurred in the Topopah Spring Member. Shear fractures commonly show obli