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

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

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

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

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.

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.

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.

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

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.

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

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

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

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.

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.

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.

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.

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.

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.

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

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.

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

La Tentation et les savoirs

Directory of Open Access Journals (Sweden)

Gisèle Séginger

2009-01-01

Full Text Available Malgré son inactualité apparente, La Tentation de Saint Antoine se rattache à une série de savoirs, de recherches historiques, d’interrogations qui caractérisent son époque et définissent une configuration épistémologique. Les savoirs sont impliqués à deux niveaux : dans l’organisation de la poétique de l’œuvre, dans les représentations de l’œuvre. Flaubert utilise des savoirs historiques, anthropologiques et psychiatriques qui légitiment l’organisation du texte et les déconstruit en même temps. Il invente une nouvelle forme de grotesque – le grotesque des idées – et met en abyme un questionnement sur les savoirs qui évolue de la première Tentation à celle de 1874.Despite its apparent irrelevancy to Flaubert's time, La Tentation de Saint Antoine is linked to a net of knowledge, historical research, questions that characterize a period and define an epistemological configuration. These types of knowledge are at play on two levels: in the organization of the poetics of the work and in its representations. Flaubert uses historical, anthropological and psychiatric knowledge which legitimates the organization of the text while at the same time he deconstructs this body of knowledge. Flaubert invents a new form of grotesque – the grotesque of ideas – and, in a mise-en-abyme from the first Tentation to the 1874 version, he questions these fields of knowledge.

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

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.)

Salt site performance assessment activities

International Nuclear Information System (INIS)

Kircher, J.F.; Gupta, S.K.

1983-01-01

During this year the first selection of the tools (codes) for performance assessments of potential salt sites have been tentatively selected and documented; the emphasis has shifted from code development to applications. During this period prior to detailed characterization of a salt site, the focus is on bounding calculations, sensitivity and with the data available. The development and application of improved methods for sensitivity and uncertainty analysis is a focus for the coming years activities and the subject of a following paper in these proceedings. Although the assessments to date are preliminary and based on admittedly scant data, the results indicate that suitable salt sites can be identified and repository subsystems designed which will meet the established criteria for protecting the health and safety of the public. 36 references, 5 figures, 2 tables

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.

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.

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

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.

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.

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

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)

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

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

29 CFR 1902.21 - Tentative decision following formal proceeding.

Science.gov (United States)

2010-07-01

... Section 1902.21 Labor Regulations Relating to Labor (Continued) OCCUPATIONAL SAFETY AND HEALTH..., the Assistant Secretary shall issue a tentative decision either approving or disapproving the plan... therefor on all material issues of fact, law, or discretion which have been presented. The tentative...

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...

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

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

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

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

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

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.

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

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).

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.''

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.

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

Aesthetics-based classification of geological structures in outcrops for geotourism purposes: a tentative proposal

Science.gov (United States)

Mikhailenko, Anna V.; Nazarenko, Olesya V.; Ruban, Dmitry A.; Zayats, Pavel P.

2017-03-01

The current growth in geotourism requires an urgent development of classifications of geological features on the basis of criteria that are relevant to tourist perceptions. It appears that structure-related patterns are especially attractive for geotourists. Consideration of the main criteria by which tourists judge beauty and observations made in the geodiversity hotspot of the Western Caucasus allow us to propose a tentative aesthetics-based classification of geological structures in outcrops, with two classes and four subclasses. It is possible to distinguish between regular and quasi-regular patterns (i.e., striped and lined and contorted patterns) and irregular and complex patterns (paysage and sculptured patterns). Typical examples of each case are found both in the study area and on a global scale. The application of the proposed classification permits to emphasise features of interest to a broad range of tourists. Aesthetics-based (i.e., non-geological) classifications are necessary to take into account visions and attitudes of visitors.

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

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

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

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

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.

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.

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.

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

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

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

DSM disorders and their criteria: how should they inter-relate?

Science.gov (United States)

Kendler, K S

2017-09-01

While the changes in psychiatric diagnosis introduced by Diagnostic and Statistical Manual third edition (DSM-III) have had major benefits to the field of psychiatry, the reification of its diagnostic criteria and the widespread adoption of diagnostic literalism have been problematic. I argue that, at root, these developments can be best understood by contrasting two approaches to the relationship between DSM disorders and their criteria. In a constitutive relationship, criteria definitively define the disorder. Having a disorder is nothing more than meeting the criteria. In an indexical relationship, the criteria are fallible indices of a disorder understood as a hypothetical, tentative diagnostic construct. I trace the origins of the constitutive model to the philosophical theory of operationalism. I then examine a range of historical and empirical results that favor the indexical over the constitutive position including (i) evidence that individual criteria for DSM-III were selected from a broader pool of possible symptoms/signs, (ii) revisions of DSM have implicitly assumed an indexical criteria-disorder relationship, (iii) the indexical position allows DSM criteria to be wrong and misdiagnose patients while such a result is incoherent for a constitutive model, an implausible position, (iv) we assume an indexical criteria-scale relationships for many personality and symptom measures commonly used in psychiatric practice and research, and (v) empirical studies suggesting similar performance for DSM and non-DSM symptoms for major depression. I then review four reasons for the rise of the constitutive position: (i) the 'official' nature of the DSM criteria, (ii) the strong investment psychiatry has had in the DSM manual and its widespread use and success, iii) lack of a clear pathophysiology for our disorders, and (iv) the absence of informative diagnostic signs of minimal clinical importance. I conclude that the constitutive position is premature and reflects a

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

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.

A first possible chameleon from the late Miocene of India (the hominoid site of Haritalyangar): a tentative evidence for an Asian dispersal of chameleons.

Science.gov (United States)

Sankhyan, Anek R; Čerňanský, Andrej

2016-12-01

Miocene rare fossils from India, tentatively attributed to chameleons, are described for the first time. The material consists of a fragment of the left squamosal and an element interpreted as a posterodorsal process of the parietal. The specimens come from a late Miocene site of the Nagri Formation (Middle Siwaliks, ~ 9 Mya) at Haritalyangar, North India. This material presents a possible evidence for a chameleon dispersal to Asia. Based on molecular data, the dispersion of an Asian chamaeleonid lineage from Africa to Arabia/Asia is dated at approximately 13 Mya and its diversification in situ at around 6-8 Mya. However, till now, no Miocene-age fossil record has been described to support crown chamaeleonid presence in this area. The material described herein is very fragmented. If correctly allocated, the Haritalyangar chameleons show the oldest known occurrence of this clade in India, at least approximately 9 Mya ago.

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

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

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.

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)

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

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.''

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.)

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.)

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

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

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

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...

A Tentative Organizational Schema for Decision-Making Problems.

Science.gov (United States)

Osborn, William C.; Goodman, Barbara Ettinger

This report presents the results of research that examined widely diverse decision problems and attempted to specify their common behavior elements. To take into account the psychological complexity of most real-life decision problems, and to develop a tentative organization of decision behavior that will embrace the many, highly diverse types of…

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.

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

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)

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.

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.

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

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

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.

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

Tentative novel lyssavirus in a bat in Finland.

Science.gov (United States)

Nokireki, T; Tammiranta, N; Kokkonen, U-M; Kantala, T; Gadd, T

2018-06-01

A tentative novel member of the genus Lyssavirus, designated as Kotalahti bat lyssavirus, was detected in a Brandt's bat (Myotis brandtii) in Finland. Based on phylogenetic analysis, the virus differs from other known lyssaviruses, being closely related to Khujand virus, Aravan virus, Bokeloh bat lyssavirus and European bat lyssavirus 2. © 2018 The Authors. Transboundary and Emerging Diseases Published by Blackwell Verlag GmbH.

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

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.

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.

Photovoltaic system criteria documents. Volume 3: Environmental issues and evaluation criteria for photovoltaic applications

Science.gov (United States)

Koenig, John C.; Billitti, Joseph W.; Tallon, John M.

1979-01-01

The environmental issues and evaluation criteria relating to the suitability of sites proposed for photovoltaic (PV) system deployment are identified. The important issues are defined, briefly discussed and then developed into evaluation criteria. System designers are provided with information on the environmental sensitivity of PV systems in realistic applications, background material which indicates the applicability of the siting issues identified, and evaluation criteria are defined to facilitate the selection of sites that maximize PV system operation.

Opaque Watercolor (Tentative Course Outline). Art Education: 6673.05.

Science.gov (United States)

Greenaway, Jean E.

This tentative course outline is for use in one of the Quinmester Program classes, Opaque Watercolor. Designed for students in grades 7-12, with no prerequisite, the course includes the introduction of a variety of techniques in a number of opaque media including tempera, gouache, and cassein. Matting and mounting techniques are also taught. A…

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

76 FR 57981 - Environmental Management Site-Specific Advisory Board, Portsmouth

Science.gov (United States)

2011-09-19

... DEPARTMENT OF ENERGY Environmental Management Site-Specific Advisory Board, Portsmouth AGENCY... Environmental Management Site-Specific Advisory Board (EM SSAB), Portsmouth. The Federal Advisory Committee Act... environmental restoration, waste management and related activities. Tentative Agenda Call to Order...

77 FR 2283 - Environmental Management Site-Specific Advisory Board, Portsmouth

Science.gov (United States)

2012-01-17

... DEPARTMENT OF ENERGY Environmental Management Site-Specific Advisory Board, Portsmouth AGENCY... Environmental Management Site-Specific Advisory Board (EM SSAB), Portsmouth. The Federal Advisory Committee Act... environmental restoration, waste management and related activities. Tentative Agenda Call to Order...

76 FR 36100 - Environmental Management Site-Specific Advisory Board, Portsmouth

Science.gov (United States)

2011-06-21

... DEPARTMENT OF ENERGY Environmental Management Site-Specific Advisory Board, Portsmouth AGENCY... Environmental Management Site-Specific Advisory Board (EM SSAB), Portsmouth. The Federal Advisory Committee Act... environmental restoration, waste management and related activities. Tentative Agenda Call to Order...

77 FR 29997 - Environmental Management Site-Specific Advisory Board, Portsmouth

Science.gov (United States)

2012-05-21

... DEPARTMENT OF ENERGY Environmental Management Site-Specific Advisory Board, Portsmouth AGENCY... Environmental Management Site-Specific Advisory Board (EM SSAB), Portsmouth. The Federal Advisory Committee Act... environmental restoration, waste management and related activities. Tentative Agenda Call to Order...

77 FR 37390 - Environmental Management Site-Specific Advisory Board, Portsmouth

Science.gov (United States)

2012-06-21

... DEPARTMENT OF ENERGY Environmental Management Site-Specific Advisory Board, Portsmouth AGENCY... Environmental Management Site-Specific Advisory Board (EM SSAB), Portsmouth. The Federal Advisory Committee Act... environmental restoration, waste management and related activities. Tentative Agenda: Call to Order...

76 FR 78909 - Environmental Management Site-Specific Advisory Board, Portsmouth

Science.gov (United States)

2011-12-20

... DEPARTMENT OF ENERGY Environmental Management Site-Specific Advisory Board, Portsmouth AGENCY... Environmental Management Site-Specific Advisory Board (EM SSAB), Portsmouth. The Federal Advisory Committee Act... the areas of environmental restoration, waste management, and related activities. Tentative Agenda...

77 FR 6790 - Environmental Management Site-Specific Advisory Board, Portsmouth

Science.gov (United States)

2012-02-09

... DEPARTMENT OF ENERGY Environmental Management Site-Specific Advisory Board, Portsmouth AGENCY... Environmental Management Site-Specific Advisory Board (EM SSAB), Portsmouth. The Federal Advisory Committee Act... environmental restoration, waste management and related activities. Tentative Agenda Call to Order...

75 FR 51026 - Environmental Management Site-Specific Advisory Board, Portsmouth

Science.gov (United States)

2010-08-18

... DEPARTMENT OF ENERGY Environmental Management Site-Specific Advisory Board, Portsmouth AGENCY... Environmental Management Site-Specific Advisory Board (EM SSAB), Portsmouth. The Federal Advisory Committee Act... the areas of environmental restoration, waste management and related activities. Tentative Agenda...

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

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.

75 FR 7577 - Environmental Management Site-Specific Advisory Board, Portsmouth

Science.gov (United States)

2010-02-22

... DEPARTMENT OF ENERGY Environmental Management Site-Specific Advisory Board, Portsmouth AGENCY... Environmental Management Site-Specific Advisory Board (EM SSAB), Portsmouth. The Federal Advisory Committee Act... areas of environmental restoration, waste management and related activities. Tentative Agenda: Call to...

75 FR 65615 - Environmental Management Site-Specific Advisory Board, Portsmouth

Science.gov (United States)

2010-10-26

... DEPARTMENT OF ENERGY Environmental Management Site-Specific Advisory Board, Portsmouth AGENCY... Environmental Management Site-Specific Advisory Board (EM SSAB), Portsmouth. The Federal Advisory Committee Act... areas of environmental restoration, waste management and related activities. Tentative Agenda Call to...

76 FR 17118 - Environmental Management Site-Specific Advisory Board Chairs

Science.gov (United States)

2011-03-28

... DEPARTMENT OF ENERGY Environmental Management Site-Specific Advisory Board Chairs AGENCY... Environmental Management Site-Specific Advisory Board (EM SSAB) Chairs. The Federal Advisory Committee Act (Pub... areas of environmental restoration, waste management, and related activities. Tentative Agenda Topics...

76 FR 62054 - Environmental Management Site-Specific Advisory Board Chairs

Science.gov (United States)

2011-10-06

... DEPARTMENT OF ENERGY Environmental Management Site-Specific Advisory Board Chairs AGENCY... of the Environmental Management Site-Specific Advisory Board (EM SSAB) Chairs. The Federal Advisory... environmental restoration, waste management, and related activities. Tentative Agenda Topics [cir] EM Program...

75 FR 82003 - Environmental Management Site-Specific Advisory Board, Portsmouth

Science.gov (United States)

2010-12-29

... DEPARTMENT OF ENERGY Environmental Management Site-Specific Advisory Board, Portsmouth AGENCY... Environmental Management Site-Specific Advisory Board (EM SSAB), Portsmouth. The Federal Advisory Committee Act... areas of environmental restoration, waste management and related activities. Tentative Agenda: Call to...

75 FR 19379 - Environmental Management Site-Specific Advisory Board, Portsmouth

Science.gov (United States)

2010-04-14

... DEPARTMENT OF ENERGY Environmental Management Site-Specific Advisory Board, Portsmouth AGENCY... Environmental Management Site-Specific Advisory Board (EM SSAB), Portsmouth. The Federal Advisory Committee Act... areas of environmental restoration, waste management and related activities. Tentative Agenda Call to...

77 FR 51789 - Environmental Management Site-Specific Advisory Board, Paducah

Science.gov (United States)

2012-08-27

... management and related activities. Tentative Agenda Call to Order, Introductions, Review of Agenda... DEPARTMENT OF ENERGY Environmental Management Site-Specific Advisory Board, Paducah AGENCY... Environmental Management Site-Specific Advisory Board (EM SSAB), Paducah. The Federal Advisory Committee Act...

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.

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

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

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

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

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

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)

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

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

Preservice Biology Teachers' Conceptions About the Tentative Nature of Theories and Models in Biology

Science.gov (United States)

Reinisch, Bianca; Krüger, Dirk

2018-02-01

In research on the nature of science, there is a need to investigate the role and status of different scientific knowledge forms. Theories and models are two of the most important knowledge forms within biology and are the focus of this study. During interviews, preservice biology teachers ( N = 10) were asked about their understanding of theories and models. They were requested to give reasons why they see theories and models as either tentative or certain constructs. Their conceptions were then compared to philosophers' positions (e.g., Popper, Giere). A category system was developed from the qualitative content analysis of the interviews. These categories include 16 conceptions for theories ( n tentative = 11; n certai n = 5) and 18 conceptions for models ( n tentative = 10; n certain = 8). The analysis of the interviews showed that the preservice teachers gave reasons for the tentativeness or certainty of theories and models either due to their understanding of the terms or due to their understanding of the generation or evaluation of theories and models. Therefore, a variety of different terminology, from different sources, should be used in learning-teaching situations. Additionally, an understanding of which processes lead to the generation, evaluation, and refinement or rejection of theories and models should be discussed with preservice teachers. Within philosophy of science, there has been a shift from theories to models. This should be transferred to educational contexts by firstly highlighting the role of models and also their connections to theories.

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

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

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

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)

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

Cleanup criteria for the West Valley demonstration project

International Nuclear Information System (INIS)

Parrott, J.D.

1999-01-01

The US Nuclear Regulatory Commission (NRC) is prescribing decontamination and decommissioning (cleanup) criteria for the West Valley Demonstration Project and the West Valley, New York, site. The site is contaminated with various forms of residual radioactive contamination and contains a wide variety of radioactive waste. The NRC is planning to issue cleanup criteria for public comment in Fall 1999. Due to the complexity of the site, and the newness of NRC's cleanup criteria policy, applying NRC's cleanup criteria to this site will be an original regulatory undertaking. (author)

Tentative identification of the second substrate binding site in Arabidopsis phytochelatin synthase.

Directory of Open Access Journals (Sweden)

Ju-Chen Chia

Full Text Available Phytochelatin synthase (PCS uses the substrates glutathione (GSH, γGlu-Cys-Gly and a cadmium (Cd-bound GSH (Cd∙GS2 to produce the shortest phytochelatin product (PC2, (γGlu-Cys2-Gly through a ping-pong mechanism. The binding of the 2 substrates to the active site, particularly the second substrate binding site, is not well-understood. In this study, we generated a structural model of the catalytic domain of Arabidopsis AtPCS1 (residues 12-218 by using the crystal structure of the γGlu-Cys acyl-enzyme complex of the PCS of the cyanobacterium Nostoc (NsPCS as a template. The modeled AtPCS1 revealed a cavity in proximity to the first substrate binding site, consisting of 3 loops containing several conserved amino acids including Arg152, Lys185, and Tyr55. Substitutions of these amino acids (R152K, K185R, or double mutation resulted in the abrogation of enzyme activity, indicating that the arrangement of these 2 positive charges is crucial for the binding of the second substrate. Recombinant AtPCS1s with mutations at Tyr55 showed lower catalytic activities because of reduced affinity (3-fold for Y55W for the Cd∙GS2, further suggesting the role of the cation-π interaction in recognition of the second substrate. Our study results indicate the mechanism for second substrate recognition in PCS. The integrated catalytic mechanism of PCS is further discussed.

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.

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.

Tentative identification of 2-imidazoline as a transformation product of ethylenebisdithiocarbamate fungicides

NARCIS (Netherlands)

Vonk, J.W.; Kaars Sijpesteijn, A.

2-Imidazoline has been identified tentatively as a minor conversion product of ethylenethiourea in seedlings of cucumber and wheat. As ethylenethiourea is known to be present in plants after root treatment with ethylenebisdithiocarbamate fungicides, 2-imidazoline is assumed to be a terminal residue

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

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

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

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

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

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.

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.

Controlling criteria for radiation exposure of astronauts and space workers

International Nuclear Information System (INIS)

Katoh, Kazuaki

1989-01-01

Space workers likely to suffer from radiation exposure in the outer space are currently limited to the U.S. and Soviet Union, and only a small amount of data and information is available concerning the techniques and criteria for control of radiation exposure in this field. Criteria used in the Soviet Union are described first. The criteria (TRS-75), called the Radiation Safety Criteria for Space Navigation, are tentative ones set up in 1975. They are based on risk assessment. The standard radiation levels are established based on unit flight time: 50rem for 1 month, 80rem for 3 months, 110rem for 6 months and 150rem for 12 months. These are largely different from the emergency exposure limit of 100mSv (10rem) specified in a Japanese law, and the standard annual exposure value of 50mSv (5rem) for workers in nuclear power plants at normal times. For the U.S., J.A. Angelo, Jr., presented a paper titled 'Radiation Protection Issues and Techniques concerning Extended Manned Space Missions' at an IAEA meeting held in 1988. Though the criteria shown in the paper are not formal ones at the national level, similar criteria are expected to be adopted by the nation in the near future. The exposure limits recommended in the paper include a depth dose of 1-4Sv for the whole life span of a worker. (Nogami, K.)

Safety Report within the licence application for the siting of a radioactive waste repository/disposal facility

International Nuclear Information System (INIS)

Horyna, J.; Sinaglova, R.

2004-01-01

The initial safety specification report, which is submitted to the licensing authority as one of the application documents, is the basic document assessing the planned repository/disposal facility with respect to the suitability of the chosen site for this purpose. The following topics are covered: General information; Description and evidence of suitability of the site chosen; Description and tentative assessment of the repository/disposal facility design; Tentative assessment of impacts of running the facility on the employees, general public and environment (radionuclide inventory, transport routes, radionuclide release in normal, abnormal and emergency situations); Proposed concept of repository/disposal facility shutdown; and Assessment of quality assurance in the site selection, in preparatory work for the construction of the facility and in the subsequent stages. (P.A.)

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)

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

Initiation of Hoshin Kanri in SMEs using a tentative process

OpenAIRE

Löfving, Malin; Melander, Anders; Andersson, David; Elgh, Fredrik; Thulin, Mikael

2015-01-01

Hoshin Kanri is a management method supporting strategic work. In spite of a number of Hoshin Kanri success stories in large organizations, little research attention are given to SMEs. This research encourages an increased focus on Hoshin Kanri in SMEs. In this paper a tentative process for the initiation of Hoshin Kanri in SMEs is outlined. We also identify factors influencing the initiation of Hoshin Kanri in SMEs based on findings from eight case studies. The result shows that the initiati...

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...

The Savannah River Site`s Groundwater Monitoring Program, second quarter 1989

Energy Technology Data Exchange (ETDEWEB)

1989-12-31

The Environmental Monitoring Section of the Environmental and Health Protection (EHP) Department administers the Savannah River Site`s Groundwater Monitoring Program. During second quarter 1989 (April--June), EHP conducted routine sampling of monitoring wells and drinking water locations. EHP collected the drinking water samples from Savannah River Site (SRS) drinking water systems supplied by wells. EHP established two sets of flagging criteria in 1986 to assist in the management of sample results. The flagging criteria aid personnel in sample scheduling, interpretation of data, and trend identification. The flagging criteria are based on detection limits, background levels in SRS groundwater, and drinking water standards. An explanation of flagging criteria for the second quarter is presented in the Flagging Criteria section of this document. All analytical results from second quarter 1989 are listed in this report, which is distributed to all waste-site custodians.

Initial formulation results for in situ grouting of a waste trench at ORNL Site No. 6

International Nuclear Information System (INIS)

Tallent, O.K.; McDaniel, E.W.; Spence, R.D.; Godsey, T.T.

1987-01-01

An investigation is being conducted by the Chemical Technology Division to assist the Environmental Sciences Division in developing a grout formulation for use in testing in situ grouting in a waste trench at ORNL Site 6. This final report satisfies the milestone of Subtack 12 entitled, ''Low Level Waste (LLW) Trench Grouting Assessment,'' which was initially issued as RAP-86-7, December 31, 1985. Grouts prepared from dry-solid blends containing Type I Portland cement, ASTM Class C or Class F fly ash, and bentonite, mixed water at ratios of 10 to 15 lb/gal, were evaluated. The grouts prepared with ASTM Class C fly ash exhibited significantly better properties than those prepared with ASTM Class F fly ash. The grouts containing ASTM Class C fly ash satisfy tentative performance criteria for the project. 8 refs., 7 tabs

The Savannah River Site`s Groundwater Monitoring Program. Fourth quarter, 1989

Energy Technology Data Exchange (ETDEWEB)

1989-12-31

The Environmental Monitoring Section of the Environmental and Health Protection (EHP) Department administers the Savannah River Site`s Groundwater Monitoring Program. During fourth quarter 1989 (October--December), EHP conducted routine sampling of monitoring wells and drinking water locations. EHP collected the drinking water samples from Savannah River Site (SRS) drinking water systems supplied by wells. EHP established two sets of flagging criteria in 1986 to assist in the management of sample results. The flagging criteria aid personnel in sample scheduling, interpretation of data, and trend identification. An explanation of flagging criteria for the fourth quarter is presented in the Flagging Criteria section of this document. All analytical results from fourth quarter 1989 are listed in this report, which is distributed to all waste-site custodians.

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

The Savannah River Site`s Groundwater Monitoring Program, third quarter 1989

Energy Technology Data Exchange (ETDEWEB)

1989-12-31

The Environmental Monitoring Section of the Environmental and Health Protection (EHP) Department administers the Savannah River Site`s Groundwater Monitoring Program. During third quarter 1989 (July--September), EHP conducted routine sampling of monitoring wells and drinking water locations. EHP collected the drinking water samples from Savannah River Site (SRS) drinking water systems supplied by wells. EHP established two sets of flagging criteria in 1986 to assist in the management of sample results. The flagging criteria do not define contamination levels; instead they aid personnel in sample scheduling, interpretation of data, and trend identification. The flagging criteria are based on detection limits, background levels in SRS groundwater, and drinking water standards. An explanation of flagging criteria for the third quarter is presented in the Flagging Criteria section of this document. All analytical results from third quarter 1989 are listed in this report, which is distributed to all waste-site custodians.

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

Toxic chemical risk acceptance criteria

International Nuclear Information System (INIS)

Craig, D.K.; Davis, J.; Lee, L.; Lein, P.; Omberg, S.

1992-01-01

This paper presents recommendations of a subcommittee of the Westinghouse M ampersand 0 Nuclear Facility Safety Committee concerning toxic chemical risk acceptance criteria. Two sets of criteria have been developed, one for use in the hazard classification of facilities, and the second for use in comparing risks in DOE non-reactor nuclear facility Safety Analysis Reports. The Emergency Response Planning Guideline (ERPG) values are intended to provide estimates of concentration ranges for specific chemicals above which exposure would be expected to lead to adverse heath effects of increasing severity for ERPG-1, -2, and -3s. The subcommittee recommends that criteria for hazard class or risk range be based on ERPGs for all chemicals. Probability-based Incremental Cancer Risk (ICR) criteria are recommended for additional analyses of risks from all known or suspected human carcinogens. Criteria are given for both on-site and off-site exposure. The subcommittee also recommends that the 5-minute peak concentration be compared with the relevant criterion with no adjustment for exposure time. Since ERPGs are available for only a limited number of chemicals, the subcommittee has developed a proposed hierarchy of concentration limit parameters for the different criteria

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...

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

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.

Multivariant design and multiple criteria analysis of building refurbishments

Energy Technology Data Exchange (ETDEWEB)

Kaklauskas, A.; Zavadskas, E. K.; Raslanas, S. [Faculty of Civil Engineering, Vilnius Gediminas Technical University, Vilnius (Lithuania)

2005-07-01

In order to design and realize an efficient building refurbishment, it is necessary to carry out an exhaustive investigation of all solutions that form it. The efficiency level of the considered building's refurbishment depends on a great many of factors, including: cost of refurbishment, annual fuel economy after refurbishment, tentative pay-back time, harmfulness to health of the materials used, aesthetics, maintenance properties, functionality, comfort, sound insulation and longevity, etc. Solutions of an alternative character allow for a more rational and realistic assessment of economic, ecological, legislative, climatic, social and political conditions, traditions and for better the satisfaction of customer requirements. They also enable one to cut down on refurbishment costs. In carrying out the multivariant design and multiple criteria analysis of a building refurbishment much data was processed and evaluated. Feasible alternatives could be as many as 100,000. How to perform a multivariant design and multiple criteria analysis of alternate alternatives based on the enormous amount of information became the problem. Method of multivariant design and multiple criteria of a building refurbishment's analysis were developed by the authors to solve the above problems. In order to demonstrate the developed method, a practical example is presented in this paper. (author)

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.

Risk assessment of soil contamination criteria

International Nuclear Information System (INIS)

King, C.M.; Marter, W.L.; Montaque, D.F.; Holton, G.A.

1987-06-01

Criteria have been developed to select radioactive and nonradioactive contaminants at waste sites detailed analysis and risk assessment. These criteria were based on soil and water quality guidelines developed by various government agencies to determine if the criteria were appropriate. We performed a risk assessment of a hypothetical site which contained radioactive and nonradioactive contaminants at levels equal to the criteria values. Risks to the public from atmospheric, surface water, and groundwater exposure pathways were examined. Health risks to the public from atmospheric releases of radioactive and nonradioactive materials from a waste at soil criteria contamination levels are low. Health risks to the maximally exposed individual to chemical carcinogens are considerably below traditional EPA action levels. And health risks to the maximally exposed individual to atmospherically released radioactive contaminants is 1.88 x 10 -7 , more than a factor of 5 less than 10 -6 . Based on our atmospheric exposure pathways analysis and risk assessment, the applied soil criteria are appropriate for screening out unimportant risk contributors to human health from atmospheric exposure pathways. 13 refs., 3 figs., 7 tabs

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

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

Site organization and site arrangement

International Nuclear Information System (INIS)

Boissonnet, B.; Macqueron, J.F.

1976-01-01

The present paper deals with criteria for the choice of a production unit or power plant site, the organization and development of a site in terms of its particular characteristics and takes into account personnel considerations in site organizations as well as the problem of integrating the architecture into the environment. (RW) [de

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)

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.

Outline of the seismic design guideline of an FBR - a tentative draft

International Nuclear Information System (INIS)

Akiyama, Hiroshi; Ohtsubo, Hideomi; Nakamura, Hideharu; Matsuura, Shinichi; Hagiwara, Yutaka; Yuhara, Tetsuo; Hirayama, Hiroshi; Kokubo, Kunio; Ooka, Yuji.

1993-01-01

Central Research Institute of Electric Power Industry (Japan) is carrying out the Demonstration Test and Research Program of Buckling of FBR (FY 1987-FY 1993). The first half of the research program was finished after establishing a seismic buckling design guideline (a tentative draft). The purpose of this paper is to describe the dynamic buckling characteristics of FBR main vessels and the outline of the rationalized buckling design guideline for seismic loadings. (orig.)

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)

Radiological criteria for underground nuclear tests

International Nuclear Information System (INIS)

Malik, J.S.; Brownlee, R.R.; Costa, C.F.; Mueller, H.F.; Newman, R.W.

1981-04-01

The radiological criteria for the conduct of nuclear tests have undergone many revisions with the current criteria being 0.17 rad for uncontrolled populations and 0.5 rad for controllable populations. Their effect upon operations at the Nevada Test Site and the current off-site protective plans are reviewed for areas surrounding the Site. The few accidental releases that have occurred are used to establish estimates of probability of release and of hazard to the population. These are then put into context by comparing statistical data on other accidents and cataclysms. The guidelines established by DOE Manual Chapter MC-0524 have never been exceeded during the entire underground nuclear test program. The probability of real hazard to off-site populations appears to be sufficiently low as not to cause undue concern to the citizenry

Radiological criteria for underground nuclear tests

Energy Technology Data Exchange (ETDEWEB)

Malik, J.S.; Brownlee, R.R.; Costa, C.F.; Mueller, H.F.; Newman, R.W.

1981-04-01

The radiological criteria for the conduct of nuclear tests have undergone many revisions with the current criteria being 0.17 rad for uncontrolled populations and 0.5 rad for controllable populations. Their effect upon operations at the Nevada Test Site and the current off-site protective plans are reviewed for areas surrounding the Site. The few accidental releases that have occurred are used to establish estimates of probability of release and of hazard to the population. These are then put into context by comparing statistical data on other accidents and cataclysms. The guidelines established by DOE Manual Chapter MC-0524 have never been exceeded during the entire underground nuclear test program. The probability of real hazard to off-site populations appears to be sufficiently low as not to cause undue concern to the citizenry.

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.

The seconding values of family business in corporate branding – a tentative model

OpenAIRE

Blombäck, Anna

2010-01-01

Why and under what circumstances can references to family business influence marketing outcomes? This paper suggests we view “family business” as a brand of its own. Through secondary brand associations, this brand can distinguish corporate as well as product brands. Tentative models present the function of family business references in relation to corporate and product communications, and firm performance. Propositions to aid further research are proposed.

The Savannah River Site`s Groundwater Monitoring Program: Fourth quarter 1991

Energy Technology Data Exchange (ETDEWEB)

Rogers, C.D. [Westinghouse Savannah River Co., Aiken, SC (United States)

1992-06-02

The Environmental Protection Department/Environmental Monitoring Section (EPD/EMS) administers the Savannah River Site`s (SRS) Groundwater Monitoring Program. During fourth quarter 1991, EPD/EMS conducted extensive sampling of monitoring wells. EPD/EMS established two sets of criteria in 1986 to assist in the management of sample results. The flagging criteria do not define contamination levels; instead, they aid personnel in sample scheduling, interpretation of data, and trend identification. Beginning in 1991, the flagging criteria are based on EPA drinking water standards and method detection limits. A detailed explanation of the current flagging criteria is presented in the Flagging Criteria section of this document. Analytical results from fourth quarter 1991 are listed in this report.

The Savannah River Site`s Groundwater Monitoring Program, second quarter 1990

Energy Technology Data Exchange (ETDEWEB)

1991-02-07

The Environmental Protection Department/Environmental Monitoring Section (EPD/EMS) administers the Savannah River Site`s (SRS) Groundwater Monitoring Program. During second quarter 1990 (April through June) EPD/EMS conducted routine sampling of monitoring wells and drinking water locations. EPD/EMS established two sets of flagging criteria in 1986 to assist in the management of sample results. The flagging criteria aid personnel in sample scheduling, interpretation of data, and trend identification. The flagging criteria are based on detection limits, background levels in SRS groundwater, and drinking water standards. An explanation of flagging criteria for the second quarter is presented in the Flagging Criteria section of this document. All analytical results from second quarter 1990 are listed in this report.

The Savannah River Site`s Groundwater Monitoring Program: Second quarter 1992

Energy Technology Data Exchange (ETDEWEB)

Rogers, C.D. [Westinghouse Savannah River Co., Aiken, SC (United States)

1992-10-07

The Environmental Protection Department/Environmental Monitoring Section (EPD/EMS) administers the Savannah River Site`s (SRS) Groundwater Monitoring Program. During second quarter 1992, EPD/EMS conducted extensive sampling of monitoring wells. EPD/EMS established two sets of criteria to assist in the management of sample results. The flagging criteria do not define contamination levels; instead, they aid personnel in sample scheduling, interpretation of data, and trend identification. Since 1991, the flagging criteria have been based on the federal Environmental Protection Agency (EPA) drinking water standards and on method detection limits. A detailed explanation of the current flagging criteria is presented in the Flagging Criteria section of this document. Analytical results from second quarter 1992 are listed in this report.

The Savannah River Site`s Groundwater Monitoring Program. Second quarter, 1991

Energy Technology Data Exchange (ETDEWEB)

1992-01-10

The Environmental Protection Department/Environmental Monitoring Section (EPD/EMS) administers the Savannah River Site`s (SRS) Groundwater Monitoring Program. During second quarter 1991 EPD/EMS conducted extensive sampling of monitoring wells. EPD/EMS established two sets of flagging criteria in 1986 to assist in the management of sample results. The flagging criteria do not define contamination levels; instead, they aid personnel in sample scheduling, interpretation of data, and trend identification. Beginning in 1991, the flagging criteria are based on EPA drinking water standards and method detection limits. A detailed explanation of the current flagging criteria is presented in the Flagging Criteria section of this document. Analytical results from second quarter 1991 are listed in this report.

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.

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.

Safety criteria for nuclear chemical plants

International Nuclear Information System (INIS)

Ball, P.W.; Curtis, L.M.

1983-01-01

Safety measures have always been required to limit the hazards due to accidental release of radioactive substances from nuclear power plants and chemical plants. The risk associated with the discharge of radioactive substances during normal operation has also to be kept acceptably low. BNFL (British Nuclear Fuels Ltd.) are developing risk criteria as targets for safe plant design and operation. The numerical values derived are compared with these criteria to see if plants are 'acceptably safe'. However, the criteria are not mandatory and may be exceeded if this can be justified. The risk assessments are subject to independent review and audit. The Nuclear Installations Inspectorate also has to pass the plants as safe. The assessment principles it uses are stated. The development of risk criteria for a multiplant site (nuclear chemical plants tend to be sited with many others which are related functionally) is discussed. This covers individual members of the general public, societal risks, risks to the workforce and external hazards. (U.K.)

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

Criteria for the PNE seismic network

International Nuclear Information System (INIS)

Pruvost, N.L.

1978-01-01

A 1976 treaty between the United States and the Soviet Union permits a local seismic network to be deployed at the site of a peaceful nuclear explosion to monitor the event. Criteria for the design and selection of the data-acquisition equipment for such a network are provided. Constraints imposed by the protocol of the treaty, the environment, and the expected properties of seismic signals (based on experiences at the Nevada Test Site) are discussed. Conclusions are drawn about the desired operating mode. Criteria for a general seismic instrumentation system are described

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

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.

Establishing the credibility of archaeoastronomical sites

Science.gov (United States)

Ruggles, Clive L. N.

2015-08-01

This is not a talk about archaeoastronomy per se, but rather about how the Astronomy and World Heritage Initiative helps us deal with archaeoastronomical sites as potential World Heritage.In 2011, an attempt to nominate a prehistoric “observatory” site onto the World Heritage List proved unsuccessful because UNESCO rejected the interpretation as statistically and archaeologically unproven. The case highlights an issue at the heart of archaeoastronomical methodology and interpretation: the mere existence of astronomical alignments in ancient sites does not prove that they were important to those who constructed and used the sites, let alone giving us insights into their likely significance and meaning. Advances in archaeoastronomy over several decades have resulted in the development of a substantial body of theory and practice (Ruggles 2014) where the most favoured interpretations depend upon integrating methods from astronomy, anthropology and other disciplines, but individual cases can still engender considerable controversy.The fact that more archaeoastronomical sites are now appearing on national tentative lists prior to their WHL nomination means that this is no longer just an academic issue; establishing the credibility of the archaeoastronomical interpretations is crucial to any assessment of their value in heritage terms.In this talk I shall describe progress that has been made within the Astronomy and World Heritage Initiative towards establishing broadly acceptable measures of archaeoastronomical credibility that make sense in the context of the heritage evaluation process. I will focus particularly, but not exclusively, on sites that are included in the Thematic Studies and/or are already included on national Tentative Lists, such as the Portuguese/Spanish seven-stone antas (Neolithic dolmens) and Chankillo in Peru (solar observation device dating to c. 300BC). I will also mention how the recognition of astronomical attributes of potential

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

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.

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.

The Savannah River site`s groundwater monitoring program: second quarter 1997

Energy Technology Data Exchange (ETDEWEB)

Rogers, C.D. [Westinghouse Savannah River Company, AIKEN, SC (United States)

1997-11-01

The Environmental Protection Department/Environmental Monitoring Section (EPD/EMS) administers the Savannah River Site`s (SRS) Groundwater Monitoring Program. During second quarter 1997, EPD/EMS conducted extensive sampling of monitoring wells. A detailed explanation of the flagging criteria is presented in the Flagging Criteria section of this document. Analytical results from second quarter 1997 are included in this report.

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)

Waste-acceptance criteria for greater confinement disposal

International Nuclear Information System (INIS)

Gilbert, T.L.; Meshkov, N.K.

1987-01-01

A methodology for establishing waste-acceptance criteria based on quantitative performance factors that characterize the confinement capabilities of a waste disposal site and facility has been developed. The methodology starts from the basic objective of protecting public health and safety by providing assurance that disposal of the waste will not result in a radiation dose to any member of the general public, in either the short or long term, in excess of an established basic dose limit. The method is based on an explicit, straight-forward, and quantitative relationship among individual risk, confinement capabilities, and waste characteristics. A key aspect of the methodology is introduction of a confinement factor that characterizes the overall confinement capability of a particular facility and can be used for quantitative assessments of the performance of different disposal sites and facilities, as well as for establishing site-specific waste acceptance criteria. Confinement factors are derived by means of site-specific pathway analyses. They make possible a direct and simple conversion of a basic dose limit into waste-acceptance criteria, specified as concentration limits on radionuclides in the waste streams and expressed in quantitative form as a function of parameters that characterize the site, facility design, waste containers, and waste form. Waste acceptance criteria can be represented visually as activity/time plots for various waste streams. These plots show the concentrations of radionuclides in a waste stream as a function of time and permit a visual, quantitative assessment of long-term performance, relative risks from different radionuclides in the waste stream, and contributions from ingrowth. 13 references, 7 figures

Waste-acceptance criteria for greater-confinement disposal

International Nuclear Information System (INIS)

Gilbert, T.L.; Meshkov, N.K.

1986-01-01

A methodology for establishing waste-acceptance criteria based on quantitative performance factors that characterize the confinement capabilities of a waste-disposal site and facility has been developed. The methodology starts from the basic objective of protecting public health and safety by providing assurance that dispsoal of the waste will not result in a radiation dose to any member of the general public, in either the short or long term, in excess of an established basic dose limit. The method is based on an explicit, straightforward, and quantitative relationship among individual risk, confinement capabilities, and waste characteristics. A key aspect of the methodology is the introduction of a confinement factor that characterizes the overall confinement capability of a particular facility and can be used for quantitative assessments of the performance of different disposal sites and facilities, as well as for establishing site-specific waste-acceptance criteria. Confinement factors are derived by means of site-specific pathway analyses. They make possible a direct and simple conversion of a basic dose limit into waste-acceptance criteria, specified as concentration limits on radionuclides in the waste streams and expressed in quantitative form as a function of parameters that characterize the site, facility design, waste containers, and waste form. Waste-acceptance criteria can be represented visually as activity/time plots for various waste streams. These plots show the concentrations of radionuclides in a waste stream as a function of time and permit a visual, quantitative assessment of long-term performance, relative risks from different radionuclides in the waste stream, and contributions from ingrowth. 13 refs

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

Radwaste characteristics and Disposal Facility Waste Acceptance Criteria

International Nuclear Information System (INIS)

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

2008-01-01

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

Assessment of candidate sites for disposal of treated effluents at the Hanford Site, Washington

International Nuclear Information System (INIS)

Davis, J.D.

1992-01-01

A rigidly defined evaluation process was used to recommend a preferred location to dispose of treated effluents from facilities in the 200 Areas of the US Department of Energy's Hanford Site in Washington State. First, siting constraints were defined based on functional design considerations and siting guidelines. Then, criteria for selecting a preferred site from among several candidates were identified and their relative importance defined. Finally, the weighted criteria were applied and a site was selected for detailed characterization by subsurface investigations

Evaluation of breastfeeding Web sites for patient education.

Science.gov (United States)

Dornan, Barbara A; Oermann, Marilyn H

2006-01-01

To evaluate the quality of Web sites on breastfeeding for patient education. Descriptive study of 30 Web sites on breastfeeding for patient education, evaluated based on the Health Information Technology Institute (HITI) criteria, readability, and eight content criteria from the American Academy of Pediatrics (AAP) policy statement on breastfeeding. The mean Flesch-Kincaid Grade Level for readability of the 30 sites was 9.2. Seven of the sites included all eight of the content criteria from the AAP, and three sites did not include any of the information recommended by the AAP content criteria. Nurses should be able to recommend best patient education materials for their patients. The five best Web sites for breastfeeding education are identified for patient teaching, and the HITI criteria are explained for nurses to learn how to evaluate Web sites for themselves and their patients.

Siting Process for HLW Repository in Japan

International Nuclear Information System (INIS)

Masuda, S.; Kitayama, K.; Umeki, H.; Naito, M.

2002-01-01

In the year 2000, the geological disposal program for high-level radioactive waste in Japan moved from the phase of generic research and development (R and D) into the phase of implementation. Following legislation entitled the ''Specified Radioactive Waste Final Disposal Act'', the Nuclear Waste Management Organization of Japan (NUMO) was established as the implementing organization. The assigned activities of NUMO include selection of the repository site, demonstration of disposal technology at the site, developing relevant licensing applications and construction, operation and closure of the repository. As the first milestone of siting process, NUMO announced to the public an overall procedure for selection of preliminary investigation areas for potential candidate sites on October 29, 2001. The procedure specifies that NUMO will solicit volunteer municipalities for preliminary investigation areas with publishing four documents as an information package. These documents are tentatively entitled ''Instructions for Application'', ''Siting Factors for the Preliminary Investigation Areas'', a ''Repository Concepts'' as well as an ''Site Investigation Community Outreach Scheme''

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

CT diagnostic criteria of branchial cysts

Energy Technology Data Exchange (ETDEWEB)

Jend, H.H.; Jend-Rossmann, I.; Techentin, E.C.

1984-09-01

Although well known, the morphology of branchial cysts has not been sufficiently presented in CT literature. In the present case report, diagnostic criteria are given, such as typical site of occurrence, ductal extension towards the supratonsillar fossa, and cystic, but occasionally soft tissue density. Differential diagnosis is given for cases which cannot be classified according to these criteria.

Nuclear power plant site selection: a case study

International Nuclear Information System (INIS)

Lugasi, Y.; Mehrez, A.; Sinuany-Stern, Z.

1985-01-01

Selecting the site for a nuclear power plant involves the evaluation of numerous criteria and the professional judgment of various experts. The Israel Atomic Energy Commission has been concerned with the problem of selecting a site for a nuclear power station. Previous studies have been performed by the commission to identify potential sites. There were initial screenings where potential sites were chosen according to various minimal criteria and international standards. Only sites that met all the criteria were chosen. A study was made to find the most preferred site among the potential sites that met all the criteria. Two mathematical approaches were used: Keeney's multiattribute utility function and Saaty's eigenvalue prioritization technique. Both models ranked the same site as the most desirable; however, the models differed in their ranking of the other sites

Idaho National Engineering Laboratory release criteria for decontamination and decommissioning

International Nuclear Information System (INIS)

Dolenc, M.R.; Case, M.J.

1986-01-01

Criteria have been developed for release of Idaho National Engineering Laboratory (INEL) facilities and land areas following decontamination and decommissioning (D and D). Decommissioning release criteria in the form of dose guidelines were proposed by the US Nuclear Regulatory Commission as early as 1980. These criteria were used on an interim basis for INEL D and D projects. However, dose guidelines alone do not adequately cover the criteria necessary to release sites for unrestricted use. In actual practice, other parameters such as pathways analyses, sampling and instrumentation techniques, and implementation procedures are required to develop the basis for unrestricted release of a site. Thus, a rigorous approach for evaluating these other parameters is needed to develop acceptable D and D release criteria. Because of the complex and sensitive nature of the dose and pathways analyses work, 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 each DOE field office, to validate technical content of the INEL site-specific document

CT diagnostic criteria of branchial cysts

International Nuclear Information System (INIS)

Jend, H.H.; Jend-Rossmann, I.; Techentin, E.C.

1984-01-01

Although well known, the morphology of branchial cysts has not been sufficiently presented in CT literature. In the present case report, diagnostic criteria are given, such as typical site of occurrence, ductal extension towards the supratonsillar fossa, and cystic, but occasionally soft tissue density. Differential diagnosis is given for cases which cannot be classified according to these criteria. (orig.) [de

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

Site Study Plan for laboratory soil mechanics, Deaf Smith County site, Texas: Revision 1

International Nuclear Information System (INIS)

1987-12-01

This Site Study Plan for laboratory soil mechanics describes the laboratory testing to be conducted on soil samples collected as part of the characterization of the Deaf Smith County site, Texas. This study provides for measurements of index, mechanical, thermal, hydrologic, chemical, and mineral properties of soils from boring throughout the site. Samples will be taken from Playa Borings/Trenching, Transportation/Utilities Foundation Borings, Repository Surface Facilities Design Foundation Borings, and Exploratory Shaft Facilities Design Foundation Borings. Data from the laboratory tests will be used for soil strata characterization, design of foundations for surface structures, design of transportation facilities and utility structures, design of impoundments, design of shaft lining, design of the shaft freeze wall, shaft permitting, performance assessment calculations, and other program requirements. A tentative testing schedule and milestone log are given. A quality assurance program will be utilized to assure that activities affecting quality are performed correctly and that appropriate documentation is maintained. 18 refs., 6 figs., 3 tabs

Site selection for new nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Rizzo, Paul C.; Dubinsky, Melissa; Tastan, Erdem Onur, E-mail: paul.rizzo@rizzoassoc.com, E-mail: melissa.dubinsky@rizzoassoc.com, E-mail: onur.tastan@rizzoassoc.com [RIZZO Associates Inc., Pittsburgh, PA (United States); Miano, Sandra C., E-mail: scm27@psu.edu [Eletrobras Termonuclear S.A. (ELETRONUCLEAR), RJ (Brazil); Pennsylvania State University, Department of Mechanical and Nuclear Engineering, State College, PA (United States)

2015-07-01

The current methodology for selecting the most advantageous site(s) for nuclear power plant (NPP) development is based on the latest evolution of protocols originally established in the 1990's by the Electric Power Research Institute (EPRI) and others for programs in the USA, and more recently by the International Atomic Energy Agency (IAEA), among others. The methodology includes protocols that account for lessons learned from both the Gen III projects and the catastrophic event at Fukushima, Japan. In general, the approach requires consideration of Exclusionary or 'fatal flaw' Criteria first, based on safety as well as significant impact to the environment or human health. Sites must meet all of these Exclusionary Criteria to be considered for NPP development. Next, the remaining sites are evaluated for Avoidance Criteria that affect primarily ease of construction and operations, which allow a ranking of sites best suited for NPP development. Finally, Suitability Criteria are applied to the potential sites to better differentiate between closely ranked sites. Generally, final selection of a Preferred and an Alternate Site will require balancing of factors, expert judgment, and client input, as sites being compared will differ in their scores associated with different Avoidance Criteria and Suitability Criteria. RIZZO Associates (RIZZO) offers in this paper a modification to this methodology for selecting the site for NPP development, which accords to the categories of Exclusionary, Avoidance and Suitability Criteria strict definitions which can be considered as Absolute Factors, Critical Factors, and Economic Factors for a more focused approach to site selection. Absolute Factors include all of the safety-related Exclusionary Criteria. Critical Factors are those that are difficult to overcome unless extraordinary mitigation measures are implemented; they have a significant impact on the ability of the project to be successful and may cause the

Site selection for new nuclear power plants

International Nuclear Information System (INIS)

Rizzo, Paul C.; Dubinsky, Melissa; Tastan, Erdem Onur; Miano, Sandra C.

2015-01-01

The current methodology for selecting the most advantageous site(s) for nuclear power plant (NPP) development is based on the latest evolution of protocols originally established in the 1990's by the Electric Power Research Institute (EPRI) and others for programs in the USA, and more recently by the International Atomic Energy Agency (IAEA), among others. The methodology includes protocols that account for lessons learned from both the Gen III projects and the catastrophic event at Fukushima, Japan. In general, the approach requires consideration of Exclusionary or 'fatal flaw' Criteria first, based on safety as well as significant impact to the environment or human health. Sites must meet all of these Exclusionary Criteria to be considered for NPP development. Next, the remaining sites are evaluated for Avoidance Criteria that affect primarily ease of construction and operations, which allow a ranking of sites best suited for NPP development. Finally, Suitability Criteria are applied to the potential sites to better differentiate between closely ranked sites. Generally, final selection of a Preferred and an Alternate Site will require balancing of factors, expert judgment, and client input, as sites being compared will differ in their scores associated with different Avoidance Criteria and Suitability Criteria. RIZZO Associates (RIZZO) offers in this paper a modification to this methodology for selecting the site for NPP development, which accords to the categories of Exclusionary, Avoidance and Suitability Criteria strict definitions which can be considered as Absolute Factors, Critical Factors, and Economic Factors for a more focused approach to site selection. Absolute Factors include all of the safety-related Exclusionary Criteria. Critical Factors are those that are difficult to overcome unless extraordinary mitigation measures are implemented; they have a significant impact on the ability of the project to be successful and may cause the

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.

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.

Predicting Ligand Binding Sites on Protein Surfaces by 3-Dimensional Probability Density Distributions of Interacting Atoms

Science.gov (United States)

Jian, Jhih-Wei; Elumalai, Pavadai; Pitti, Thejkiran; Wu, Chih Yuan; Tsai, Keng-Chang; Chang, Jeng-Yih; Peng, Hung-Pin; Yang, An-Suei

2016-01-01

Predicting ligand binding sites (LBSs) on protein structures, which are obtained either from experimental or computational methods, is a useful first step in functional annotation or structure-based drug design for the protein structures. In this work, the structure-based machine learning algorithm ISMBLab-LIG was developed to predict LBSs on protein surfaces with input attributes derived from the three-dimensional probability density maps of interacting atoms, which were reconstructed on the query protein surfaces and were relatively insensitive to local conformational variations of the tentative ligand binding sites. The prediction accuracy of the ISMBLab-LIG predictors is comparable to that of the best LBS predictors benchmarked on several well-established testing datasets. More importantly, the ISMBLab-LIG algorithm has substantial tolerance to the prediction uncertainties of computationally derived protein structure models. As such, the method is particularly useful for predicting LBSs not only on experimental protein structures without known LBS templates in the database but also on computationally predicted model protein structures with structural uncertainties in the tentative ligand binding sites. PMID:27513851

Research across the disciplines: a road map for quality criteria in empirical ethics research.

Science.gov (United States)

Mertz, Marcel; Inthorn, Julia; Renz, Günter; Rothenberger, Lillian Geza; Salloch, Sabine; Schildmann, Jan; Wöhlke, Sabine; Schicktanz, Silke

2014-03-01

Research in the field of Empirical Ethics (EE) uses a broad variety of empirical methodologies, such as surveys, interviews and observation, developed in disciplines such as sociology, anthropology, and psychology. Whereas these empirical disciplines see themselves as purely descriptive, EE also aims at normative reflection. Currently there is literature about the quality of empirical research in ethics, but little or no reflection on specific methodological aspects that must be considered when conducting interdisciplinary empirical ethics. Furthermore, poor methodology in an EE study results in misleading ethical analyses, evaluations or recommendations. This not only deprives the study of scientific and social value, but also risks ethical misjudgement. While empirical and normative-ethical research projects have quality criteria in their own right, we focus on the specific quality criteria for EE research. We develop a tentative list of quality criteria--a "road map"--tailored to interdisciplinary research in EE, to guide assessments of research quality. These quality criteria fall into the categories of primary research question, theoretical framework and methods, relevance, interdisciplinary research practice and research ethics and scientific ethos. EE research is an important and innovative development in bioethics. However, a lack of standards has led to concerns about and even rejection of EE by various scholars. Our suggested orientation list of criteria, presented in the form of reflective questions, cannot be considered definitive, but serves as a tool to provoke systematic reflection during the planning and composition of an EE research study. These criteria need to be tested in different EE research settings and further refined.

Certification Criteria for Linked Learning Pathways

Science.gov (United States)

ConnectEd: The California Center for College and Career, 2010

2010-01-01

Pathways offer a promising strategy for transforming high schools and improving student outcomes. However, to achieve these desired results, pathways must be of high quality. To guide sites in planning and implementing such pathways, a design team of experts developed the criteria outlined in this document. Sites can choose to go through a…

Le Cosmos d'Alexandre von Humboldt et La Tentation de saint Antoine de Gustave Flaubert : deux œuvres de toute une vie

Directory of Open Access Journals (Sweden)

Mary Orr

2010-12-01

Full Text Available Dans le septième et dernier tableau de La Tentation de saint Antoine de 1874, la fin célèbre est mise en contexte par une description longue et détaillée qui n’a jamais attiré l’attention critique qu’elle mérite. Cet article analyse l’importance de ce panorama du monde naturel sous la forme d’une exploration intertextuelle des passages du Cosmos d’Alexandre de Humboldt. Que Flaubert signale ses lectures de l’œuvre de Humboldt dans sa Correspondance de 1860 suggère des liens très riches entre Le Cosmos – que Humboldt désigne comme « l’œuvre de ma vie » – et la Tentation de saint Antoine définitive que Flaubert retravaillait au même moment. Cette relecture de La Tentation à travers la perspective de Humboldt souligne la place importante du Cosmos parmi les découvertes et les textes scientifiques contemporains de Flaubert, et la manière dont ceux-ci informent la vision de la vie scientifique et religieuse de son protagoniste, Antoine.In the seventh and final tableau of the Tentation de Saint Antoine of 1874, the famous finale is set in the context of a long, detailed description which has not attracted the critical attention it deserves. This article focuses on the importance of this panorama of the natural world as an intertextual exploration of passages from Kosmos by Alexander von Humboldt. The fact that Flaubert’s Correspondance of 1860 mentions his reading of Humboldt’s works suggests rich lines of investigation between Kosmos – which Humboldt calls the « work of all of life » and the final Tentation de Saint Antoine,which Flaubert was reworking at the same moment. This re-reading of the Tentation through the optic of Humboldt underscores the pivotal position of Kosmos amid the scientific discoveries and texts contemporary to Flaubert, and how these inform the vision of life of his protagonist, Antoine, as scientific and religious.

Siting of nuclear facilities. Selections from Nuclear Safety

Energy Technology Data Exchange (ETDEWEB)

Buchanan, J.R.

1976-07-01

The report presented siting policy and practice for nuclear power plants as developed in the U.S. and abroad. Twenty-two articles from Nuclear Safety on this general topic are reprinted since they provide a valuable reference source. The appendices also include reprints of some relevant regulatory rules and guides on siting. Advantages and disadvantages of novel siting concepts such as underground containment, offshore siting, and nuclear energy parks are addressed. Other topics include site criteria, risk criteria, and nuclear ship criteria.

Siting of nuclear facilities. Selections from Nuclear Safety

International Nuclear Information System (INIS)

Buchanan, J.R.

1976-07-01

The report presented siting policy and practice for nuclear power plants as developed in the U.S. and abroad. Twenty-two articles from Nuclear Safety on this general topic are reprinted since they provide a valuable reference source. The appendices also include reprints of some relevant regulatory rules and guides on siting. Advantages and disadvantages of novel siting concepts such as underground containment, offshore siting, and nuclear energy parks are addressed. Other topics include site criteria, risk criteria, and nuclear ship criteria

Development of small reactor safety criteria in Canada

International Nuclear Information System (INIS)

Ernst, P.C.; French, P.M.; Axford, D.J.; Snell, V.G.

1990-01-01

A number of new small reactor designs have been proposed in Canada over the last several years and some have reached the stage where licensing discussions have been initiated with the Atomic Energy Control Board (AECB). An inter-organizational Small Reactor Criteria (SRC) working group was formed in 1988 to propose safety and licensing criteria for these small reactors. Two levels of criteria are proposed. The first level forms a safety philosophy and the second is a set of criteria for specific reactor applications. The safety philosophy consists of three basic safety objectives together with evaluation criteria, and fourteen fundamental principles measured by specific criteria, which must be implemented to meet the safety objectives. Two of the fourteen principles are prime: defence in depth, and safety culture; the other twelve principles can be seen as deriving from them. A benefit of this approach is that the concepts of defence in depth and safety culture become well-defined. The objectives and principles are presented in the paper and their criteria are summarized. The second level of criteria, under development, will form a safety application set and will provide small reactor criteria in a number of general areas, such as regulatory process and safety assessment, as well as for specific reactor life-cycle activities, from siting through to decommissioning. The criteria are largely deterministic. However, the frequencies and consequences of postulated accidents are assessed against numerical criteria to assist in judging the acceptability of plant design, operation, and proposed siting. All criteria proposed are designed to be testable in some evidentiary fashion, readily enabling an assessment of compliance for a given proposal

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)

Development of criteria and standards for management of low-level radioactive waste

International Nuclear Information System (INIS)

Grey, A.E.; Falconer, K.L.

1980-08-01

The basic need for criteria and standards for radioactive waste management is to ensure compliance with Federal and State regulations applicable to this activity. In addition, criteria and standards can establish the parameters by which a radioactive waste disposal site is selected, the form in which the waste is to be disposed, how a disposal site is to be operated, and how that site is to be closed when it reaches the end of its useful life. For developing criteria and standards, this report discusses the nature of low-level radioactive waste and the role government agencies play in regulating its management. It describes subject areas for which criteria and standards could be developed, current and evolving requirements, and future suggested analyses

Coordinated site characterization and performance assessment - an iterative approach for the site evaluation

International Nuclear Information System (INIS)

Papp, T.; Ericsson, L.O.; Thegerstroem, C.; Almen, K.E.

1995-01-01

SKB planning for siting a deep repository involves feasibility studies in 5-10 municipalities surface based characterization and drilling on two candidate sites and detailed characterization of one site including a shaft to proposed repository depth. The selection of a site or the detailed layout of the repository defines characteristics that might influence safety in a broad sense. There is a strong ling between the safety, technical (engineering) and functional aspects. The site selection will be based on general geoscientific information, i.e. mechanical stability, ground-water chemistry, slow ground-water movements and complicating factors like high potential for mineralization. The general layout of the repository in the actual geological structure of the site must be done with regard to a number of guidelines, e.g. to hydraulically separate the parts of the repository containing the spent nuclear fuel from those for other types of long lived waste and to separate the two stages of the spent fuel repository so they can be handled separately in the licensing process. When the various parts of the repository have been tentatively located the consequence of the multiple barrier principle is that the layout of the various parts should be made with the aim to utilize the available natural barrier system at the site as well as possible. (authors). 2 refs., 3 figs., 2 tabs

An evaluation of criteria for defining tectonic, seismic, or seismotectonic provinces

International Nuclear Information System (INIS)

1980-05-01

A compilation and generic critique of the diagnostic siting criteria now in use throughout the world to delineate or approximate bounded tectonic, seismic, or seismotectonic provinces or zones, are presented. The criteria are referenced and tabulated to facilitate determination of their regulatory, scientific and practical application to siting of important engineered structures in Canada

Site study plan for routine laboratory rock mechanics, Deaf Smith County Site, Texas: Revision 1

International Nuclear Information System (INIS)

1987-12-01

This Site Study Plan for Routine Laboratory Rock Mechanics describes routine laboratory testing to be conducted on rock samples collected as part of the characterization of the Deaf Smith County site, Texas. This study plan describes the early laboratory testing. Additional testing may be required and the type and scope of testing will be dependent upon the results of the early testing. This study provides for measurements of index, hydrological, mechanical, and chemical properties with tests which are standardized and used widely in geotechnical investigations. Another Site Study Plan for Nonroutine Laboratory Rock Mechanics describes laboratory testing of samples from the site to determine mechanical, thermomechanical, and thermal properties by less widely used methods, many of which have been developed specifically for characterization of the site. Data from laboratory tests will be used for characterization of rock strata, design of shafts and underground facilities, and modeling of repository behavior in support of resolution of both preclosure and postclosure issues. A tentative testing schedule and milestone log are given. A quality assurance program will be utilized to assure that activities affecting quality are performed correctly and that appropriate documentation is maintained. 18 refs., 8 figs., 3 tabs

75 FR 12233 - New York State Prohibition of Discharges of Vessel Sewage; Receipt of Petition and Tentative...

Science.gov (United States)

2010-03-15

... protection of the water quality. EPA hereby makes a tentative affirmative determination that adequate... pumpout, if the calculation were based solely on number of slips. The availability of seven for this canal...: Connection to Municipal System Name: Village of Waterford Phone Number: (518) 237-0651 Lat/Long: 42.787608...

Siting process for disposal site of low level radiactive waste in Thailand

International Nuclear Information System (INIS)

Yamkate, P.; Sriyotha, P.; Thiengtrongjit, S.; Sriyotha, K.

1992-01-01

The radioactive waste in Thailand is composed of low level waste from the application of radioisotopes in medical treatment and industry, the operation of the 2 MW TRIGA Mark III Research Reactor and the production of radioisotopes at OAEP. In addition, the high activity of sealed radiation sources i.e. Cs-137 Co-60 and Ra-226 are also accumulated. Since the volume of treated waste has been gradually increased, the general needs for a repository become apparent. The near surface disposal method has been chosen for this aspect. The feasibility study on the underground disposal site has been done since 1982. The site selection criteria have been established, consisting of the rejection criteria, the technical performance criteria and the economic criteria. About 50 locations have been picked for consideration and 5 candidate sites have been selected and subsequent investigated. After thoroughly investigation, a definite location in Ratchburi Province, about 180 kilometers southwest of Bangkok, has been selected as the most suitable place for the near surface disposal of radioactive waste in Thailand

US Department of Energy wind turbine candidate site program: the regulatory process

Energy Technology Data Exchange (ETDEWEB)

Greene, M.R.; York, K.R.

1982-06-01

Sites selected in 1979 as tentative sites for installation of a demonstration MOD-2 turbine are emphasized. Selection as a candidate site in this program meant that the US Department of Energy (DOE) designated the site as eligible for a DOE-purchased and installed meteorological tower. The regulatory procedures involved in the siting and installation of these meteorological towers at the majority of the candidate sites are examined. An attempt is also made, in a preliminary fashion, to identify the legal and regulatory procedures that would be required to put up a turbine at each of these candidate sites. The information provided on each of these sites comes primarily from utility representatives, supplemented by conversations with state and local officials. The major findings are summarized on the following: federal requirements, state requirements, local requirements, land ownership, wind rights, and public attitudes.

Research across the disciplines: a road map for quality criteria in empirical ethics research

Science.gov (United States)

2014-01-01

Background Research in the field of Empirical Ethics (EE) uses a broad variety of empirical methodologies, such as surveys, interviews and observation, developed in disciplines such as sociology, anthropology, and psychology. Whereas these empirical disciplines see themselves as purely descriptive, EE also aims at normative reflection. Currently there is literature about the quality of empirical research in ethics, but little or no reflection on specific methodological aspects that must be considered when conducting interdisciplinary empirical ethics. Furthermore, poor methodology in an EE study results in misleading ethical analyses, evaluations or recommendations. This not only deprives the study of scientific and social value, but also risks ethical misjudgement. Discussion While empirical and normative-ethical research projects have quality criteria in their own right, we focus on the specific quality criteria for EE research. We develop a tentative list of quality criteria – a “road map” – tailored to interdisciplinary research in EE, to guide assessments of research quality. These quality criteria fall into the categories of primary research question, theoretical framework and methods, relevance, interdisciplinary research practice and research ethics and scientific ethos. Summary EE research is an important and innovative development in bioethics. However, a lack of standards has led to concerns about and even rejection of EE by various scholars. Our suggested orientation list of criteria, presented in the form of reflective questions, cannot be considered definitive, but serves as a tool to provoke systematic reflection during the planning and composition of an EE research study. These criteria need to be tested in different EE research settings and further refined. PMID:24580847

Seismic design criteria for the system 80+ advanced light water reactor

International Nuclear Information System (INIS)

Manrique, M.A.; Dermitzakis, S.N.; Gerdes, L.D.; Kennedy, R.P.; Idriss, I.M.; Cassidy, J.R.

1991-01-01

This paper presents the development of seismic design criteria in support of design certification by the Nuclear Regulatory Commission (NRC) of the ABB-Combustion Engineering's System 80+ Standard Design. The design certification effort is sponsored by the US Department of Energy (DOE). The development of the design criteria included: (a) development of the seismic control motion, (b) development of generic soil profiles for anticipated sites, (c) generation of in-structure response spectra and design loads for structures and equipment through soil-structure interaction (SSI) analyses, and (d) acceptance criteria for future construction sites

The Savannah River Site`s groundwater monitoring program. Third quarter 1990

Energy Technology Data Exchange (ETDEWEB)

1991-05-06

The Environmental Protection Department/Environmental Monitoring Section (EPD/EMS) administers the Savannah River Site`s (SRS) Groundwater Monitoring Program. During third quarter 1990 (July through September) EPD/EMS conducted routine sampling of monitoring wells and drinking water locations. EPD/EMS established two sets of flagging criteria in 1986 to assist in the management of sample results. The flagging criteria do not define contamination levels; instead they aid personnel in sample scheduling, interpretation of data, and trend identification. The flagging criteria are based on detection limits, background levels in SRS groundwater, and drinking water standards. All analytical results from third quarter 1990 are listed in this report, which is distributed to all site custodians. One or more analytes exceeded Flag 2 in 87 monitoring well series. Analytes exceeded Flat 2 for the first since 1984 in 14 monitoring well series. In addition to groundwater monitoring, EPD/EMS collected drinking water samples from SRS drinking water systems supplied by wells. The drinking water samples were analyzed for radioactive constituents.

Design criteria for advanced reactors

International Nuclear Information System (INIS)

Dennielou, Y.

1991-01-01

Design criteria for advanced reactors are discussed, including safety aspects, site selection, problems related to maintenance and possibility of repairing or replacing structures or components of a nuclear power plant, the human factor considerations. Bearing in mind that some of these criteria are the subject of consensus at international level, the author suggests to establish a table of different operator requirements, to prepare a dossier on the comparison of input data for probabilistic risk analysis, to take into consideration the means to control a severe accident from the very start of the design

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

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.

Eleven Years of Data on the Jefferson Scale of Empathy-Medical Student Version (JSE-S): Proxy Norm Data and Tentative Cutoff Scores.

Science.gov (United States)

Hojat, Mohammadreza; Gonnella, Joseph S

2015-01-01

This study was designed to provide typical descriptive statistics, score distributions and percentile ranks of the Jefferson Scale of Empathy-Medical Student version (JSE-S) of male and female medical school matriculants to serve as proxy norm data and tentative cutoff scores. The participants were 2,637 students (1,336 women and 1,301 men) who matriculated at Sidney Kimmel (formerly Jefferson) Medical College between 2002 and 2012, and completed the JSE at the beginning of medical school. Information extracted from descriptive statistics, score distributions and percentile ranks for male and female matriculants were used to develop proxy norm data and tentative cutoff scores. The score distributions of the JSE tended to be moderately skewed and platykurtic. Women obtained a significantly higher mean score (116.2 ± 9.7) than men (112.3 ± 10.8) on the JSE-S (t2,635 = 9.9, p norm data. The tentative cutoff score to identify low scorers was ≤ 95 for men and ≤ 100 for women. Our findings provide norm data and cutoff scores for admission decisions under certain conditions and for identifying students in need of enhancing their empathy. © 2015 S. Karger AG, Basel.

Tentative reference method for measurement of tritium in environmental waters. Environmental monitoring series

International Nuclear Information System (INIS)

1975-12-01

A tentative reference method for the measurement of tritium in potable and nonpotable environmental water is described. Water samples are treated with sodium hydroxide and potassium permanganate and then a water fraction is separated from interferences by distillation. Two distillation procedures are described, a simple aqueous distillation for samples from potable water sources, and an aqueous-azeotropic-benzene distillation for nonpotable water sources. Alliquots of a designated distillate fraction are measured for tritium activity by liquid scintillation detection. Distillation recovery and counting efficiency factors are determined with tritium standards. Results are reported in picocuries per milliliter

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

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.

Radiological design criteria

International Nuclear Information System (INIS)

Selby, J.M.; Andersen, B.V.; Carter, L.A.; Waite, D.A.

1977-01-01

Many new nuclear facilities are unsatisfactory from a radiation protection point of view, particularly when striving to maintain occupational exposure as low as practicable 'ALAP'. Radiation protection is achieved through physical protective features supplemented by administrative controls. Adequate physical protective feature should be achieved during construction so that supplemental administrative controls may be kept simple and workable. Many nuclear facilities fall short of adequate physical protective features, thus, remedial and sometimes awkward administrative procedures are required to safely conduct work. In reviewing the various handbooks, reports and regulations which deal with radiation protection, it may be noted that there is minimal radiological design guidance for application to nuclear facilities. A set of criteria or codes covering functional areas rather than specific nuclear facility types is badly needed. The following are suggested as functional areas to be considered: characterization of the Facility; siting and access; design exposure limits; layout (people and materials flow); ventilation and effluent control; radiation protection facilities and systems. The application of such radiological design criteria early in the design process would provide some assurance that nuclear facilities will be safe, flexible, and efficient with a minimum of costly retrofitting or administrative restrictions. Criteria which we have found helpful in these functional areas is discussed together with justification for adoption of such criteria and identification of problems which still require solution

Tentative investigation on neutron mirror fabrication with electroless nickel plating

International Nuclear Information System (INIS)

Guo, Jiang; Morita, Shin-ya; Yamagata, Yutaka; Takeda, Shin; Kato, Jun-ichi; Hino, Masahiro; Furusaka, Michihiro

2013-01-01

Neutron optics becomes highly required due to the rapid development of neutron technology. In this paper, we attempt to fabricate the neutron mirror by using a metal substrate made of electroless nickel plating to take place of glass concerning about mirror's optical performance and manufacturing method. A new manufacture process chain of neutron mirror is proposed by following the steps of fast milling and precision cutting of aluminium/stainless, electroless nickel plating, ultra-precision cutting by diamond tools, super-smooth polishing and super mirror coating to obtain high form accuracy and good surface roughness time-efficiently. Some tentative investigations are carried out. A workpiece (□ 50 x 50 mm 2 ) with flat surface made of electroless nickel plating is machined by ultra-precision cutting and polishing. The surface roughness with 0.728 nm rms (0.588 nm Ra) is acquired. According to results of reflectometry, the neutron beam can be reflected effectively with high intensity and little scattering. (author)

Environmental Restoration Disposal Facility Waste Acceptance Criteria

International Nuclear Information System (INIS)

Dronen, V.R.

1998-06-01

The Hanford Site is operated by the U. S. Department of Energy (DOE) with a primary mission of environmental cleanup and restoration. The Environmental Restoration Disposal Facility (ERDF) is an integral part of the DOE environmental restoration effort at the Hanford Site. The purpose of this document is to establish the ERDF waste acceptance criteria for disposal of materials resulting from Hanford Site cleanup activities. Definition of and compliance with the requirements of this document will enable implementation of appropriate measures to protect human health and the environment, ensure the integrity of the ERDF liner system, facilitate efficient use of the available space in the ERDF, and comply with applicable environmental regulations and DOE orders. To serve this purpose, the document defines responsibilities, identifies the waste acceptance process, and provides the primary acceptance criteria and regulatory citations to guide ERDF users. The information contained in this document is not intended to repeat or summarize the contents of all applicable regulations

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

Criteria for Drug Reimbursement Decision-Making: An Emerging Public Health Challenge in Bulgaria

Directory of Open Access Journals (Sweden)

Georgi Iskrov

2016-02-01

Full Text Available Background: During times of fiscal austerity, means of reimbursement decision-making are of particular interest for public health theory and practice. Introduction of advanced health technologies, growing health expenditures and increased public scrutiny over drug reimbursement decisions have pushed governments to consider mechanisms that promote the use of effective health technologies, while constraining costs. Aims: The study’s aim was to explore the current rationale of the drug reimbursement decision-making framework in Bulgaria. Our pilot research focused on one particular component of this process – the criteria used – because of the critical role that criteria are known to have in setting budgets and priorities in the field of public health. The analysis pursued two objectives: to identify important criteria relevant to drug reimbursement decision-making and to unveil relationships between theory and practice. Study Design: Cross-sectional study. Methods: The study was realized through a closed-ended survey on reimbursement criteria among four major public health stakeholders – medical professionals, patients, health authorities, and industry. Empirical outcomes were then cross-compared with the theoretical framework, as defined by current Bulgarian public health legislation. Analysis outlined what is done and what needs to be done in the field of public health reimbursement decision-making. Results: Bulgarian public health stakeholders agreed on 15 criteria to form a tentative optimal framework for drug reimbursement decision-making. The most apparent gap between the empirically found preferences and the official legislation is the lack of consideration for the strength of evidence in reimbursement decisions. Conclusion: Bulgarian policy makers need to address specific gaps, such as formal consideration for strength of evidence, explicit role of efficiency criteria, and means to effectively empower patient and citizen

Minimizing impacts of land use change on ecosystem services using multi-criteria heuristic analysis.

Science.gov (United States)

Keller, Arturo A; Fournier, Eric; Fox, Jessica

2015-06-01

Development of natural landscapes to support human activities impacts the capacity of the landscape to provide ecosystem services. Typically, several ecosystem services are impacted at a single development site and various footprint scenarios are possible, thus a multi-criteria analysis is needed. Restoration potential should also be considered for the area surrounding the permanent impact site. The primary objective of this research was to develop a heuristic approach to analyze multiple criteria (e.g. impacts to various ecosystem services) in a spatial configuration with many potential development sites. The approach was to: (1) quantify the magnitude of terrestrial ecosystem service (biodiversity, carbon sequestration, nutrient and sediment retention, and pollination) impacts associated with a suite of land use change scenarios using the InVEST model; (2) normalize results across categories of ecosystem services to allow cross-service comparison; (3) apply the multi-criteria heuristic algorithm to select sites with the least impact to ecosystem services, including a spatial criterion (separation between sites). As a case study, the multi-criteria impact minimization algorithm was applied to InVEST output to select 25 potential development sites out of 204 possible locations (selected by other criteria) within a 24,000 ha property. This study advanced a generally applicable spatial multi-criteria approach for 1) considering many land use footprint scenarios, 2) balancing impact decisions across a suite of ecosystem services, and 3) determining the restoration potential of ecosystem services after impacts. Copyright © 2015 The Authors. Published by Elsevier Ltd.. All rights reserved.

Decaying vs. annihilating dark matter in light of a tentative gamma-ray line

International Nuclear Information System (INIS)

Buchmüller, Wilfried; Garny, Mathias

2012-01-01

Recently reported tentative evidence for a gamma-ray line in the Fermi-LAT data is of great potential interest for identifying the nature of dark matter. We compare the implications for decaying and annihilating dark matter taking the constraints from continuum gamma-rays, antiproton flux and morphology of the excess into account. We find that higgsino and wino dark matter are excluded, also for nonthermal production. Generically, the continuum gamma-ray flux severely constrains annihilating dark matter. Consistency of decaying dark matter with the spatial distribution of the Fermi-LAT excess would require an enhancement of the dark matter density near the Galactic center

Decaying vs annihilating dark matter in light of a tentative gamma-ray line

Energy Technology Data Exchange (ETDEWEB)

Buchmueller, Wilfried; Garny, Mathias

2012-06-15

Recently reported tentative evidence for a gamma-ray line in the Fermi-LAT data is of great potential interest for identifying the nature of dark matter. We compare the implications for decaying and annihilating dark matter taking the constraints from continuum gamma-rays, antiproton flux and morphology of the excess into account. We find that higgsino and wino dark matter are excluded, also for nonthermal production. Generically, the continuum gamma-ray ux severely constrains annihilating dark matter. Consistency of decaying dark matter with the spatial distribution of the Fermi-LAT excess would require an enhancement of the dark matter density near the Galactic center.

Evaluation Criteria and Indicators of Quality for Internet Resources.

Science.gov (United States)

Wilkinson, Gene L.; And Others

1997-01-01

Most Web site rating systems overemphasize technological "bells and whistles." The University of Georgia's information quality criteria address site access and usability; resource identification and documentation; author identification; authority of author; information structure and design; relevance and scope, validity, and accuracy and…

A tentative map of discourse studies and their place in Linguistics A tentative map of discourse studies and their place in Linguistics

Directory of Open Access Journals (Sweden)

Michael Hoey

2008-04-01

Full Text Available In this paper I want to look at a range of approaches to discourse analysis with a view not to describing any of them in detail but to seeing how they relate to each other in the discipline. Surveys are a necessary evil at best; they inevitably offend by simplification and omission and ometimes by distortion as well. Despite my best endeavours, this survey is unlikely to be any exception. By way of compensation the latter part of the paper attempts a tentative characterisation of the place of discourse studies within linguistics in general and seeks to suggest why there are differences in focus between such studies; if this part of the paper offends, it will at least offend by commission. Discourse analysis has become over the past few years one of the growth areas of modern linguistics. As a result there is now far more being written every year than any person could possibly read. In estimates prepared for an inter-University working party on a computerised bibliography of ESP and Discourse Analysis, Hoey & de Escorcia reported that in 1981 an estimated 5,000 papers and 200 books were published on discourse. A consequence of this growth has been a parallel growth in terminological distinctions, reflected most schismatically perhaps in the two labels given to the sub-discipline(s we study - discourse analysis and textlinguistics. In this paper I want to look at a range of approaches to discourse analysis with a view not to describing any of them in detail but to seeing how they relate to each other in the discipline. Surveys are a necessary evil at best; they inevitably offend by simplification and omission and ometimes by distortion as well. Despite my best endeavours, this survey is unlikely to be any exception. By way of compensation the latter part of the paper attempts a tentative characterisation of the place of discourse studies within linguistics in general and seeks to suggest why there are differences in focus between such studies

Accident analysis and DOE criteria

International Nuclear Information System (INIS)

Graf, J.M.; Elder, J.C.

1982-01-01

In analyzing the radiological consequences of major accidents at DOE facilities one finds that many facilities fall so far below the limits of DOE Order 6430 that compliance is easily demonstrated by simple analysis. For those cases where the amount of radioactive material and the dispersive energy available are enough for accident consequences to approach the limits, the models and assumptions used become critical. In some cases the models themselves are the difference between meeting the criteria or not meeting them. Further, in one case, we found that not only did the selection of models determine compliance but the selection of applicable criteria from different chapters of Order 6430 also made the difference. DOE has recognized the problem of different criteria in different chapters applying to one facility, and has proceeded to make changes for the sake of consistency. We have proposed to outline the specific steps needed in an accident analysis and suggest appropriate models, parameters, and assumptions. As a result we feed DOE siting and design criteria will be more fairly and consistently applied

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

Waste acceptance criteria for the Waste Isolation Pilot Plant

International Nuclear Information System (INIS)

1996-04-01

The Waste Isolation Pilot Plant (WIPP) Waste Acceptance Criteria (WAC), DOE/WIPP-069, was initially developed by a U.S. Department of Energy (DOE) Steering Committee to provide performance requirements to ensure public health and safety as well as the safe handling of transuranic (TRU) waste at the WIPP. This revision updates the criteria and requirements of previous revisions and deletes those which were applicable only to the test phase. The criteria and requirements in this document must be met by participating DOE TRU Waste Generator/Storage Sites (Sites) prior to shipping contact-handled (CH) and remote-handled (RH) TRU waste forms to the WIPP. The WIPP Project will comply with applicable federal and state regulations and requirements, including those in Titles 10, 40, and 49 of the Code of Federal Regulations (CFR). The WAC, DOE/WIPP-069, serves as the primary directive for assuring the safe handling, transportation, and disposal of TRU wastes in the WIPP and for the certification of these wastes. The WAC identifies strict requirements that must be met by participating Sites before these TRU wastes may be shipped for disposal in the WIPP facility. These criteria and requirements will be reviewed and revised as appropriate, based on new technical or regulatory requirements. The WAC is a controlled document. Revised/changed pages will be supplied to all holders of controlled copies

Ubuntu feminism: Tentative reflections

Directory of Open Access Journals (Sweden)

Drucilla Cornell

2015-06-01

ubuntu is always sought ethically, and for the authors it underscores what we have both endorsed as ethical feminism. In this essay it is considered how ubuntu feminism could refuse the demands of patriarchy, as well as the confines of liberal feminism. The authors are interested in thinking about ubuntu in general as critique, as a critical response to the pervasiveness of a liberal legal order. Their aim is also to explore tentatively ubuntu and spatiality � how could one understand ubuntu in spatial terms, and more pertinently, how could ubuntu and ubuntu feminism relate to spatial justice? Before turning to the theoretical discussion, some of the on-the-ground history of the Ubuntu Project will be reviewed, including the Project�s attempt to build an Ubuntu Women�s Centre in Khayamandi in the Western Cape, South Africa.

Identification of the provenience of Majolica from sites in the Caribbean using neutron activation analysis

International Nuclear Information System (INIS)

Olin, J.S.; Sayre, E.V.

1975-01-01

Tin-enamelled earthenware pottery from five early Spanish Colonial sites in the Dominican Republic and Venezuela were sampled and analyzed by neutron activation analysis in an attempt to determine whether these sherds had a common source. The tentative conclusion was that although several sources were indicated for the specimens analyzed the overall similarity in composition indicated that these sources were probably closely related

Criteria for Determination of MC and A System Effectiveness

International Nuclear Information System (INIS)

Johnson, Geneva; Long, DeAnn; Albright, Ross; Wright, John

2008-01-01

The Nevada Test Site (NTS) is a test bed for implementation of the Safeguards First Principles Initiative (SFPI), a risk-based approach to Material Control and Accountability (MC and A) requirements. The Comprehensive Assessment of Safeguards Strategies (COMPASS) model is used to determine the effectiveness of safeguards systems under SFPI. Under this model, MC and A is divided into nine primary elements. Each element is divided into sub-elements. Then, each sub-element is assigned two values, effectiveness and contribution, that are used to calculate the rating. Effectiveness is a measure of sub-element implementation and how well it meets requirements. Contribution is a relative measure of the importance, and functions as a weighting factor. The COMPASS model provides the methodology for calculation of element and subelement, but not the actual criteria. Each site must develop its own criteria. For the rating to be meaningful, the effectiveness criteria must be objective and based on explicit, measurable criteria. Contribution (weights) must reflect the importance within the MC and A program. This paper details the NTS approach to system effectiveness and contribution values, and will cover the following: the basis for the ratings, an explanation of the contribution weights, and the objective, performance-based effectiveness criteria. Finally, the evaluation process will be described

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.

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

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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

Geographic factors related to site suitability of low-level waste disposal

Science.gov (United States)

Zittel, H. E.

Factors related to the site suitability of low level waste disposal sites are discussed including those which might be considered environmental and those dealing with site criteria. Possible population criteria, alternative site selection, transportation criteria, and community involvement are considered. All these factors are based on the premise that the technology exists to carry out low level waste disposal in a manner such that public health and safety can be insured. It is concluded that problems encountered in siting low level waste facilities are largely societal and political in nature.

Transferability of habitat suitability criteria for fishes in warmwater streams

Science.gov (United States)

Freeman, Mary C.; Bowen, Z.H.; Crance, J.H.

1997-01-01

We developed habitat suitability criteria and tested their transferability for nine fishes inhabiting unregulated Piedmont and Coastal Plain streams in Alabama. Cr iteria for optimal habitat were defined as ranges of depth, velocity, substrate type and cover type for which a species' suitability index (proportional abundance divided by proportional habitat availability, scaled from 0 to 1) equalled or exceeded 0.4. We evaluated the transferability of criteria between study sites by testing the null hypothesis that species occurrence in a sample was independent of whether or not the sample was taken in optimal habitat. We also tested criteria transference to a large, flow-regulated river sampled during low flow periods. Depth, velocity and most substrate criteria developed for the bronze darter Percina palmaris successfully transferred between unregulated streams and to the flow-regulated river samples. All criteria developed for a pair of closely related, allopatric darter species, Etheostoma chuckwachattee and E. jordani, transferred sucessfully when applied between species (in the unregulated sites) and to the regulated river samples. In contrast, criteria for the Alabama shiner Cyprinella callistia failed nearly all tests of transferability. Criteria for E. stigmaeum, P. nigrofasciata, an undescribed Percina species, and a pair of related, allopatric Cyprinella species transferred inconsistently. The species with good criteria transference had high suitability indices for shallow depths, fast current velocities and coarse substrates, characteristic of riffle species. We suggest that microhabitat criteria for riffle fishes are more likely to provide a transferable measure of habitat quality than criteria for fishes that, although restricted to fluvial habitats, commonly occupy a variety of pool and riffle habitats.

Decommissioning of nuclear facilities using current criteria

International Nuclear Information System (INIS)

Shum, E.Y.; Swift, J.J.; Malaro, J.C.

1991-01-01

When a licensed nuclear facility ceases operation, the US Nuclear Regulatory Commission (NRC) is responsible for ensuring that the facility and its site are decontaminated to an acceptable level so that it is safe to release that facility and site for unrestricted public use. Currently, the NRC is developing decommissioning criteria based on reducing public doses from residual contamination in soils and structures at sites released for unrestricted use to as low as is reasonably achievable (ALARA). Plans are to quantify ALARA in terms of an annual total effective dose equivalent (TEDE) to an average member of the most highly exposed population group. The NRC is working on a regulatory guidance document to provide a technical basis for translating residual contamination levels to annual dose levels. Another regulatory guide is being developed to provide guidance to the licensee on how to conduct radiological surveys to demonstration compliance with the NRC decommissioning criteria. The methods and approaches used in these regulatory guides on the decommissioning of a nuclear facility are discussed in the paper

Decision aiding techniques for site remediation

Energy Technology Data Exchange (ETDEWEB)

Van de Walle, B

1996-09-18

Decision making problems in the nuclear domain are known for their complexity since they usually involve a wide range of technical, social, and political considerations. Site restoration is a typical example of a complex nuclear decision problem, and more and more decision makers realize that they need new tools to assist in the decision making process. This paper reports on multi-criteria decision analysis, a powerful tool for handling complex decisions involving multiple criteria. The motivation to use multi-criteria decision analysis in the domain of site restoration is illustrated. New developments and challenges in this field are addressed.

Decision aiding techniques for site remediation

International Nuclear Information System (INIS)

Van de Walle, B.

1996-01-01

Decision making problems in the nuclear domain are known for their complexity since they usually involve a wide range of technical, social, and political considerations. Site restoration is a typical example of a complex nuclear decision problem, and more and more decision makers realize that they need new tools to assist in the decision making process. This paper reports on multi-criteria decision analysis, a powerful tool for handling complex decisions involving multiple criteria. The motivation to use multi-criteria decision analysis in the domain of site restoration is illustrated. New developments and challenges in this field are addressed

DOE Standard: Fire protection design criteria

International Nuclear Information System (INIS)

1999-07-01

The development of this Standard reflects the fact that national consensus standards and other design criteria do not comprehensively or, in some cases, adequately address fire protection issues at DOE facilities. This Standard provides supplemental fire protection guidance applicable to the design and construction of DOE facilities and site features (such as water distribution systems) that are also provided for fire protection. It is intended to be used in conjunction with the applicable building code, National Fire Protection Association (NFPA) Codes and Standards, and any other applicable DOE construction criteria. This Standard replaces certain mandatory fire protection requirements that were formerly in DOE 5480.7A, ''Fire Protection'', and DOE 6430.1A, ''General Design Criteria''. It also contains the fire protection guidelines from two (now canceled) draft standards: ''Glove Box Fire Protection'' and ''Filter Plenum Fire Protection''. (Note: This Standard does not supersede the requirements of DOE 5480.7A and DOE 6430.1A where these DOE Orders are currently applicable under existing contracts.) This Standard, along with the criteria delineated in Section 3, constitutes the basic criteria for satisfying DOE fire and life safety objectives for the design and construction or renovation of DOE facilities

Repository operational criteria comparative analysis

International Nuclear Information System (INIS)

Hageman, J.P.; Chowdhury, A.H.

1994-06-01

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 among the components of the regulations and impacts of any potential changes to those regulations. The ROC task addresses regulatory criteria and uncertainties related to the preclosure aspects of the geologic repository. Those parts of 10 CFR Part 60 that require routine guidance or minor changes to the rule were addressed in Hageman and Chowdhury, 1992. The ROC task shows a possible need for further regulatory clarity, by major changes to the rule, related to the design bases and siting of a geologic repository operations area and radiological emergency planning in order to assure defense-in-depth. The analyses, presented in this report, resulted in the development and refinement of regulatory concepts and their supporting rationale for recommendations for potential major changes to 10 CFR Pan 0 regulations

Could Plasmodium vivax malaria trigger malnutrition? Revisiting the Bradford Hill criteria to assess a causal relationship between two neglected problems

Directory of Open Access Journals (Sweden)

Wuelton Marcelo Monteiro

2016-06-01

Full Text Available Abstract: The benign characteristics formerly attributed to Plasmodium vivax infections have recently changed owing to the increasing number of reports of severe vivax malaria resulting in a broad spectrum of clinical complications, probably including undernutrition. Causal inference is a complex process, and arriving at a tentative inference of the causal or non-causal nature of an association is a subjective process limited by the existing evidence. Applying classical epidemiology principles, such as the Bradford Hill criteria, may help foster an understanding of causality and lead to appropriate interventions being proposed that may improve quality of life and decrease morbidity in neglected populations. Here, we examined these criteria in the context of the available data suggesting that vivax malaria may substantially contribute to childhood malnutrition. We found the data supported a role for P. vivax in the etiology of undernutrition in endemic areas. Thus, the application of modern causal inference tools, in future studies, may be useful in determining causation.

Systems based on photogrammetry to evaluation of built heritage: tentative guidelines and control parameters

Directory of Open Access Journals (Sweden)

J. Valença

2014-06-01

Full Text Available Technological innovations based on close-range imaging have arisen. The developments are related with both the advances in mathematical algorithms and acquisition equipment. This evolution allows to acquire data with large and powerful sensors and the fast and efficient processing of data. In general, the preservation of built heritage have applied these technological innovations very successfully in their different areas of intervention, namely, photogrammetry, digital image processing and multispectral image analysis. Furthermore, commercial packages of software and hardware have emerged. Thus, guidelines to best-practice procedures and to validate the results usually obtained should be established. Therefore, simple and easy to understand concepts, even for nonexperts in the field, should relate the characteristics of: (i objects under study; (ii acquisition conditions; (iii methods applied; and (iv equipment applied. In this scope, the limits of validity of the methods and a comprehensive protocol to achieve the required precision and accuracy for structural analysis is a mandatory task. Application of close-range photogrammetry to build 3D geometric models and for evaluation of displacements are herein presented. Parameters such as distance-to-object, sensor size and focal length, are correlated to the precision and accuracy achieved for displacement in both experimental and on site environment. This paper shows an early stage study. The aim consist in defining simple expressions to estimate the characteristics of the equipment and/or the conditions for image acquisition, depending on the required precision and accuracy. The results will be used to define tentative guidelines considered the all procedure, from image acquisition to final results of coordinates and displacements.

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.

Role of regulatory body related to siting

International Nuclear Information System (INIS)

Asmis, G.J.K.

1981-11-01

The role of a regulatory body, the Atomic Energy Control Board of Canada, in the siting process is discussed. A description of the Board's legal structure and safety criteria is followed by an example of the implementation of these criteria in relation to the siting of the Darlington nuclear power plant, with particular reference to external hazards such as tornadoes, earthquakes and explosions

Cleanup around an old waste site

International Nuclear Information System (INIS)

Vandergaast, G.; Moffett, D.; Lawrence, B.E.

1988-01-01

42,500 m 3 of contaminated soil were removed from off-site areas around an old, low-level radioactive waste site near Port Hope, Ontario. The cleanup was done by means of conventional excavation equipment to criteria developed by Eldorado specific to the land use around the company's waste management facility. These cleanup criteria were based on exposure analyses carried out for critical receptors in two different scenarios. The excavated soils, involving eight different landowners, were placed on the original burial area of the waste management facility. Measures were also undertaken to stabilize the soils brought on-site and to ensure that there would be no subsequent recontamination of the off-site areas

Criminal Justice Web Sites.

Science.gov (United States)

Dodge, Timothy

1998-01-01

Evaluates 15 criminal justice Web sites that have been selected according to the following criteria: authority, currency, purpose, objectivity, and potential usefulness to researchers. The sites provide narrative and statistical information concerning crime, law enforcement, the judicial system, and corrections. Searching techniques are also…

Integrating multi-criteria decision analysis for a GIS-based hazardous waste landfill sitting in Kurdistan Province, western Iran

International Nuclear Information System (INIS)

Sharifi, Mozafar; Hadidi, Mosslem; Vessali, Elahe; Mosstafakhani, Parasto; Taheri, Kamal; Shahoie, Saber; Khodamoradpour, Mehran

2009-01-01

The evaluation of a hazardous waste disposal site is a complicated process because it requires data from diverse social and environmental fields. These data often involve processing of a significant amount of spatial information which can be used by GIS as an important tool for land use suitability analysis. This paper presents a multi-criteria decision analysis alongside with a geospatial analysis for the selection of hazardous waste landfill sites in Kurdistan Province, western Iran. The study employs a two-stage analysis to provide a spatial decision support system for hazardous waste management in a typically under developed region. The purpose of GIS was to perform an initial screening process to eliminate unsuitable land followed by utilization of a multi-criteria decision analysis (MCDA) to identify the most suitable sites using the information provided by the regional experts with reference to new chosen criteria. Using 21 exclusionary criteria, as input layers, masked maps were prepared. Creating various intermediate or analysis map layers a final overlay map was obtained representing areas for hazardous waste landfill sites. In order to evaluate different landfill sites produced by the overlaying a landfill suitability index system was developed representing cumulative effects of relative importance (weights) and suitability values of 14 non-exclusionary criteria including several criteria resulting from field observation. Using this suitability index 15 different sites were visited and based on the numerical evaluation provided by MCDA most suitable sites were determined.

The Savannah River Site's Groundwater Monitoring Program

Energy Technology Data Exchange (ETDEWEB)

1989-01-01

The Environmental Monitoring Section of the Environmental and Health Protection (EHP) Department administers the Savannah River Site's Groundwater Monitoring Program. During fourth quarter 1989 (October--December), EHP conducted routine sampling of monitoring wells and drinking water locations. EHP collected the drinking water samples from Savannah River Site (SRS) drinking water systems supplied by wells. EHP established two sets of flagging criteria in 1986 to assist in the management of sample results. The flagging criteria aid personnel in sample scheduling, interpretation of data, and trend identification. An explanation of flagging criteria for the fourth quarter is presented in the Flagging Criteria section of this document. All analytical results from fourth quarter 1989 are listed in this report, which is distributed to all waste-site custodians.

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.

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.

Site study plan for non-routine laboratory rock mechanics, Deaf Smith County Site, Texas: Revision 1

International Nuclear Information System (INIS)

1987-12-01

This Site Study Plan describes the non-routine rock mechanics and thermal properties laboratory testing program planned for the characterization of site-specific geologic materials for the Deaf Smith County site, Texas. The study design provides for measurements of index, mechanical, thermomechanical, thermal and special properties for the host salt, and where appropriate, for nonhost lithologies. The types of tests which will be conducted are constant stress (creep) tests, constant strain (stress relaxation) tests, constant strain-rate tests, constant stress-rate tests, cyclic loading tests, hollow cylinder tests, uniaxial and triaxial compression tests, direct tension tests, indirect (triaxial) shear tests, thermal property determinations (conductivity, specific heat, expansivity, and diffusivity), fracture healing tests, thermal decrepitation tests, moisture content determinations, and petrographic and micromechanics analyses. Tests will be conducted at confining pressures up to 30 MPa and temperatures up to 300/degree/C. These data are used to construct mathematical models for the phenomenology of salt deformation. The models are then used in finite-element codes to predict repository response. A tentative testing schedule and milestone log are given. The duration of the testing program is expected to be approximately 5 years. 44 refs., 13 figs., 13 tabs

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

L’hallucination de la connaissance : La Tentation de saint Antoine de Flaubert

Directory of Open Access Journals (Sweden)

Dagmar Stöferle

2010-12-01

Full Text Available En représentant les démons dans la Tentation de saint Antoine, Flaubert transforme un concept chrétien par un concept psychologique élaboré par Alfred Maury, à savoir celui de l’hallucination hypnagogique. Mais ce n’est qu’à travers les différentes variantes du texte qu’on peut observer ce processus de substitution. Dans la première version de 1849, les apparitions sont toujours appelées des « démons ». Quand on lit Die christliche Mystik de Joseph von Görres que Flaubert a connu par la traduction de Charles Sainte-Foi (La mystique divine, naturelle et diabolique, Paris, 1862 on peut faire une découverte intéressante : Görres opère une distinction entre une « vraie » mystique chrétienne et une « fausse » mystique démoniaque. Ce qui là s’appelle l’extase est ici la possession par les démons. Toute la démonologie est expliquée par une conception hérétique du Mal, laquelle repose sur une fausse substantialisation, et dont il voit la manifestation la plus pure dans la religion gnostique du manichéisme. Or, comme l’on sait, Antoine est fortement attiré par la Gnose qui est, au sens grec du terme, une religion de la connaissance. Avec les adhérents de la Gnose il partage le dualisme entre un monde matériel, terrestre et un principe premier d’essence divine dans l’au-delà. Ainsi faut-il se poser la question s’il réussit finalement à surmonter le dualisme en recevant la connaissance ou bien si les dualismes continuent à persister dans le texte. La lecture de la Tentation mène à un double résultat : D’un point de vue macro-structurel, l’élément gnostique reste le non-surmontement du dualisme, lequel s’exprime sur le plan rhétorique par la résistance de l’allégorique dans le texte. En revanche, à la fin du texte, le dualisme est surmonté une seule fois dans la mise en scène d’une inversion du monisme (être-dans-le-monde et du dualisme (acosmisme.Representing the demons

Irreversibility and multiplicity: two criteria for the disposal of nuclear wastes

International Nuclear Information System (INIS)

Rochlin, G.

1976-01-01

Two criteria are suggested for comparing waste management methods: technical irreversibility and site multiplicity. These criteria can be used to reduce future risk in the face of inherent uncertainty and to provide for safe disposal without requiring guaranteed future ability to recognize, detect or repair areas of failure

Geographic factors related to site suitability of low-level waste disposal

International Nuclear Information System (INIS)

Zittel, H.E.

1981-01-01

A number of factors related to the site suitability of low-level waste disposal sites are discussed. The factors are a combination of those which might be considered environmental and those dealing with site criteria. Among the factors covered are: possible population criteria, alternative site selection, transportation criteria and community involvement considerations. All these factors are discussed in a manner based on the premise that the technology exists to carry out low-level waste disposal in a manner such that public health and safety can be insured. The conclusion of the discussion is that problems encountered in siting low-level waste facilities will be largely societal and political in nature

Site release in the decommissioning of nuclear installations

International Nuclear Information System (INIS)

Revilla, Jose Luis; Sanz, Maria Teresa; Marugan, Inmaculada; Simon, Inmaculada; Martin, Manuel; Solis, Susana; Sterling, Agustina

2008-01-01

Spanish regulatory framework for the decommissioning process of a nuclear facility ends up with a decommission statement, which releases the licence-holder of the facility from its responsibilities as an operator. It also establishes -where a restricted site release applies- the appropriate future use restrictions, and the responsible of both maintaining such restrictions and ensuring their compliance. Releasing a site implies eliminating all radiological monitoring. The Regulations, however, did not specify either the radiological conditions to be met for the site to be released, or the possibility of a partial release -with or without restrictions-. In case of restricted site release, the Regulations did not specify either the required criteria for such a release. This paper presents the main features of the Safety Instruction IS-13 'Radiological criteria for the release of nuclear facilities sites' issued recently by the Spanish Nuclear Safety Council as a new specific regulation. This Safety Instruction establishes the requirements and conditions for the release of nuclear facility sites, that is, radiological criteria on the effective dose to the public, partial release of nuclear facility sites and restricted release of nuclear facility sites. (author).

Criteria for Determination of Material Control and Accountability System Effectiveness

International Nuclear Information System (INIS)

John Wright

2008-01-01

The Nevada Test Site (NTS) is a test bed for implementation of the Safeguards First Principles Initiative (SFPI), a risk-based approach to Material Control and Accountability (MC and A) requirements. The Comprehensive Assessment of Safeguards Strategies (COMPASS) model is used to determine the effectiveness of MC and A systems under SFPI. Under this model, MC and A is divided into nine primary elements. Each element is divided into sub-elements. Then each sub-element is assigned two values, effectiveness and contribution, that are used to calculate the rating. Effectiveness is a measure of subelement implementation and how well it meets requirements. Contribution is a relative measure of the importance, and functions as a weighting factor. The COMPASS model provides the methodology for calculation of sub-element and element ratings, but not the actual criteria. Each site must develop its own criteria. For the rating to be meaningful, the effectiveness criteria must be objective and based on explicit, measurable criteria. Contribution (weights) must reflect the importance within the MC and A program. This paper details the NTS approach to system effectiveness and contribution values, and will cover the following: the basis for the ratings, an explanation of the contribution 'weights', and the objective, performance based effectiveness criteria. Finally, the evaluation process will be described

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)

Selection Methodology Approach to Preferable and Alternative Sites for the First NPP Project in Yemen

Energy Technology Data Exchange (ETDEWEB)

Kassim, Moath [Kyunghe Univ., Yongin (Korea, Republic of); Kessel, David S. [KEPCO International Nuclear Graduate School, Ulsan (Korea, Republic of)

2015-05-15

The purpose of this paper is to briefly present the methodology and results of the first siting study for the first nuclear power plant (NPP) in Yemen. In this study it has been demonstrated that there are suitable sites for specific unit/units power of 1000 MWt (about 300 MWe) nuclear power plant. To perform the site selection, a systematic selection method was developed. The method uses site-specific data gathered by literature review and expert judgement to identify the most important site selection criteria. A two-step site selection process was used. Candidate sites were chosen that meet a subset of the selection criteria that form the most important system constraints. These candidate sites were then evaluated against the full set of selection criteria using the Analytical Hierarchy Process Method (AHP). Candidate sites underwent a set of more specific siting criteria weighted by expert judgment to select preferable sites and alternatives using AHP method again. Expert Judgment method was used to rank and weight the importance of each criteria, then AHP method used to evaluate and weight the relation between criterion to criterion and between all criteria against the global weight. Then logical decision software was used to rank sites upon their weighting value.

Selection Methodology Approach to Preferable and Alternative Sites for the First NPP Project in Yemen

International Nuclear Information System (INIS)

Kassim, Moath; Kessel, David S.

2015-01-01

The purpose of this paper is to briefly present the methodology and results of the first siting study for the first nuclear power plant (NPP) in Yemen. In this study it has been demonstrated that there are suitable sites for specific unit/units power of 1000 MWt (about 300 MWe) nuclear power plant. To perform the site selection, a systematic selection method was developed. The method uses site-specific data gathered by literature review and expert judgement to identify the most important site selection criteria. A two-step site selection process was used. Candidate sites were chosen that meet a subset of the selection criteria that form the most important system constraints. These candidate sites were then evaluated against the full set of selection criteria using the Analytical Hierarchy Process Method (AHP). Candidate sites underwent a set of more specific siting criteria weighted by expert judgment to select preferable sites and alternatives using AHP method again. Expert Judgment method was used to rank and weight the importance of each criteria, then AHP method used to evaluate and weight the relation between criterion to criterion and between all criteria against the global weight. Then logical decision software was used to rank sites upon their weighting value

A Tentative Research on the Education of Teacher by "Adlerian Psychology" (II) : Using Structured Group Encounter Method

OpenAIRE

柴山, 謙二; シバヤマ, ケンジ; Shibayama, Kenji

1998-01-01

This is a tentative research on the education of teacher explored in Adlerian Psychology that used the structured group encounter method. The purpose of teacher education by Adlerian Psychology is to develop and deepen social interests of teachers, and to learn this theory and psychological techniques at school. The process of short-time workshop for teachers who were specialized in guidance for pupils was designed and documented for the education of teacher, and the author participated in th...

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...

Idaho CERCLA Disposal Facility Complex Waste Acceptance Criteria

Energy Technology Data Exchange (ETDEWEB)

W. Mahlon Heileson

2006-10-01

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

In situ bioremediation (natural attenuation) at a gas plant waste site

International Nuclear Information System (INIS)

Ginn, J.S.; Sims, R.C.

1995-01-01

A former manufactured gas plant (MGP) waste site in New York was evaluated with regard to natural attenuation of polycyclic aromatic hydrocarbons (PAHs). Parent-compound concentrations of PAHs within an aquifer plume were observed to decrease with time subsequent to source removal of coal tar. Biotransformation-potential studies indicated that indigenous microorganisms in soil from the site were capable of degrading naphthalene and phenanthrene. A biochemical metabolite of phenanthrene degradation, 1-hydroxy-2-naphthoic acid (1H2NA), was tentatively characterized in coal-tar-contaminated soil from the site-based on liquid chromatographic retention time. Kinetic information was developed for the disappearance of phenanthrene and 1H2NA in nonspiked contaminated soil at the site. The Microtox trademark bioassay was used to evaluate toxicity trends in contaminated soil at the site. Results from the Microtox trademark indicated a decreasing trend in toxicity with respect to time in contaminated site soil. Research results were evaluated with regard to the National Research Council's guidelines for evaluating in situ bioremediation, and were used to enhance site characterization and monitoring information for evaluating the role of bioremediation as part of natural attenuation of PAHs at coal-tar-contaminated sites

New foot remains from the Gran Dolina-TD6 Early Pleistocene site (Sierra de Atapuerca, Burgos, Spain).

Science.gov (United States)

Pablos, Adrián; Lorenzo, Carlos; Martínez, Ignacio; Bermúdez de Castro, José María; Martinón-Torres, María; Carbonell, Eudald; Arsuaga, Juan Luis

2012-10-01

This paper presents and describes new foot fossils from the species Homo antecessor, found in level TD6 of the site of Gran Dolina (Sierra de Atapuerca, Burgos, Spain). These new fossils consist of an almost complete left talus (ATD6-95) and the proximal three-quarters of a right fourth metatarsal (ATD6-124). The talus ATD6-95 is tentatively assigned to Hominin 10 of the TD6 sample, an adult male specimen with which the second metatarsal ATD6-70+107 (already published) is also tentatively associated. Analysis of these fossils and other postcranial remains has made possible to estimate a stature similar to those of the specimens from the Middle Pleistocene site of Sima de los Huesos (Sierra de Atapuerca, Burgos, Spain). The morphology of the TD6 metatarsals does not differ significantly from that of modern humans, Neanderthals and the specimens from Sima de los Huesos. Talus ATD6-95, however, differs from the rest of the comparative samples in being long and high, having a long and wide trochlea, and displaying a proportionally short neck. Copyright © 2012 Elsevier Ltd. All rights reserved.

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

Vicinity Property Assessments at Formerly Utilized Sites Remedial Action Program Project Sites in the New York District - 13420

Energy Technology Data Exchange (ETDEWEB)

Ewy, Ann; Hays, David [U.S. Army Corps of Engineers (United States)

2013-07-01

The Formerly Utilized Sites Remedial Action Program (FUSRAP) has addressed sites across the nation for almost 4 decades. Multiple stake holder pressures, multiple regulations, and process changes occur over such long time periods. These result in many challenges to the FUSRAP project teams. Initial FUSRAP work was not performed under Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) Records of Decision (ROD). The ROD identifies the remedy decision and ultimately the criteria to be used to release a site. Early FUSRAP projects used DOE Orders or the Uranium Mill Tailings Radiation Control Act (UMTRCA) standards. Under current RODs, regulations may differ, resulting in different cleanup criteria than that used in prior Vicinity Property (VP) remediation. The USACE, in preparation for closeout of Sites, conducts reviews to evaluate whether prior actions were sufficient to meet the cleanup criteria specified in the current ROD. On the basis of these reviews, USACE has conducted additional sampling, determined that prior actions were sufficient, or conducted additional remediation consistent with the selected remedy in the ROD. As the public pressures, regulations, and processes that the FUSRAP encounters continue to change, the program itself continues to evolve. Assessment of VPs at FUSRAP sites is a necessary step in the life cycle of our site management. (authors)

Vicinity Property Assessments at Formerly Utilized Sites Remedial Action Program Project Sites in the New York District - 13420

International Nuclear Information System (INIS)

Ewy, Ann; Hays, David

2013-01-01

The Formerly Utilized Sites Remedial Action Program (FUSRAP) has addressed sites across the nation for almost 4 decades. Multiple stake holder pressures, multiple regulations, and process changes occur over such long time periods. These result in many challenges to the FUSRAP project teams. Initial FUSRAP work was not performed under Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) Records of Decision (ROD). The ROD identifies the remedy decision and ultimately the criteria to be used to release a site. Early FUSRAP projects used DOE Orders or the Uranium Mill Tailings Radiation Control Act (UMTRCA) standards. Under current RODs, regulations may differ, resulting in different cleanup criteria than that used in prior Vicinity Property (VP) remediation. The USACE, in preparation for closeout of Sites, conducts reviews to evaluate whether prior actions were sufficient to meet the cleanup criteria specified in the current ROD. On the basis of these reviews, USACE has conducted additional sampling, determined that prior actions were sufficient, or conducted additional remediation consistent with the selected remedy in the ROD. As the public pressures, regulations, and processes that the FUSRAP encounters continue to change, the program itself continues to evolve. Assessment of VPs at FUSRAP sites is a necessary step in the life cycle of our site management. (authors)

Acceptance criteria for radioactive waste deposition

International Nuclear Information System (INIS)

Rzyski, B.M.

1989-01-01

The disposal of low-and intermediate level radioactive waste in either shallow ground or rock cavities must be subjected to special guidelines which are used by national authorities and implementing bodies when establishing and regulating respositories. These informations are given by the acceptance criteria and will depend on specific site conditions and optmized procedures. (author) [pt

Optimal Procedure for siting of Nuclear Power Plant

International Nuclear Information System (INIS)

Aziuddin, Khairiah Binti; Park, Seo Yeon; Roh, Myung Sub

2013-01-01

This study discusses on a simulation approach for sensitivity analysis of the weights of multi-criteria decision models. The simulation procedures can also be used to aid the actual decision process, particularly when the task is to select a subset of superior alternatives. This study is to identify the criteria or parameters which are sensitive to the weighting factor that can affect the results in the decision making process to determine the optimal site for nuclear power plant (NPP) site. To perform this study, we adhere to IAEA NS-R-3 and DS 433. The siting process for nuclear installation consists of site survey and site selection stages. The siting process generally consists of an investigation of a large region to select one or more candidate sites by surveying the sites. After comparing the ROI, two candidate sites are compared for final determination, which are Wolsong and Kori site. Some assumptions are taken into consideration due to limitations and constraints throughout performing this study. Sensitivity analysis of multi criteria decision models is performed in this study to determine the optimal site in the site selection stage. Logical Decisions software will be employed as a tool to perform this analysis. Logical Decisions software helps to formulate the preferences and then rank the alternatives. It provides clarification of the rankings and hence aids the decision makers on evaluating the alternatives, and finally draw a conclusion on the selection of the optimal site

Optimal Procedure for siting of Nuclear Power Plant

Energy Technology Data Exchange (ETDEWEB)

Aziuddin, Khairiah Binti; Park, Seo Yeon; Roh, Myung Sub [KEPCO International Nuclear Graduate School, Ulsan (Korea, Republic of)

2013-10-15

This study discusses on a simulation approach for sensitivity analysis of the weights of multi-criteria decision models. The simulation procedures can also be used to aid the actual decision process, particularly when the task is to select a subset of superior alternatives. This study is to identify the criteria or parameters which are sensitive to the weighting factor that can affect the results in the decision making process to determine the optimal site for nuclear power plant (NPP) site. To perform this study, we adhere to IAEA NS-R-3 and DS 433. The siting process for nuclear installation consists of site survey and site selection stages. The siting process generally consists of an investigation of a large region to select one or more candidate sites by surveying the sites. After comparing the ROI, two candidate sites are compared for final determination, which are Wolsong and Kori site. Some assumptions are taken into consideration due to limitations and constraints throughout performing this study. Sensitivity analysis of multi criteria decision models is performed in this study to determine the optimal site in the site selection stage. Logical Decisions software will be employed as a tool to perform this analysis. Logical Decisions software helps to formulate the preferences and then rank the alternatives. It provides clarification of the rankings and hence aids the decision makers on evaluating the alternatives, and finally draw a conclusion on the selection of the optimal site.

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.

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

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

Metropolitan siting: a historical perspective

International Nuclear Information System (INIS)

Bunch, D.F.

1978-09-01

The paper discusses the development and implementation of the Reactor Site Criteria and particularly the evolving posture of the agency on the subject of metropolitan siting. The review actions on nine sites are described to illustrate the various issues and positions and to clarify at least some of the bases for current practices of the NRC staff

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)

Nuclear Energy Center study. Phase II. Site suitability analysis. Final report

International Nuclear Information System (INIS)

Fellows, W.S.; Sharp, J.M.; Benator, B.I.

1978-06-01

A site screening study was conducted to identify a site or sites for detailed, site-specific study as a nuclear energy center. Using technical criteria of water requirements, geotechnical constraints, and projected load center and transmission considerations as well as environmental and institutional considerations, five potential study sites in the State of South Carolina were identified, evaluated against established criteria, and ranked according to their acceptability as potential nuclear energy center study sites. Consideration of what is ''representative'' of a site as well as the ranking score was factored into site recommendations, since the site deemed easiest to license and permit may not be the most desirable site for future study of the technical and institutional feasibility and practicality of a specific site. The sites near Lake Hartwell and the Savannah River Plant (SRP) of the Department of Energy were selected as potential study sites after consideration of the above criteria. Because the Lake Hartwell site offers the opportunity to consider institutional issues which may be more representative of other possible NEC sites, it is recommended that the Lake Hartwell site be studied to establish the feasibility and practicality of the nuclear energy concept on a site-specific basis

A database of annotated tentative orthologs from crop abiotic stress transcripts.

Science.gov (United States)

Balaji, Jayashree; Crouch, Jonathan H; Petite, Prasad V N S; Hoisington, David A

2006-10-07

A minimal requirement to initiate a comparative genomics study on plant responses to abiotic stresses is a dataset of orthologous sequences. The availability of a large amount of sequence information, including those derived from stress cDNA libraries allow for the identification of stress related genes and orthologs associated with the stress response. Orthologous sequences serve as tools to explore genes and their relationships across species. For this purpose, ESTs from stress cDNA libraries across 16 crop species including 6 important cereal crops and 10 dicots were systematically collated and subjected to bioinformatics analysis such as clustering, grouping of tentative orthologous sets, identification of protein motifs/patterns in the predicted protein sequence, and annotation with stress conditions, tissue/library source and putative function. All data are available to the scientific community at http://intranet.icrisat.org/gt1/tog/homepage.htm. We believe that the availability of annotated plant abiotic stress ortholog sets will be a valuable resource for researchers studying the biology of environmental stresses in plant systems, molecular evolution and genomics.

GIS-based multicriteria municipal solid waste landfill suitability analysis: a review of the methodologies performed and criteria implemented.

Science.gov (United States)

Demesouka, O E; Vavatsikos, A P; Anagnostopoulos, K P

2014-04-01

Multicriteria spatial decision support systems (MC-SDSS) have emerged as an integration of the geographical information systems (GIS) and multiple criteria decision analysis (MCDA) methods. GIS-based MCDA allows the incorporation of conflicting objectives and decision maker (DM) preferences into spatial decision models. During recent decades, a variety of research articles have been published regarding the implementation of methods and/or tools in a variety of real-world case studies. The article discusses, in detail, the criteria and methods that are implemented in GIS-based landfill siting suitability analysis and especially the exclusionary and non-exclusionary criteria that can be considered when selecting sites for municipal solid waste (MSW) landfills. This paper reviews 36 seminal articles in which the evaluation of candidate landfill sites is conducted using MCDA methods. After a brief description of the main components of a MC-SDSS and the applied decision rules, the review focuses on the criteria incorporated into the decision models. The review provides a comprehensive guide to the landfill siting analysis criteria, providing details regarding the utilization methods, their decision or exclusionary nature and their monotonicity.

The complete genomic sequence of a tentative new polerovirus identified in barley in South Korea.

Science.gov (United States)

Zhao, Fumei; Lim, Seungmo; Yoo, Ran Hee; Igori, Davaajargal; Kim, Sang-Min; Kwak, Do Yeon; Kim, Sun Lim; Lee, Bong Choon; Moon, Jae Sun

2016-07-01

The complete nucleotide sequence of a new barley polerovirus, tentatively named barley virus G (BVG), which was isolated in Gimje, South Korea, has been determined using an RNA sequencing technique combined with polymerase chain reaction methods. The viral genomic RNA of BVG is 5,620 nucleotides long and contains six typical open reading frames commonly observed in other poleroviruses. Sequence comparisons revealed that BVG is most closely related to maize yellow dwarf virus-RMV, with the highest amino acid identities being less than 90 % for all of the corresponding proteins. These results suggested that BVG is a member of a new species in the genus Polerovirus.

Application of a GIS Multi-Criteria Decision Analysis for the Identification of Intrinsic Suitable Sites in Costa Rica for the Application of Managed Aquifer Recharge (MAR through Spreading Methods

Directory of Open Access Journals (Sweden)

José Pablo Bonilla Valverde

2016-09-01

Full Text Available Costa Rica’s annual mean precipitation is above 3300 mm, but this precipitation is not evenly distributed in time or space, producing clear differentiated wet and dry seasons in most of the country. Droughts are also common phenomena which greatly affect the availability of water resources. Managed aquifer recharge (MAR schemes are being taken into consideration to enhance the underground water storage capacity of the country. The present study constitutes the first assessment for the identification of suitable sites for the implementation of MAR technology spreading methods (SM in Costa Rica. The suitable sites are identified by means of a geographic information system multi-criteria decision analysis (GIS-MCDA based on four criteria: hydrogeological aptitude, terrain slope, top soil texture and drainage network density. Four steps are performed in order to identify these sites: problem definition, screening for suitable areas, suitability mapping, and sensitivity analysis. The suitability map was divided in two zones after the screening: suitable and unsuitable, the first zone was further divided in five classes according to the weighted linear combination (WLC ranking. The results indicate that 61% of the country is suitable for conducting SM. This map is a tool for future implementation of MAR techniques in the country.

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)

A comparison of international criteria for the ultimate storage of radioactive wastes

International Nuclear Information System (INIS)

Mielke, H.

1985-01-01

In countries other than the Federal Republic of Germany and internationally there are no comprehensive codes referring to criteria and safety requirements except those of the IAEA and USA. In other countries there exist safety goals for the ultimate storage or for purely geological criteria. The degree of detailing regulations differs widely abroad and internationally. Safety goals abroad and internationally as well as measures for their realisation in the ultimate storage of radioactive wastes in deep geological formations are in line with the German safety goals. The IAEA refers to general aspects of geological, waste technology and ultimate storage technology criteria. In the USA, ultimate storage technology criteria have been quantified in part. The quantitative geological criteria existing in Great Britain and in the Netherlands are only relevant in as much as safety analyses must be performed for a specific site to provide evidence for the safety of this site. The comparison shows that most requirements pronounced abroad are also made for the Federal Republic of Germany. Some requirements are more specified in the Federal Republic of Germany, some are more detailed abroad. (orig./HP) [de

If you're going to be a leader, at least act like it! Prejudice towards women who are tentative in leader roles.

Science.gov (United States)

Bongiorno, Renata; Bain, Paul G; David, Barbara

2014-06-01

Role congruity theory predicts prejudice towards women who meet the agentic requirements of the leader role. In line with recent findings indicating greater acceptance of agentic behaviour from women, we find evidence for a more subtle form of prejudice towards women who fail to display agency in leader roles. Using a classic methodology, the agency of male and female leaders was manipulated using assertive or tentative speech, presented through written (Study 1, N = 167) or verbal (Study 2, N = 66) communications. Consistent with predictions, assertive women were as likeable and influential as assertive men, while being tentative in leadership reduced the likeability and influence of women, but not of men. Although approval of agentic behaviour from women in leadership reflects progress, evidence that women are quickly singled out for disapproval if they fail to show agency is important for understanding how they continue to be at a distinct disadvantage to men in leader roles. © 2013 The British Psychological Society.

Natural phenomena hazards, Hanford Site, south central Washington

International Nuclear Information System (INIS)

Tallman, A.M.

1996-01-01

This document presents the natural phenomena hazard (NPH) loads for use in implementing DOE Order 5480.28, Natural Phenomena Hazards Mitigation, at the Hanford Site in south-central Washington State. The purpose of this document is twofold: (1) summarize the NPH that are important to the design and evaluation of structures, systems, and components at the Hanford Site; (2) develop the appropriate natural phenomena loads for use in the implementation of DOE Order 5480.28. The supporting standards, DOE-STD-1020-94, Natural Phenomena Hazards Design and Evaluation Criteria for Department of Energy Facilities (DOE 1994a); DOE-STD-1022-94, Natural Phenomena Hazards Site Characteristics Criteria (DOE 1994b); and DOE-STD-1023-95, Natural Phenomena Hazards Assessment Criteria (DOE 1995) are the basis for developing the NPH loads

A TENTATIVE IDENTIFICATION OF HCN ICE ON TRITON

International Nuclear Information System (INIS)

Burgdorf, M.; Cruikshank, D. P.; Dalle Ore, C. M.; Sekiguchi, T.; Nakamura, R.; Orton, G.; Quirico, E.; Schmitt, B.

2010-01-01

Spectra of Triton between 1.8 and 5.5 μm, obtained in 2007 May and 2009 November, have been analyzed to determine the global surface composition. The spectra were acquired with the grism and the prism of the Infrared Camera on board AKARI with spectral resolutions of 135 and 22, respectively. The data from 4 to 5 μm are shown in this Letter and compared to the spectra of N 2 , CO, and CO 2 , i.e., all the known ices on this moon that have distinct bands in this previously unexplored wavelength range. We report the detection of a 4σ absorption band at 4.76 μm (2101 cm -1 ), which we attribute tentatively to the presence of solid HCN. This is the sixth ice to be identified on Triton and an expected component of its surface because it is a precipitating photochemical product of Triton's thin N 2 and CH 4 atmosphere. It is also formed directly by irradiation of mixtures of N 2 and CH 4 ices. Here we consider only pure HCN, although it might be dissolved in N 2 on the surface of Triton because of the evaporation and recondensation of N 2 over its seasonal cycle. The AKARI spectrum of Triton also covers the wavelengths of the fundamental (1-0) band of β-phase N 2 ice (4.296 μm, 2328 cm -1 ), which has never been detected in an astronomical body before, and whose presence is consistent with the overtone (2-0) band previously reported. Fundamental bands of CO and CO 2 ices are also present.

Nuclear Energy Center study. Phase II. Site suitability analysis. Final report

Energy Technology Data Exchange (ETDEWEB)

Fellows, W.S.; Sharp, J.M.; Benator, B.I.

1978-06-01

A site screening study was conducted to identify a site or sites for detailed, site-specific study as a nuclear energy center. Using technical criteria of water requirements, geotechnical constraints, and projected load center and transmission considerations as well as environmental and institutional considerations, five potential study sites in the State of South Carolina were identified, evaluated against established criteria, and ranked according to their acceptability as potential nuclear energy center study sites. Consideration of what is ''representative'' of a site as well as the ranking score was factored into site recommendations, since the site deemed easiest to license and permit may not be the most desirable site for future study of the technical and institutional feasibility and practicality of a specific site. The sites near Lake Hartwell and the Savannah River Plant (SRP) of the Department of Energy were selected as potential study sites after consideration of the above criteria. Because the Lake Hartwell site offers the opportunity to consider institutional issues which may be more representative of other possible NEC sites, it is recommended that the Lake Hartwell site be studied to establish the feasibility and practicality of the nuclear energy concept on a site-specific basis.

A proposed framework for establishing integrated cost and performance criteria for environmental technologies: A summary report

International Nuclear Information System (INIS)

1994-05-01

This document presents a summary of results of a joint EPA/DOE project aimed at establishing a suite of standard cost and performance criteria for evaluating environmental cleanup technologies for DOE sites. Project findings include: (1) decisionmakers have quite different perspectives with interests and information needs varying among decisionmaker groups, (2) previous criteria development efforts may be too narrowly focused to apply to all decisionmakers, (3) criteria must include social/political/economic interests of decisionmakers as well as site-specific variations, and (4) there are 5 core questions that all decisionmakers are likely to ask when considering a technology for use at a site. The resource developed in the project offers decisionmakers a first-time comprehensive assessment of major technology evaluation issues

Tentative characterization of precursor compounds and co-factors of pigment formation in production of 'wu mi' from Vaccinium bracteatum Thunb. Leaves.

Science.gov (United States)

Fan, Mingcong; Fan, Yihui; Huang, Weiping; Wang, Li; Li, Yan; Qian, Haifeng; Zhang, Hui; Qi, Xiguang

2018-10-01

Vaccinium bracteatum leaves (VBTL) are traditionally used in China to dye rice grains, which assume a deep blue color, named 'Wu mi'. Information on the mechanism of pigment formation is limited. In this study, CIELAB color space parameters were used to represent the color of 'Wu mi'. Precursor compounds of pigments formed during the dyeing process were identified by UPLC Q-TOF MS analysis. The changes in co-factors for pigment formation in VBTL were measured at different growth stages. The L ∗ and b ∗ values of dyed rice increased as the leaves aged, whereas a ∗ values showed irregular changes. Six compounds were tentatively identified as pigment precursors by UPLC Q-TOF MS analysis. The pH and β-glucosidase activity at different growth stages of VBTL were indicated to be crucial co-factors for pigment formation. A tentative hypothesis is presented that iridoid glycosides are hydrolyzed by acids and β-glucosidases to form a dialdehyde structure that binds covalently with amino residues of lysine side chains in rice protein molecules. Copyright © 2018 Elsevier Ltd. All rights reserved.

EPA RE-Powering Mapper: Alternative Energy Potential at Cleanup Sites

Science.gov (United States)

The U.S. Environmental Protection Agency (EPA) Office of Land and Emergency Management??s (OLEM) Office of Communications, Partnerships and Analysis (OCPA) initiated the RE-Powering America's Land Initiative to demonstrate the enormous potential that contaminated lands, landfills, and mine sites provide for developing renewable energy in the United States. EPA developed national level site screening criteria in partnership with the U.S. Department of Energy (DOE) National Renewable Energy Laboratory (NREL) for wind, solar, biomass, and geothermal facilities. While the screening criteria demonstrate the potential to reuse contaminated land for renewable energy facilities, the criteria and data are neither designed to identify the best sites for developing renewable energy nor all-inclusive. Therefore, more detailed, site-specific analysis is necessary to identify or prioritize the best sites for developing renewable energy facilities based on the technical and economic potential. Please note that these sites were only pre-screened for renewable energy potential. The sites were not evaluated for land use constraints or current on the ground conditions. Additional research and site-specific analysis are needed to verify viability for renewable energy potential at a given site.

Geographical information system (GIS) suitability analysis of radioactive waste repository site in Pahang, Malaysia

International Nuclear Information System (INIS)

Faizal Azrin Abd Razalim; Noraini Surip; Ahmad Hasnulhadi; Nazran Harun; Nurul Nadia Abd Malek; Roziah Che Musa

2010-01-01

The aim of this project is to identify a suitable site for radioactive waste repository in Pahang using remote sensing and geographical information system (GIS) technologies. There are ten parameters considered in the analysis, which divided into Selection Criteria and Exclusion Criteria. The Selection Criteria parameters consists of land use, rainfall, lineament, slope, groundwater potential and elevation while Exclusion Criteria parameters consist of urban, protected land and island. Furthermore, all parameters were integrated, given weight age and ranked for site selection evaluation in GIS environment. At the first place, about twelve sites have been identified as suitable sites for radioactive waste repository throughout the study area. These sites were further analysed by ground checking on the physical setting including geological, drainage, and population density in order to finalise three most suitable sites for radioactive waste repository. (author)

Association of atopy and tentative diagnosis of skin cancer - results from occupational skin cancer screenings.

Science.gov (United States)

Schäfer, I; Mohr, P; Zander, N; Fölster-Holst, R; Augustin, M

2017-12-01

The relationship between atopic conditions and carcinoma of the skin has been described inconsistently. Population-based data providing information on atopic diseases as well as on skin cancer are sparse. To determine the correlation between atopy and prevalence of precanceroses, non-melanoma skin cancer and malignant melanoma (MM), while taking into account known risk factors for skin cancer. Data from occupational skin cancer screenings were analysed in a cross-sectional study. Dermatologists performed whole body examinations and collected medical histories. Subjects comprised all employees (16-70 years) examined from 2006 to 2014. 'Atopy' was defined by clinical screening diagnosis and/or by participant-reported, pre-existing atopic dermatitis, allergic asthma or other specified allergies confirmed by a physician. Tentative screening diagnoses of skin cancer related to actinic keratosis, basal cell carcinoma and malignant melanoma. The study cohort comprised 90 265 employees (mean age 43 ± 11 years, 58.5% male), 30.7% of whom were ever diagnosed with an atopic disease. Persons with atopic conditions recorded in their medical history and at the time of screening had a significantly lower prevalence of actinic keratosis (AK), basal cell carcinoma (BCC) and MM. After controlling for age, sex and relevant risk factors (skin type, childhood sun burns), atopy remained significantly protective against BCC (OR 0.77) and MM (OR 0.53). Design limitations of the study include that all findings of skin cancer were based on clinical examination only and must therefore be considered tentative diagnoses. Furthermore, owing to the cross-sectional study design, causal pathways cannot be proven. However, analyses of data from such a large and general population-based cohort afford valuable insights into the relationship between atopic diseases and skin cancer. They provide the grounds for prospective cohort studies to evaluate and dissect the underlying mechanism. © 2017

Multi-criteria decision analysis integrated with GIS for radio ...

African Journals Online (AJOL)

Multi-criteria decision analysis integrated with GIS for radio astronomical observatory site selection in peninsular of Malaysia. R Umar, Z.Z. Abidin, Z.A. Ibrahim, M.K.A. Kamarudin, S.N. Hazmin, A Endut, H Juahir ...

Siting of a low-level radioactive waste disposal facility

International Nuclear Information System (INIS)

Alvarado, R.A.

1983-01-01

The Texas Low-Level Radioactive Waste Disposal Authority was established by the 67th Legislature to assure safe and effective disposal of the state's low-level radioactive waste. The Authority operates under provisions of the Texas Low-Level Radioactive Waste Disposal Authority Act, VACS 4590f-1. In Texas, low-level radioactive waste is defined as any radioactive material that has a half-life of 35 years or less or that has less than 10 nanocuries per gram of transuranics, and may include radioactive material not excluded by this definition with a half-life or more than 35 years if special disposal criteria are established. Prior to beginning the siting study, the Authority developed both exclusionary and inclusionary criteria. Major requirements of the siting guidelines are that the site shall be located such that it will not interfere with: (1) existing or near-future industrial use, (2) sensitive environmental and ecological areas, and (3) existing and projected population growth. Therefore, the site should be located away from currently known recoverable mineral, energy and water resources, population centers, and areas of projected growth. This would reduce the potential for inadvertent intruders, increasing the likelihood for stability of the disposal site after closure. The identification of potential sites for disposal of low-level radioactive waste involves a phased progression from statewide screening to site-specific exploration, using a set of exclusionary and preferential criteria to guide the process. This methodology applied the criteria in a sequential manner to focus the analysis on progressively smaller and more favorable areas. The study was divided into three phases: (1) statewide screening; (2) site identification; and (3) preliminary site characterization

Procedures for evaluation of vibratory ground motions of soil deposits at nuclear power plant sites

International Nuclear Information System (INIS)

1975-06-01

According to USNRC requirements set forth in Appendix A, 10 CFR, Part 100, vibratory ground motion criteria for a nuclear plant must be based on local soil conditions, as well as on the seismicity, geology, and tectonics of the region. This report describes how such criteria can be developed by applying the latest technology associated with analytical predictions of site-dependent ground motions and with the use of composite spectra obtained from the current library of strong motion records. Recommended procedures for defining vibratory ground motion criteria contain the following steps: (1) geologic and seismologic studies; (2) site soils investigations; (3) site response sensitivity studies; (4) evaluation of local site response characteristics; (5) selection of site-matched records; and (6) appraisal and selection of seismic input criteria. An in-depth discussion of the engineering characteristics of earthquake ground motions including parameters used to characterize earthquakes and strong motion records, geologic factors that influence ground shaking, the current strong motion data base, and case histories of the effects of past earthquake events is presented. Next, geotechnical investigations of the seismologic, geologic, and site soil conditions required to develop vibratory motion criteria are briefly summarized. The current technology for establishing vibratory ground motion criteria at nuclear plant sites, including site-independent and site-dependent procedures that use data from strong motion records and from soil response analyses is described. (auth)

Identifying criteria and establishing parameters for forest-based ecotourism in Northern Ontario, Canada

Science.gov (United States)

Stephen W. Boyd; Richard W. Butler; Wolfgang Haider

1995-01-01

This paper identifies the following criteria as indicators for ecotourism suitability within a Northern Ontario context: naturalness, wildlife, cultural heritage, landscape and community. A methodology is proposed which uses Geographical Information Systems (GIS) to identify ecotourism sites by linking criteria deemed important with actual landscape characteristics of...

Incorporating cumulative effects into environmental assessments of mariculture: Limitations and failures of current siting methods

International Nuclear Information System (INIS)

King, Sarah C.; Pushchak, Ronald

2008-01-01

Assessing and evaluating the cumulative impacts of multiple marine aquaculture facilities has proved difficult in environmental assessment. A retrospective review of 23 existing mariculture farms in southwestern New Brunswick was conducted to determine whether cumulative interactions would have justified site approvals. Based on current scientific evidence of cumulative effects, six new criteria were added to a set of far-field impacts and other existing criteria were expanded to include regional and cumulative environmental impacts in Hargrave's [Hargrave BT. A traffic light decision system for marine finfish aquaculture siting. Ocean Coast Manag 2002; 45:215-35.] Traffic Light Decision Support System (DSS) presently used in Canadian aquaculture environmental assessments. Before mitigation, 19 of the 23 sites failed the amended set of criteria and after considering mitigation, 8 sites failed. Site and ecosystem indices yielded varying site acceptability scores; however, many sites would not have been approved if siting decisions had been made within a regional management framework and cumulative impact criteria were considered in the site evaluation process

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

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.

Management strategy for site characterization at candidate HLW repository sites

International Nuclear Information System (INIS)

Bartlett, J.W.

1988-01-01

This paper describes a management strategy for HLW repository site characterization which is aimed at producing an optimal characterization trajectory for site suitability and licensing evaluations. The core feature of the strategy is a matrix of alternative performance targets and alternative information-level targets which can be used to allocate and justify program effort. Strategies for work concerning evaluation of expected and disrupted repository performance are distinguished, and the need for issue closure criteria is discussed

Working draft regulatory guide on release criteria for decommissioning: NRC staff's draft for comment

International Nuclear Information System (INIS)

Daily, M.C.; Huffert, A.; Cardile, F.; Malaro, J.C.

1994-08-01

The Nuclear Regulatory Commission's (NRC) regulations in 10 CFR 20 are being amended to include radiological criteria for decommissioning of lands and structures at nuclear facilities. 10 CFR Part 20, Subpart E establishes criteria for the remediation of contaminated sites or facilities that will allow their release for future use with or without restrictions. The criteria include a Total Effective Dose Equivalent (TEDE) limit of 15 mrem/year (0.15 mSv/y) that should not be exceeded by an average individual among those who could potentially receive the greatest exposure from any residual activity within a facility or on a site. The criteria also require a licensee to reduce any residual radioactivity to as-low-as-reasonably-achievable (ALARA) levels. This staff draft guide describes acceptable procedures for determining the predicted dose level (PDL) from any residual radioactivity at the site. It describes the basic features of the calculational models and the associated default assumptions and parameter values the NRC staff would find acceptable in calculating PDLs. Appendices A, B, and C provide numerical values that can be used to estimate the dose from residual radioactivity remaining at a site. Since 10 CFR Part 20, Subpart E introduces several new concepts, definitions and discussions are included in a regulatory position concepts section of the guide to assist licensees in understanding some of the philosophy underlying the rule

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

Position paper: Seismic design criteria

International Nuclear Information System (INIS)

Farnworth, S.K.

1995-01-01

The purpose of this paper is to document the seismic design criteria to be used on the Title 11 design of the underground double-shell waste storage tanks and appurtenant facilities of the Multi-Function Waste Tank Facility (MWTF) project, and to provide the history and methodologies for determining the recommended Design Basis Earthquake (DBE) Peak Ground Acceleration (PGA) anchors for site-specific seismic response spectra curves. Response spectra curves for use in design are provided in Appendix A

Research on high level radioactive waste repository seismic design criteria

International Nuclear Information System (INIS)

Jing Xu

2012-01-01

Review seismic hazard analysis principle and method in site suitable assessment process of Yucca Mountain Project, and seismic design criteria and seismic design basis in primary design process. Demonstrated spatial character of seismic hazard by calculated regional seismic hazard map. Contrasted different level seismic design basis to show their differences and relation. Discussed seismic design criteria for preclosure phrase of high level waste repository and preference goal under beyond design basis ground motion. (author)

Waste site grouping for 200 Areas soil investigations

International Nuclear Information System (INIS)

1997-01-01

The purpose of this document is to identify logical waste site groups for characterization based on criteria established in the 200 Areas Soil Remediation Strategy (DOE-RL 1996a). Specific objectives of the document include the following: finalize waste site groups based on the approach and preliminary groupings identified in the 200 Areas Soil Remediation Strategy; prioritize the waste site groups based on criteria developed in the 200 Areas Soil Remediation Strategy; select representative site(s) that best represents typical and worse-case conditions for each waste group; develop conceptual models for each waste group. This document will serve as a technical baseline for implementing the 200 Areas Soil Remediation Strategy. The intent of the document is to provide a framework, based on waste site groups, for organizing soil characterization efforts in the 200 Areas and to present initial conceptual models

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.

Analysis of air toxics, criteria pollutants and meteorological monitoring data in Valdez, Alaska

International Nuclear Information System (INIS)

Stopenhagen, K.W.; Kester, R.A.; Caniparoli, D.G.; Gravely, R.J.

1991-01-01

An ambient monitoring network began operation in Valdez, Alaska in August 1990. The twelve month study for the Alyeska Pipeline Service Company will gather data for regulatory compliance, risk assessment dispersion modeling. The network consists of seven sites. Four sites measure selected species of VOCs by laboratory grade gas chromatographs. The GCS yield hourly concentrations, special plumbing, valving and computer software enable unattended and automated operation. Chromatography is performed by flame ionization detector. Pollutants measured are benzene, ethyl-benzene, toluene and xylenes. Criteria pollutants are measured at four sites; one of which is for permit compliance. VOC and Criteria data presented will show site-by-site concentration comparisons, relate values to ambient standards, and applicability of previous modeling results. A discussion of the use of lab-grade gas chromatographs in the field for automated continuous sampling will be included. Meteorological data discussion will analyze circulation patterns within the fjord for patterns such as cross fjord transport and terrain induced flow regimes

The Savannah River Site's Groundwater Monitoring Program, second quarter 1989

Energy Technology Data Exchange (ETDEWEB)

1989-01-01

The Environmental Monitoring Section of the Environmental and Health Protection (EHP) Department administers the Savannah River Site's Groundwater Monitoring Program. During second quarter 1989 (April--June), EHP conducted routine sampling of monitoring wells and drinking water locations. EHP collected the drinking water samples from Savannah River Site (SRS) drinking water systems supplied by wells. EHP established two sets of flagging criteria in 1986 to assist in the management of sample results. The flagging criteria aid personnel in sample scheduling, interpretation of data, and trend identification. The flagging criteria are based on detection limits, background levels in SRS groundwater, and drinking water standards. An explanation of flagging criteria for the second quarter is presented in the Flagging Criteria section of this document. All analytical results from second quarter 1989 are listed in this report, which is distributed to all waste-site custodians.

The influence of quality criteria on parents' evaluation of medical web-pages: an Italian randomised trial.

Science.gov (United States)

Currò, Vincenzo; Buonuomo, Paola Sabrina; Zambiano, Annaluce; Vituzzi, Andrea; Onesimo, Roberta; D'Atri, Alessandro

2007-01-01

The aim of this study is to verify the usefulness for parents of a web evaluation framework composed of ten quality criteria to improve their ability to assess the quality level of medical web sites. We conducted a randomised controlled trial that included two groups of parents who independently evaluated five paediatric web sites by filling out two distinct questionnaires: group A with the evaluation framework, group B without it. 40 volunteers were recruited from parents referring to the General Paediatrics Out-patients Department who satisfied the following eligibility criteria: Internet users, at least 1 child under 12 months old, no professional skill in Internet and medicine. The survey was taken between February 2, 2000 and March 22, 2000. Parents evaluated each web site and assigned a score, compared with a gold standard created by a group of experts. Suggesting evaluation criteria to parents seem useful for an improvement of their ability to evaluate web sites.

Low-level siting, Edgemont, South Dakota

International Nuclear Information System (INIS)

Andrews, L.J.

1984-01-01

The siting of a low-level radwaste disposal facility and characterization activities to date in Edgemont, South Dakota are discussed. By using past and present experience the author sets forth the major problem, the social and political considerations, community acceptance, media and public officials' attitudes, criteria for acceptance and significance of countywide vote in support of facility. Characterization activities, site selection planning and criteria, above-grade and below-grade technical evaluation, NRC interface, 10 CFR Part 61 related to technical work, as well as community acceptance and license application are covered. The paper deals with specific problems, solutions and ongoing activities

Site Selection for Surplus Plutonium Disposition Facilities at the Savannah River Site

International Nuclear Information System (INIS)

Wike, L.D.

2000-01-01

A site selection study was conducted to evaluate locations for the proposed Surplus Plutonium Disposition Facilities. Facilities to be located include the Mixed Oxide (MOX) Fuel Fabrication Facility, the Pit Disassembly and Conversion Facility (PDCF), and the Plutonium Immobilization Project (PIP) facility. Objectives of the study include: (1) Confirm that the Department of Energy (DOE) selected locations for the MOX and PDCF were suitable based on selected siting criteria, (2) Recommend a site in the vicinity of F Area that is suitable for the PIP, and (3) Identify alternative suitable sites for one or more of these facilities in the event that further geotechnical characterization or other considerations result in disqualification of a currently proposed site

Plutonium contamination at Maralinga - dosimetry and clean-up criteria

International Nuclear Information System (INIS)

Cooper, M.B.; Martin, L.J.; O'Brien, R.S.; Williams, G.A.

1998-01-01

An area of South Australia remained contaminated following British nuclear weapons tests at Maralinga during 1955 - 1963. Of importance is the long-lived 239-Pu of which some 24 kg was explosively dispersed in several 'minor trials'. The extent, quantities and physical characteristics of the plutonium have been assessed and estimates of dose, dominated by the inhalation pathway in the critical group of Aborigines living a semi-traditional lifestyle, have been made for potential occupants. Rehabilitation of the most contaminated areas is underway, involving scraping of surface soil and burial at depth on site. Dosimetry, together with social and economic factors, underpins the setting of clean-up criteria in terms of activity concentrations averaged over large areas and permissible concentrations of contaminated particles. The possibility of intentional behaviour such as fragment scavenging has also influenced limits on particulate contamination.The standard for this intervention is that the annual committed dose, for any scenario involving permanent occupancy by semi-traditional Aborigines, will be less than 5 mSv. In fact, following the clean-up, annual doses are not expected to exceed 1 mSv for all realistic scenarios. The possibility of intentional behaviour, such as fragment scavenging, has led to limits on particulate contamination. Three plutonium-contaminated sites have been treated by soil-removal. At Taranaki, the most contaminated site, by limiting the activity of the remaining soil to below about 400 kBq/m2 of 239Pu, and by limiting occupancy factors to those typical of hunting activities in a particular location (0.8%), the dose criteria will be met. An area of about 1.5 km 2 has been treated by removal of surface soil at Taranaki. At the other two sites, with no occupancy constraints, more stringent soil-removal criteria have been applied

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

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.

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

Potential sites for a spent unreprocessed fuel facility (SURFF), southwesten part of the Nevada Test Site

International Nuclear Information System (INIS)

Hoover, D.L.; Eckel, E.B.; Ohl, J.P.

1978-01-01

In the absence of specific criteria, the topography, geomorphology, and geology of Jackass Flats and vicinity in the southwestern part of the Nevada Test Site are evaluated by arbitrary guidelines for a Spent Unreprocessed Fuel Facility. The guidelines include requirements for surface slopes of less than 5%, 61 m of alluvium beneath the site, an area free of active erosion or deposition, lack of faults, a minimum area of 5 km 2 , no potential for flooding, and as many logistical support facilities as possible. The geology of the Jackass Flats area is similar to the rest of the Nevada Test Site in topographic relief (305-1,200 m), stratigraphy (complexly folded and faulted Paleozoic sediments overlain by Tertiary ash-flow tuffs and lavas overlain in turn by younger alluvium), and structure (Paleozoic thrust faults and folds, strike-slip faults, proximity to volcanic centers, and Basin and Range normal faults). Of the stratigraphic units at the potential Spent Unreprocessed Fuel Facility site in Jackass Flats, only the thickness and stability of the alluvium are of immediate importance. Basin and Range faults and a possible extension of the Mine Mountain fault need further investigation. The combination of a slope map and a simplified geologic and physiographic map into one map shows several potential sites for a Spent Unreprocessed Fuel Facility in Jackass Flats. The potential areas have slopes of less than 5% and contain only desert pavement or segmented pavement--the two physiographic categories having the greatest geomorphic and hydraulic stability. Before further work can be done, specific criteria for a Spent Unreprocessed Fuel Facility site must be defined. Following criteria definition, potential sites will require detailed topographic and geologic studies, subsurface investigations (including geophysical methods, trenching, and perhaps shallow drilling for faults in alluvium), detailed surface hydrologic studies, and possibly subsurface hydrologic studies

Seismic design criteria for the Clinch River Breeder Reactor Plant

International Nuclear Information System (INIS)

Morrone, A.; Bitner, J.L.; Sigal, G.B.

1975-01-01

The general criteria for seismic resistant design for structures, systems and components of the Clinch River Breeder Reactor Plant (CRBRP) are presented and discussed. Site dependency of the maximum ground accelerations for the Operating Basis Earthquake and the Safe Shutdown Earthquake is described from the viewpoint of historical records and geological and seismological studies for the CRBRP site. The respective ground response spectra are derived by normalization of the latest AEC Regulatory standard shapes to these maximum ground accelerations. Modeling and analytical techniques and requirements are given. In addition, loading conditions and categories, loading combinations, earthquake direction effects and allowable damping values are defined. A discussion of the testing criteria which considers both single and multiple frequency test motions, and basic test procedures for single frequency sine beat testing is presented. (U.S.)

Nonreactor nuclear facilities: standards and criteria guide

International Nuclear Information System (INIS)

Brynda, W.J.; Junker, L.; Karol, R.C.; Lobner, P.R.; Goldman, L.A.

1981-09-01

This guide is a source document that identifies standards, codes, and guides that address the nuclear safety considerations pertinent to nuclear facilities as defined in DOE Order 5480.1, Chapter V, Safety of Nuclear Facilities. The guidance and criteria provided are directed toward areas of safety usually addressed in a Safety Analysis Report. The areas of safety include, but are not limited to, siting, principal design criteria and safety system design guidelines, radiation protection, accident analysis, and quality assurance. The guide is divided into two sections: general guidelines and appendices. Those guidelines that are broadly applicable to most nuclear facilities are presented in the general guidelines. These general guidelines may have limited applicability to subsurface facilities such as waste repositories. Guidelines specific to the various types or categories of nuclear facilities are presented in the appendices. These facility-specific appendices provide guidelines and identify standards and criteria that should be considered in addition to, or in lieu of, the general guidelines

Nonreactor nuclear facilities: Standards and criteria guide

International Nuclear Information System (INIS)

Brynda, W.J.; Scarlett, C.H.; Tanguay, G.E.; Lobner, P.R.

1986-09-01

This guide is a source document that identifies standards, codes, and guides that address the nuclear safety considerations pertinent to nuclear facilities as defined in DOE 5480.1A, Chapter V, ''Safety of Nuclear Facilities.'' The guidance and criteria provided is directed toward areas of safety usually addressed in a Safety Analysis Report. The areas of safety include, but are not limited to, siting, principal design criteria and safety system design guidelines, radiation protection, accident analysis, conduct of operations, and quality assurance. The guide is divided into two sections: general guidelines and appendices. Those guidelines that are broadly applicable to most nuclear facilities are presented in the general guidelines. Guidelines specific to the various types or categories of nuclear facilities are presented in the appendices. These facility-specific appendices provide guidelines and identify standards and criteria that should be considered in addition to, or in lieu of, the general guidelines. 25 figs., 62 tabs

Physical criteria for the design and assessment of restoration schemes in the United Kingdom

International Nuclear Information System (INIS)

Humphries, R.N.; McQuire, G.E.

1994-01-01

The restoration of colliery wastes and open pit coal sites in the United Kingdom (UK) is undertaken according to a land use strategy plan and detailed specifications that have been agreed upon with the planning authorities. For two of the major land uses in the UK, agriculture and forestry, data on physical criteria (climate, site features and soils) are available to assist in the planning and design of land use strategies and specification of restoration treatments. Similar criteria could also be developed for the restoration of semi natural vegetation and habitats for landscape, wildlife, and amenity uses. Three examples are described illustrating the use of the physical criteria in the design of schemes, the specification of treatments, and the assessment of achievements

Hanford Site Transuranic (TRU) Waste Certification Plan

Energy Technology Data Exchange (ETDEWEB)

GREAGER, T.M.

1999-09-09

The Hanford Site Transuranic Waste Certification Plan establishes the programmatic framework and criteria within which the Hanford Site ensures that contract-handled TRU wastes can be certified as compliant with the WIPP WAC and TRUPACT-II SARP.

Cultural Elements and Universality in the Process of Globalization : A Tentative Approach to a Theorization of Culture in sociology

OpenAIRE

丸山, 哲央

2002-01-01

"The main purpose of this paper is to propose a conceptual scheme for the analysis of cultural globalization in accordance with the Parsonian notion of culture, and to point out some problematic issues caused by cultural globalization: the unbalanced development of cultural elements and the prevalence of the pseudo universality of a dominant particular culture. With respect to the recent trend of ‘cultural turn’ in social sciences, this is a tentative approach to a theorization of culture as ...

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

Study of a conceptual nuclear energy center at Green River, Utah. Site selection

International Nuclear Information System (INIS)

1981-08-01

The siting requirements are described for a NEC. The methodology used, primary and secondary screening criteria and the results and conclusions are also presented. Appended to the report are detailed discussions of two siting factors, and evaluation of Nuclear Regulatory Commission (NRC) demographic siting criteria and a fatal flaw analyses for terrestrial and aquatic ecology

Study of a conceptual nuclear energy center at Green River, Utah. Site selection

Energy Technology Data Exchange (ETDEWEB)

1981-08-01

The siting requirements are described for a NEC. The methodology used, primary and secondary screening criteria and the results and conclusions are also presented. Appended to the report are detailed discussions of two siting factors, and evaluation of Nuclear Regulatory Commission (NRC) demographic siting criteria and a fatal flaw analyses for terrestrial and aquatic ecology.

Site selection procedure for high level radioactive waste disposal in Bulgaria

International Nuclear Information System (INIS)

Evstatiev, D.; Vachev, B.

1993-01-01

A combined site selection approach is implemented. Bulgaria's territory has been classified in three categories, presented on a 1:500000 scale map. The number of suitable sites has been reduced to 20 using the method of successive screening. The formulated site selection problem is a typical discrete multi-criteria decision making problem under uncertainty. A 5-level procedure using Expert Choice Rating and relative models is created. It is a part of a common procedure for evaluation and choice of variants for high level radwaste disposal construction. On this basis 7-8 more preferable sites are demonstrated. A new knowledge and information about the relative importance of the criteria and their subsets, about the level of criteria uncertainty and the reliability are gained. It is very useful for planning and managing of the next final stages of the site selection procedure. 7 figs., 8 refs., 4 suppls. (author)

Hanford Site Transuranic (TRU) Waste Certification Plan

International Nuclear Information System (INIS)

GREAGER, T.M.

1999-01-01

The Hanford Site Transuranic Waste Certification Plan establishes the programmatic framework and criteria with in which the Hanford Site ensures that contract-handled TRU wastes can be certified as compliant with the WIPP WAC and TRUPACT-II SARP

The Savannah River Site's Groundwater Monitoring Program, third quarter 1989

Energy Technology Data Exchange (ETDEWEB)

1989-01-01

The Environmental Monitoring Section of the Environmental and Health Protection (EHP) Department administers the Savannah River Site's Groundwater Monitoring Program. During third quarter 1989 (July--September), EHP conducted routine sampling of monitoring wells and drinking water locations. EHP collected the drinking water samples from Savannah River Site (SRS) drinking water systems supplied by wells. EHP established two sets of flagging criteria in 1986 to assist in the management of sample results. The flagging criteria do not define contamination levels; instead they aid personnel in sample scheduling, interpretation of data, and trend identification. The flagging criteria are based on detection limits, background levels in SRS groundwater, and drinking water standards. An explanation of flagging criteria for the third quarter is presented in the Flagging Criteria section of this document. All analytical results from third quarter 1989 are listed in this report, which is distributed to all waste-site custodians.

Statewide screening for low-level radioactive waste shallow land burial sites

International Nuclear Information System (INIS)

Staub, W.P.; Cannon, J.B.; Stratton, L.E.

1984-01-01

A methodology was developed for statewide low-level waste site screening based on NRC site selection criteria. The methodology and criteria were tested in Tennessee to determine their effectiveness in narrowing the choice of sites for more intensive localized site screening. The statewide screening methodology entailed two steps. The first step was to select one or more physiographic provinces wherein sites meeting the criteria were most likely to be found. The second step was to select one or more suitable outcrop bands from within the most favorable physiographic provinces. These selections were based entirely on examination of existing literature and maps at scales no larger than 1:250,000. The statewide screening project identified only one suitable physiographic province (the Mississippi Embayment region) and one favorable outcrop band (the Coon Creek Formation) within a three county area of western Tennessee. Ground water monitoring and predictability proved to be the most difficult criterion to meet. This criterion alone eliminated other outcrop bands in the Mississippi Embayment as well as the Eastern Highland Rim and Western Highland Rim physiographic provinces. Other provinces failed to meet several screening criteria. 3 references, 3 figures, 1 table

Individual uncertainty and the uncertainty of science: The impact of perceived conflict and general self-efficacy on the perception of tentativeness and credibility of scientific information

Directory of Open Access Journals (Sweden)

Danny eFlemming

2015-12-01

Full Text Available We examined in two empirical studies how situational and personal aspects of uncertainty influence laypeople’s understanding of the uncertainty of scientific information, with focus on the detection of tentativeness and perception of scientific credibility. In the first study (N = 48, we investigated the impact of a perceived conflict due to contradicting information as a situational, text-inherent aspect of uncertainty. The aim of the second study (N = 61 was to explore the role of general self-efficacy as an intra-personal uncertainty factor. In Study 1, participants read one of two versions of an introductory text in a between-group design. This text provided them with an overview about the neurosurgical procedure of deep brain stimulation (DBS. The text expressed a positive attitude toward DBS in one experimental condition or focused on the negative aspects of this method in the other condition. Then participants in both conditions read the same text that dealt with a study about DBS as experimental treatment in a small sample of patients with major depression. Perceived conflict between the two texts was found to increase the perception of tentativeness and to decrease the perception of scientific credibility, implicating that text-inherent aspects have significant effects on critical appraisal. The results of Study 2 demonstrated that participants with higher general self-efficacy detected the tentativeness to a lesser degree and assumed a higher level of scientific credibility, indicating a more naïve understanding of scientific information. This appears to be contradictory to large parts of previous findings that showed positive effects of high self-efficacy on learning. Both studies showed that perceived tentativeness and perceived scientific credibility of medical information contradicted each other. We conclude that there is a need for supporting laypeople in understanding the uncertainty of scientific information and that

Site selection

International Nuclear Information System (INIS)

Olsen, C.W.

1983-07-01

The conditions and criteria for selecting a site for a nuclear weapons test at the Nevada Test Site are summarized. Factors considered are: (1) scheduling of drill rigs, (2) scheduling of site preparation (dirt work, auger hole, surface casing, cementing), (3) schedule of event (when are drill hole data needed), (4) depth range of proposed W.P., (5) geologic structure (faults, Pz contact, etc.), (6) stratigraphy (alluvium, location of Grouse Canyon Tuff, etc.), (7) material properties (particularly montmorillonite and CO 2 content), (8) water table depth, (9) potential drilling problems (caving), (10) adjacent collapse craters and chimneys, (11) adjacent expended but uncollapsed sites, (12) adjacent post-shot or other small diameter holes, (13) adjacent stockpile emplacement holes, (14) adjacent planned events (including LANL), (15) projected needs of Test Program for various DOB's and operational separations, and (16) optimal use of NTS real estate

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.

Ferrocyanide Safety Program: Safety criteria for ferrocyanide watch list tanks

International Nuclear Information System (INIS)

Postma, A.K.; Meacham, J.E.; Barney, G.S.

1994-01-01

This report provides a technical basis for closing the ferrocyanide Unreviewed Safety Question (USQ) at the Hanford Site. Three work efforts were performed in developing this technical basis. The efforts described herein are: 1. The formulation of criteria for ranking the relative safety of waste in each ferrocyanide tank. 2. The current classification of tanks into safety categories by comparing available information on tank contents with the safety criteria; 3. The identification of additional information required to resolve the ferrocyanide safety issue

Site decommissioning management plan

International Nuclear Information System (INIS)

Fauver, D.N.; Austin, J.H.; Johnson, T.C.; Weber, M.F.; Cardile, F.P.; Martin, D.E.; Caniano, R.J.; Kinneman, J.D.

1993-10-01

The Nuclear Regulatory Commission (NRC) staff has identified 48 sites contaminated with radioactive material that require special attention to ensure timely decommissioning. While none of these sites represent an immediate threat to public health and safety they have contamination that exceeds existing NRC criteria for unrestricted use. All of these sites require some degree of remediation, and several involve regulatory issues that must be addressed by the Commission before they can be released for unrestricted use and the applicable licenses terminated. This report contains the NRC staff's strategy for addressing the technical, legal, and policy issues affecting the timely decommissioning of the 48 sites and describes the status of decommissioning activities at the sites

Site decommissioning management plan

Energy Technology Data Exchange (ETDEWEB)

Fauver, D.N.; Austin, J.H.; Johnson, T.C.; Weber, M.F.; Cardile, F.P.; Martin, D.E.; Caniano, R.J.; Kinneman, J.D.

1993-10-01

The Nuclear Regulatory Commission (NRC) staff has identified 48 sites contaminated with radioactive material that require special attention to ensure timely decommissioning. While none of these sites represent an immediate threat to public health and safety they have contamination that exceeds existing NRC criteria for unrestricted use. All of these sites require some degree of remediation, and several involve regulatory issues that must be addressed by the Commission before they can be released for unrestricted use and the applicable licenses terminated. This report contains the NRC staff`s strategy for addressing the technical, legal, and policy issues affecting the timely decommissioning of the 48 sites and describes the status of decommissioning activities at the sites.

78 FR 26681 - Medical Criteria for Evaluating Cystic Fibrosis

Science.gov (United States)

2013-05-07

...-1213, or TTY 1-800-325-0778, or visit our Internet site, Social Security Online, at http://www... SOCIAL SECURITY ADMINISTRATION [Docket No. SSA-2006-0149] RIN 0960-AF58 Medical Criteria for Evaluating Cystic Fibrosis AGENCY: Social Security Administration. ACTION: Notice of teleconference. SUMMARY...

SSC [Superconducting Super Collider] site evaluations

International Nuclear Information System (INIS)

1988-11-01

With this report, the SSC Site Task Force forwards to the Director, Office of Energy Research, US Department of Energy (DOE), its evaluation of the technical criteria and life-cycle costs for the proposed SSC sites judged to be the best qualified. The criteria against which each site was evaluated are those set forth in the Invitation for Site Proposals for the Superconducting Super Collider (DOE/ER-0315) (Invitation) which was prepared by the Task Force and issued in April 1987. The methodology followed by the Task Force in this report and in all other phases of the proposal evaluation has been consistent with the SSC site selection process approved by DOE's Energy System Acquisition Advisory Board (ESAAB). The goal of the site selection process is to identify a site that will permit the highest level of research productivity and overall effectiveness of the SSC at a reasonable cost of construction and operation and with minimial impact on the environment. The Task Force acknowledges that all seven sites are, indeed, highly qualified locations for the construction and operation of the SSC on the basis of technical and cost considerations. In performing its evaluation, which is presented in this paper, the Task Force took an in-depth look at each site on the basis of site visits and extensive technical analyses. A consensus rating for each technical evaluation criterion and subcriterion was developed for each site

Radioactive waste repository site selection in the Republic of Slovenia

International Nuclear Information System (INIS)

Jeran, M.

1992-01-01

The report shows the procedure for the low and intermediate level radwaste (LLW and ILW) repository site selection and the work performed up to the present. The procedure for the repository site selection is divided into four steps. In the first step the unsuitable areas are excluded by taking into consideration the rough exclusion criteria. In the second step, the remaining suitable areas are screened to identify the potential sites with respect to preference criteria. In the third step three to five candidate sites will be assessed and selected among the potential sites. In the final, the fourth step, detailed site investigation and confirmation of one or two most suitable sites will follow. In Slovenia the 1st and the 2nd step of site selection have been completed, while step 3 is now in its final stage. (author) [sl

Low-level siting, Edgemont, South Dakota

International Nuclear Information System (INIS)

Andrews, L.J.

1984-01-01

The siting of a low-level radwaste disposal facility and characterization activities to date, at Edgemont, South Dakota are given. Using past and present experience setting forth the major problem as viewed by the author, the social and political considerations, community acceptance, media and public officials' attitudes, criteria for acceptance and significance of countywide vote in support of facility are presented. Characterization activities, site selection planning and criteria, above-grade and below-grade technical evaluation, NRC interface, 10 CFR Part 61 related to technical work, as well as community acceptance and license application are included. The paper deals with specific problems, solutions and ongoing activities

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...

Identification of suitable sites for rainwater harvesting structures in arid and semi-arid regions: A review

Directory of Open Access Journals (Sweden)

Ammar Adham

2016-06-01

Full Text Available Harvested rainwater is an alternative source of water in arid and semi-arid regions (ASARs around the world. Many researchers have developed and applied various methodologies and criteria to identify suitable sites and techniques for rainwater harvesting (RWH. Determining the best method or guidelines for site selection, however, is difficult. The main objective of this study was to define a general method for selecting suitable RWH sites in ASARs by assembling an inventory of the main methods and criteria developed during the last three decades. We categorised and compared four main methodologies of site selection from 48 studies published in scientific journals, reports of international organisations, or sources of information obtained from practitioners. We then identified three main sets of criteria for selecting RWH locations and the main characteristics of the most common RWH techniques used in ASARs. The methods were diverse, ranging from those based only on biophysical criteria to more integrated approaches including socio-economic criteria, especially after 2000. The most important criteria for the selection of suitable sites for RWH were slope, land use/cover, soil type, rainfall, distance to settlements/streams, and cost. The success rate of RWH projects tended to increase when these criteria were considered, but an objective evaluation of these selection methods is still lacking. Most studies now select RHW sites using geographic information systems in combination with hydrological models and multi-criteria analysis.

Natural phenomena hazards design and evaluation criteria for Department of Energy Facilities

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-01-01

The Department of Energy (DOE) has issued an Order 420.1 which establishes policy for its facilities in the event of natural phenomena hazards (NPH) along with associated NPH mitigation requirements. This DOE Standard gives design and evaluation criteria for NPH effects as guidance for implementing the NPH mitigation requirements of DOE Order 420.1 and the associated implementation Guides. These are intended to be consistent design and evaluation criteria for protection against natural phenomena hazards at DOE sites throughout the United States. The goal of these criteria is to assure that DOE facilities can withstand the effects of natural phenomena such as earthquakes, extreme winds, tornadoes, and flooding. These criteria apply to the design of new facilities and the evaluation of existing facilities. They may also be used for modification and upgrading of existing facilities as appropriate. The design and evaluation criteria presented herein control the level of conservatism introduced in the design/evaluation process such that earthquake, wind, and flood hazards are treated on a consistent basis. These criteria also employ a graded approach to ensure that the level of conservatism and rigor in design/evaluation is appropriate for facility characteristics such as importance, hazards to people on and off site, and threat to the environment. For each natural phenomena hazard covered, these criteria consist of the following: Performance Categories and target performance goals as specified in the DOE Order 420.1 NPH Implementation Guide, and DOE-STD-1 021; specified probability levels from which natural phenomena hazard loading on structures, equipment, and systems is developed; and design and evaluation procedures to evaluate response to NPH loads and criteria to assess whether or not computed response is permissible.

Waste-acceptance criteria and risk-based thinking for radioactive-waste classification

International Nuclear Information System (INIS)

Lowenthal, M.D.

1998-01-01

The US system of radioactive-waste classification and its development provide a reference point for the discussion of risk-based thinking in waste classification. The official US system is described and waste-acceptance criteria for disposal sites are introduced because they constitute a form of de facto waste classification. Risk-based classification is explored and it is found that a truly risk-based system is context-dependent: risk depends not only on the waste-management activity but, for some activities such as disposal, it depends on the specific physical context. Some of the elements of the official US system incorporate risk-based thinking, but like many proposed alternative schemes, the physical context of disposal is ignored. The waste-acceptance criteria for disposal sites do account for this context dependence and could be used as a risk-based classification scheme for disposal. While different classes would be necessary for different management activities, the waste-acceptance criteria would obviate the need for the current system and could better match wastes to disposal environments saving money or improving safety or both

Siting of light-water reactor power plants in the Federal Republic of Germany

International Nuclear Information System (INIS)

Kohler, H.A.G.

1975-01-01

The nuclear power plant site requirements formulated for environment protection in Germany allow nuclear power plants to be built at any site provided these requirements are duly taken into account in preparing and monitoring the site and in the design of the proposed power plant. After a brief discussion of light water reactor power plant sites, prevailing practice in site planning, site selection criteria, licensing procedure and used criteria, rules and guidelines, this paper reports on some considerations taken into account by the expert advisers and by the licensing authorities and future site planning. (orig.) [de

What constitutes a nesting attempt? Variation in criteria causes bias and hinders comparisons across studies

Science.gov (United States)

Garcia, V.; Conway, C.J.

2009-01-01

Because reliable estimates of nesting success are very important to avian studies, the defnition of a “successful nest” and the use of different analytical methods to estimate success have received much attention. By contrast, variation in the criteria used to determine whether an occupied site that did not produce offspring contained a nesting attempt is a source of bias that has been largely ignored. This problem is especially severe in studies that deal with species whose nest contents are relatively inaccessible because observers cannot determine whether or not an egg was laid for a large proportion of occupied sites. Burrowing Owls (Athene cunicularia) often lay their eggs ≥3 m below ground, so past Burrowing Owl studies have used a variety of criteria to determine whether a nesting attempt was initiated. We searched the literature to document the extent of that variation and examined how that variation influenced estimates of daily nest survival. We found 13 different sets of criteria used by previous authors and applied each criterion to our data set of 1,300 occupied burrows. We found significant variation in estimates of daily nest survival depending on the criteria used. Moreover, differences in daily nest survival among populations were apparent using some sets of criteria but not others. These inconsistencies may lead to incorrect conclusions and invalidate comparisons of the productivity and relative site quality among populations. We encourage future authors working on cavity-, canopy-, or burrow-nesting birds to provide specific details on the criteria they used to identify a nesting attempt.

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

Multi-criteria selection of offshore wind farms: Case study for the Baltic States

International Nuclear Information System (INIS)

Chaouachi, Aymen; Covrig, Catalin Felix; Ardelean, Mircea

2017-01-01

This paper presents a multi-criteria selection approach for offshore wind sites assessment. The proposed site selection framework takes into consideration the electricity network’s operating security aspects, economic investment, operation costs and capacity performances relative to each potential site. The selection decision is made through Analytic Hierarchy Process (AHP), with an inherited flexibility that aims to allow end users to adjust the expected benefits accordingly to their respective and global priorities. The proposed site selection framework is implemented as an interactive case study for three Baltic States in the 2020 time horizon, based on real data and exhaustive power network models, taking into consideration the foreseen upgrades and network reinforcements. For each country the optimal offshore wind sites are assessed under multiple weight contribution scenarios, reflecting the characteristics of market design, regulatory aspects or renewable integration targets. - Highlights: • We use a multi-criteria selection approach for offshore wind sites assessment. • Security aspects, economic investment, operation costs and capacity performances are included. • The selection decision is made through an Analytic Hierarchy Process (AHP). • We implement the methodology as a case study for three Baltic States in the 2020 time horizon.

Modeling rock specimens through 3D printing: Tentative experiments and prospects

Science.gov (United States)

Jiang, Quan; Feng, Xiating; Song, Lvbo; Gong, Yahua; Zheng, Hong; Cui, Jie

2016-02-01

Current developments in 3D printing (3DP) technology provide the opportunity to produce rock-like specimens and geotechnical models through additive manufacturing, that is, from a file viewed with a computer to a real object. This study investigated the serviceability of 3DP products as substitutes for rock specimens and rock-type materials in experimental analysis of deformation and failure in the laboratory. These experiments were performed on two types of materials as follows: (1) compressive experiments on printed sand-powder specimens in different shapes and structures, including intact cylinders, cylinders with small holes, and cuboids with pre-existing cracks, and (2) compressive and shearing experiments on printed polylactic acid cylinders and molded shearing blocks. These tentative tests for 3DP technology have exposed its advantages in producing complicated specimens with special external forms and internal structures, the mechanical similarity of its product to rock-type material in terms of deformation and failure, and its precision in mapping shapes from the original body to the trial sample (such as a natural rock joint). These experiments and analyses also successfully demonstrate the potential and prospects of 3DP technology to assist in the deformation and failure analysis of rock-type materials, as well as in the simulation of similar material modeling experiments.

Siting factors for the Swedish deep repository for spent fuel

International Nuclear Information System (INIS)

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

1998-01-01

A project entitled Siting factors and criteria for site evaluation was initiated at the SKB in 1997. The project comprises an important part of the work of siting and site selection that is being pursued within SKB. The purpose of the project is to create a logical structure for the continued siting work, and its results should also be able to be used to assist in evaluating sites. The project will thereby also provide a means - in accordance with the Government's decision regarding Research Programme 95 - to obtain more detailed and quantified siting factors and criteria than those previously presented in the supplement to Research Programme 92. The overall goals of the project are to identify and quantify requirements and preferences regarding the properties of the rock and the soil from the perspectives of long-term safety, performance and planning and design of the rock works, and to identify siting factors and criteria. The latter should be able to be used to determine whether requirements and preferences are satisfied, both when screening sites for site investigation and after completed site investigation. Presented requirements, preferences, factors and criteria must be acceptable to national and municipal authorities or others with influence over the siting work. To start with, requirements and preferences regarding the performance of the rock in a deep repository have been clarified. These requirements and preferences are based on many years of experience of safety assessments and construction analyses within SKB. What is new here is the structuring that has been done, where a classification is made into different geoscientific disciplines, and the formalism that has been developed for the concepts requirements, preferences and performance. This is a prerequisite for a consistent and hopefully comprehensive set of requirements from a functional perspective. Work has continued on siting factors with reference to a coming site investigation programme. A

Geospatial Optimization of Siting Large-Scale Solar Projects

Energy Technology Data Exchange (ETDEWEB)

Macknick, Jordan [National Renewable Energy Lab. (NREL), Golden, CO (United States); Quinby, Ted [National Renewable Energy Lab. (NREL), Golden, CO (United States); Caulfield, Emmet [Stanford Univ., CA (United States); Gerritsen, Margot [Stanford Univ., CA (United States); Diffendorfer, Jay [U.S. Geological Survey, Boulder, CO (United States); Haines, Seth [U.S. Geological Survey, Boulder, CO (United States)

2014-03-01

Recent policy and economic conditions have encouraged a renewed interest in developing large-scale solar projects in the U.S. Southwest. However, siting large-scale solar projects is complex. In addition to the quality of the solar resource, solar developers must take into consideration many environmental, social, and economic factors when evaluating a potential site. This report describes a proof-of-concept, Web-based Geographical Information Systems (GIS) tool that evaluates multiple user-defined criteria in an optimization algorithm to inform discussions and decisions regarding the locations of utility-scale solar projects. Existing siting recommendations for large-scale solar projects from governmental and non-governmental organizations are not consistent with each other, are often not transparent in methods, and do not take into consideration the differing priorities of stakeholders. The siting assistance GIS tool we have developed improves upon the existing siting guidelines by being user-driven, transparent, interactive, capable of incorporating multiple criteria, and flexible. This work provides the foundation for a dynamic siting assistance tool that can greatly facilitate siting decisions among multiple stakeholders.

40 CFR 228.9 - Disposal site monitoring.

Science.gov (United States)

2010-07-01

... Section 228.9 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) OCEAN DUMPING CRITERIA FOR THE MANAGEMENT OF DISPOSAL SITES FOR OCEAN DUMPING § 228.9 Disposal site monitoring. (a) The... following components: (1) Trend assessment surveys conducted at intervals frequent enough to assess the...

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

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.

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

Criteria for decommissioning

International Nuclear Information System (INIS)

Ricci, P.F.

1988-01-01

In this paper the authors describe three risk acceptability criteria as parts of a strategy to clean up decommissioned facilities, related to both the status quo and to a variety of alternative technical clean-up options. The acceptability of risk is a consideration that must enter into any decision to establish when a site is properly decommissioned. To do so, both the corporate and public aspects of the acceptability issue must be considered. The reasons for discussion the acceptability of risk are to: Legitimize the process for making cleanup decisions; Determine who is at risk, who benefits, and who bears the costs of site cleanup, for each specific cleanup option, including the do nothing option; Establish those factors that, taken as a whole, determine measures of acceptability; Determine chemical-specific aggregate and individual risk levels; and Establish levels for cleanup. The choice of these reasons is pragmatic. The method consistent with these factors is risk-risk-effectiveness: the level of cleanup must be consistent with the foreseeable use of the site and budget constraints. Natural background contamination is the level below which further cleanup is generally inefficient. Case-by-case departures from natural background are to be considered depending on demonstrated risk. For example, a hot spot is obviously a prima facie exception, but should be rebuttable. Rebuttability means that, through consensus, the ''hot spot'' is shown not to be associated with exposure

Hanford site transuranic waste certification plan

International Nuclear Information System (INIS)

GREAGER, T.M.

1999-01-01

As a generator of transuranic (TRU) and TRU mixed waste destined for disposal at the Waste Isolation Pilot Plant (WIPP), the Hanford Site must ensure that its TRU waste meets the requirements of U.S. Department of Energy (DOE) Order 5820.2A, ''Radioactive Waste Management, and the Waste Acceptance Criteria for the Waste Isolation Pilot Plant' (DOE 1996d) (WIPP WAC). The WIPP WAC establishes the specific physical, chemical, radiological, and packaging criteria for acceptance of defense TRU waste shipments at WIPP. The WIPP WAC also requires that participating DOE TRU waste generator/treatment/storage sites produce site-specific documents, including a certification plan, that describe their management of TRU waste and TRU waste shipments before transferring waste to WIPP. The Hanford Site must also ensure that its TRU waste destined for disposal at WIPP meets requirements for transport in the Transuranic Package Transporter41 (TRUPACT-11). The U.S. Nuclear Regulatory Commission (NRC) establishes the TRUPACT-I1 requirements in the ''Safety Analysis Report for the TRUPACT-II Shipping Package'' (NRC 1997) (TRUPACT-I1 SARP)

Acceptance-criteria for the bedrock for deep geologic disposal of spent nuclear fuel. Proceedings from a seminar at Gothenburg University

International Nuclear Information System (INIS)

1995-11-01

The seminar was directed to Nordic participants, and discussed disposal in the Nordic crystalline bedrock. Criteria for the bedrock should include: It should give durable mechanical protection for the engineered barriers; give a stable and favorable chemical environment for these barriers; have a low turnover of ground water in the near field; be easy to characterize; give favorable recipient-conditions; not have valuable minerals in workable quantities. These general criteria raise several questions coupled to the safety analysis: e.g. the need for geological, hydrological and geochemical parameters. Which data are missing, which are most difficult to find? What should the site characterization program look like to focus on factors that are of the highest importance according to the safety analysis. The demands on the conditions at a site need to be translated into quantitative criteria, which should be expressed as values that can be measured at the site or deduced from such measurements. These questions were discussed at the seminar, and 21 contributions from Finnish, Norwegian and Swedish participants are reported in these proceedings under the chapters: Coupling to the safety analysis; Methodology and criteria for site selection in a regional geoscientific perspective; Rock as a building material - prognosis and result; Geoscientific criteria for the bedrock at the repository - Mechanical protection; Geoscientific criteria for the bedrock at the repository - Low ground water turnover, chemically favorable and stable environment in the near field; Geoscientific criteria for the bedrock at the repository - Demands on the bedrock concerning the migration of radionuclides

An integrated study of spatial multicriteria analysis and mathematical modelling for managed aquifer recharge site suitability mapping and site ranking at Northern Gaza coastal aquifer.

Science.gov (United States)

Rahman, Mohammad Azizur; Rusteberg, Bernd; Uddin, Mohammad Salah; Lutz, Annegret; Saada, Muath Abu; Sauter, Martin

2013-07-30

This paper describes an integrated approach of site suitability mapping and ranking of the most suitable sites, for the implementation of Managed Aquifer Recharge (MAR) projects, using spatial multicriteria decision analysis (SMCDA) techniques and mathematical modelling. The SMCDA procedure contains constraint mapping, site suitability analysis with criteria standardization and weighting, criteria overlay by analytical hierarchy process (AHP) combined with weighted linear combination (WLC) and ordered weighted averaging (OWA), and sensitivity analysis. The hydrogeological impacts of the selected most suitable sites were quantified by using groundwater flow and transport modelling techniques. Finally, ranking of the selected sites was done with the WLC method. The integrated approach is demonstrated by a case study in the coastal aquifer of North Gaza. Constraint mapping shows that 50% of the total study area is suitable for MAR implementation. About 25% of the total area is "very good" and 25% percent is "good" for MAR, according to the site suitability analysis. Six locations were selected and ranked against six representative decision criteria. Long term (year 2003 to year 2040) groundwater flow and transport simulations were performed to quantify the selected criteria under MAR project operation conditions at the selected sites. Finally, the suitability mapping and hydrogeological investigation recommends that the location of the existing infiltration ponds, constructed near the planned North Gaza Wastewater Treatment Plant (NGWWTP) is most suitable for MAR project implementation. This paper concludes that mathematical modelling should be combined with the SMCDA technique in order to select the best location for MAR project implementation. Besides MAR project implementation, the generalised approach can be applicable for any other water resources development project that deals with site selection and implementation. Copyright © 2013 Elsevier Ltd. All rights

MODIFIED APPROACH FOR SITE SELECTION OF UNWANTED RADIOACTIVE SEALED SOURCES DISPOSAL IN ARID COUNTRIES (CASE STUDY - EGYPT)

International Nuclear Information System (INIS)

ABDEL AZIZ, M.A.H.; COCHRAN, J.R.

2008-01-01

The aim of this study is to present a systematic methodology for siting of radioactive sealed sources disposal in arid countries and demonstrate the use of this methodology in Egypt. Availing from the experience gained from the greater confinement disposal (GCD) boreholes in Nevada, USA, the IAEA's approach for siting of near disposal was modified to fit the siting of the borehole disposal which suits the unwanted radioactive sealed sources. The modifications are represented by dividing the surveyed area into three phases; the exclusion phase in which the areas that meet exclusion criteria should be excluded, the site selection phase in which some potential sites that meet the primary criteria should be candidate and the preference stage in which the preference between the potential candidate sites should be carried out based on secondary criteria to select one or two sites at most. In Egypt, a considerable amount of unwanted radioactive sealed sources wastes have accumulated due to the peaceful uses of radio-isotopes.Taking into account the regional aspects and combining of the proposed developed methodology with geographic information system (GIS), the Nile Delta and its valley, the Sinai Peninsula and areas of historical heritage value are excluded from our concern as potential areas for radioactive waste disposal. Using the primary search criteria, some potential sites south Kharga, the Great Sand Sea, Gilf El-Kebear and the central part of the eastern desert have been identified as candidate areas meeting the primary criteria of site selection. More detailed studies should be conducted taking into account the secondary criteria to prefer among the above sites and select one or two sites at most

Successful Implementation of Soil Segregation Technology at the Painesville FUSRAP Site - 12281

Energy Technology Data Exchange (ETDEWEB)

Buechi, Stephen P.; Andrews, Shawn M. [U.S. Army Corps of Engineers, Buffalo District, Buffalo, New York (United States); Lombardo, Andrew J. [Safety and Ecology Corporation, Beaver, Pennsylvania (United States); Lively, Jeffrey W. [AMEC Environment and Infrastructure, Grand Junction, Colorado (United States)

2012-07-01

Typically the highest cost component of the radiological soils remediation of Formerly Utilized Sites Remedial Action Program (FUSRAP) sites is the cost to transport and dispose of the excavated soils, typically contaminated with naturally occurring isotopes of uranium, thorium and radium, at an appropriately permitted off-site disposal facility. The heterogeneous nature of the contamination encountered at these sites makes it difficult to accurately delineate the extent of contaminated soil using the limited, discrete sampling data collected during the investigation phases; and difficult to precisely excavate only the contaminated soil that is above the established cleanup limits using standard in-field scanning and guiding methodologies. This usually results in a conservative guided excavation to ensure cleanup criteria are met, with the attendant transportation and disposal costs for the larger volumes of soil excavated. To address this issue during the remediation of the Painesville FUSRAP Site, located in Painesville, Ohio, the Buffalo District of the U.S. Army Corps of Engineers, and its contractor, Safety and Ecology Corporation (SEC), employed automatic soil segregation technology provided by MACTEC (now AMEC) to reduce the potential for transportation and disposal of soils that met the cleanup limits. This waste minimization technology utilized gamma spectroscopy of conveyor-fed soils to automatically segregate the material into above and below criteria discharge piles. Use of the soil segregation system resulted in cost savings through the significant reduction of the volume of excavated soil that required off-site transportation and disposal, and the reduction of the amount of imported clean backfill required via reuse of 'below criteria' segregated soil as place back material in restoring the excavations. Measurements taken by the soil segregation system, as well as results of quality control sampling of segregated soils, confirmed that soils

Seismic re-evaluation criteria for Bohunice V1 reconstruction

International Nuclear Information System (INIS)

Campbell, R.; Schlund, H.; Warnken, L.

2001-01-01

Bohunice V1 in Slovakia is a Russian designed two unit WWER 440, Model 230 Pressurized Water Reactor. The plant was not originally designed for earthquake. Subsequent and ongoing reassessments now confirm that the seismic hazard at the site is significant. EBO, the plant owner has contracted with a consortium lead by Siemens AG (REKON) to do major reconstruction of the plant to significantly enhance its safety systems by the addition of new systems and the upgrading of existing systems. As part of the reconstruction, a complete seismic assessment and upgrading is required for existing safety relevant structures, systems and components. It is not practical to conduct this reassessment and upgrading using criteria applied to new design of nuclear power plants. Alternate criteria may be used to achieve adequate safety goals. Utilities in the U.S. have faced several seismic issues with operating NPPs and to resolve these issues, alternate criteria have been developed which are much more cost effective than use of criteria for new design. These alternate criteria incorporate the knowledge obtained from investigation of the performance of equipment in major earthquakes and include provisions for structures and passive equipment to deform beyond the yield point, yet still provide their essential function. IAEA has incorporated features of these alternate criteria into draft Technical Guidelines for application to Bohunice V1 and V2. REKON has developed plant specific criteria and procedures for the Bohunice V1 reconstruction that incorporate major features of the U.S. developed alternate criteria, comply to local codes and which envelop the draft IAEA Technical Guidelines. Included in these criteria and procedures are comprehensive walkdown screening criteria for equipment, piping, HVAC and cable raceways, analytical criteria which include inelastic energy absorption factors defined on an element basis and testing criteria which include specific guidance on interpretation

Site selection report basalt waste isolation program near-surface test facility

International Nuclear Information System (INIS)

Sharpe, S.D.

1978-01-01

A site selection committee was established to review the information gathered on potential sites and to select a site for the Near-Surface Test Facility Phase I. A decision was made to use a site on the north face of Gable Mountain located on the Hanford Site. This site provided convenient access to the Pomona Basalt Flow. This flow was selected for use at this site because it exhibited the characteristics established in the primary criteria. These criteria were: the flows thickness; its dryness; its nearness to the surface; and, its similarities to basalt units which are candidates for the repository. After the selection of the Near-Surface Test Facility Phase I Site, the need arose for an additional facility to demonstrate safe handling, storage techniques, and the physical effects of radioactive materials on an in situ basalt formation. The committee reviewed the sites selected for Phase I and chose the same site for locating Phase II of the Near-Surface Test Facility

Criteria for the restoration of mining residues in Germany

International Nuclear Information System (INIS)

Kraus, W.; Ettenhuber, E.; Gehrcke, K.; Przyborowski, S.

2000-01-01

Residues from uranium mines and mills and from the mining of silver, tin, cobalt, nickel and other ores, as well as of coal mineralized with uranium, are situated in densely populated regions of Germany. Social and political pressure required an urgent investigation and evaluation of these residues in order to identify relevant residues which could not be disregarded from the radiation protection point of view. There were two categories of residues. First, for huge former uranium mining and milling sites, the original owner could be made liable for restoration. A large Federal rehabilitation programme for the Wismut sites was started immediately after the political change in the former East Germany in 1990 and was based on radiological as well as on social and economic concerns. Secondly, for a large number of smaller residues, sometimes dating back to the middle ages, an evaluation of their radiological relevance was necessary before decisions could be taken on the justification of a restoration. This was the objective of a Federal programme on registration, investigation and evaluation of mining residues. Up to now only minor remedial activities have been carried out in cases where an urgent need had been detected. Criteria developed by the German Commission on radiological protection (SSK) were applied for the evaluation of the residues. The primary criterion for the justification of a restoration was an annual individual effective dose of 1 mSv for all exposure pathways except for the inhalation of radon. For inhalation of radon, the primary criterion for justification was a long term average outdoor radon concentration of 50 Bq/m 3 caused by the residues. Both levels were taken in addition to the natural background radiation level at a given site. These criteria were based on the upper end of the 'normal' range of naturally occurring exposure or concentration levels. SSK established reference levels in measurable quantities (activity concentration in soil

Measurement of strontium-89 and strontium-90 in environmental waters. A tentative reference method

International Nuclear Information System (INIS)

1976-03-01

A tentative reference method for the measurement of 89 Sr and 90 Sr in environmental waters is described. Samples of environmental water sources are collected, preserved with acid-strontium carrier, and analyzed for 89 Sr and/or 90 Sr. The isotopes are separated from the sample water by precipitating with stable strontium carrier as carbonate. The strontium carbonate is dissolved, 90 Sr separated, the strontium reprecipitated as carbonate, filtered, and counted for the combined 89 Sr and 90 Sr activity. The 90 y is allowed to grow in from the 90 y activity; the strontium carbonate is redissolved; the 90 y is separated, precipitated, and counted for the 90 Sr determination. The 89 Sr activity is then determined by difference of the total 89 Sr and 90 y and the separate 90 Sr activities. Recoveries are determined from the added and found (recovered) strontium carrier. Counting efficiencies are determined with prepared standard reference samples. Results are reported in pCi/liter

Nuclear reactor philosophy and criteria

International Nuclear Information System (INIS)

Atchison, R.J.

1979-07-01

Nuclear power plant safety criteria and principles developed in Canada are directed towards minimizing the chance of failure of the fuel and preventing or reducing to an acceptably low level the escape of fission products should fuel failure occur. Safety criteria and practices are set forth in the Reactor Siting Guide, which is based upon the concept of defence in depth. The Guide specifies that design and construction shall follow the best applicable code, standard or practice; the total of all serious process system failures shall not exceed one in three years; special safety systems are to be physically and functionally separate from process systems and each other; and safety systems shall be testable, with unavailability less than 10 - 3 . Doses to the most exposed member of the public due to normal operation, serious process failures, and dual failures are specified. Licensees are also required to consider the effects of extreme conditions due to airplane crashes, explosions, turbine disintegration, pipe burst, and natural disasters. Safety requirements are changing as nuclear power plant designs evolve and in response to social and economic pressures

Hazardous Waste Landfill Siting using GIS Technique and Analytical Hierarchy Process

Directory of Open Access Journals (Sweden)

Ozeair Abessi

2010-07-01

Full Text Available Disposal of large amount of generated hazardous waste in power plants, has always received communities' and authori¬ties attentions. In this paper using site screening method and Analytical Hierarchy Process (AHP a sophisticated approach for siting hazardous waste landfill in large areas is presented. This approach demonstrates how the evaluation criteria such as physical, socio-economical, technical, environmental and their regulatory sub criteria can be introduced into an over layer technique to screen some limited appropriate zones in the area. Then, in order to find the optimal site amongst the primary screened site utilizing a Multiple Criteria Decision Making (MCDM method for hierarchy computations of the process is recommended. Using the introduced method an accurate siting procedure for environmental planning of the landfills in an area would be enabled. In the study this approach was utilized for disposal of hazardous wastes of Shahid Rajaee thermal power plant located in Qazvin province west central part of Iran. As a result of this study 10 suitable zones were screened in the area at first, then using analytical hierarchy process a site near the power plant were chosen as the optimal site for landfilling of the hazardous wastes in Qazvin province.

G. Nuclear power plant siting

International Nuclear Information System (INIS)

1976-01-01

The selection of a site for a nuclear power site is a complex process involving considerations of public health and safety, engineering design, economics, and environmental impact. Although policies adopted in various countries differ in some details, a common philosophy usually underlies the criteria employed. The author discusses the basic requirements, as they relate to New Zealand, under the headings: engineering and economics; health and safety; environmental factors

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

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

Quality of breast cancer sites on the World Wide Web.

Science.gov (United States)

Hoffman-Goetz, L; Clarke, J N

2000-01-01

The Internet is a powerful tool for accessing information about complex health topics. The purpose of this study was to evaluate breast cancer Internet sites using published criteria about website structure. Two searches were undertaken (November 1998 and June 1999) using the Yahoo search engine, providing a sample of 136 unique addresses. The results showed 1) owner's credentials were identified in 31.6% of sites, 2) financial charges were stated in 10.3% of sites, 3) less than 14.0% identified site creation date, 4) 33.1% identified content posting update, 5) 30.1% identified information sources, and 6) just under 88% of sites provided e-mail interactivity. The results indicate variability in breast cancer Internet sites with respect to framework criteria of accountability. We suggest that websites that lack fundamental indicators (such as dating and sources) do not provide the user with fundamental information that could enable informed decision making about site quality.

Interim licensing criteria for physical protection of certain storage of spent fuel

International Nuclear Information System (INIS)

Dwyer, P.A.

1994-11-01

This document presents interim criteria to be used in the physical protection licensing of certain spent fuel storage installations. Installations that will be reviewed under this criteria are those that store power reactor spent fuel at decommissioned power reactor sites; independent spent fuel storage installations located outside of the owner controlled area of operating nuclear power reactors; monitored retrievable storage installations owned by the Department of Energy, designed and constructed specifically for the storage, of spent fuel; the proposed geologic repository operations area; or permanently shutdown power reactors still holding a Part 50 license. This criteria applies to both dry cask and pool storage. However, the criteria in this document does not apply to the storage of spent fuel within the owner-controlled area of operating nuclear power reactors

Completion of decommissioning: Monitoring for site release and license termination

International Nuclear Information System (INIS)

Boing, L.E.

1997-01-01

To request termination of a license upon completion of dismantling or decommissioning activities, documenting any residual radioactivity to show that the levels are environmentally acceptable will be necessary. When the regulators approve the decommissioning plan, they establish what the release criteria for the decommissioned site will be at the time of the site release and license termination. The criteria are numeric guidelines for direct radiation in soils and on surfaces. If the regulatory body finds that the measured on-site values are below the guidelines, the site will be acceptable for unrestricted release (no radiological controls or future use). If areas are found above those values, more decontamination or cleanup of these areas may be required unless the regulatory body grants an exemption

Theoretical studies of Cu(I) sites in faujasite and their interaction with carbon monoxide.

Science.gov (United States)

Rejmak, Pawel; Sierka, Marek; Sauer, Joachim

2007-10-28

Sitting, coordination, and properties of Cu(I) cations in zeolite faujasite are investigated using a combined quantum mechanics-interatomic potential function method. The coordination of Cu(I) ions depends on their location within the zeolite lattice. Cu(I) located inside the hexagonal prisms (site I') and in the plane of six-membered aluminosilicate rings on the walls of sodalite units (site II) is threefold coordinated, whereas Cu(I) located in the supercages (site III) is twofold coordinated. In agreement with available experimental data Cu(I) appears to be more strongly bound in sites I' and II than in site III. The binding energy of site II Cu(I) ions increases with the number of Al atoms, but only closest Al atoms have a substantial influence. The CO molecule binds more strongly onto sites with weaker bound cations and lower coordination. We assign the two CO stretching IR bands observed for Cu(I)-Y zeolites to sites II with one Al (2157-2161 cm(-1)) and two Al atoms (2140-2148 cm(-1)) in the six-membered aluminosilicate ring. For Cu(I)-X we tentatively assign the high frequency band to site III (2156-2168 cm(-1)) and the low-frequency band to site II with three Al atoms in the six-membered ring (2136-2138 cm(-1)).

Experimental Seismic Event-screening Criteria at the Prototype International Data Center

Science.gov (United States)

Fisk, M. D.; Jepsen, D.; Murphy, J. R.

- Experimental seismic event-screening capabilities are described, based on the difference of body-and surface-wave magnitudes (denoted as Ms:mb) and event depth. These capabilities have been implemented and tested at the prototype International Data Center (PIDC), based on recommendations by the IDC Technical Experts on Event Screening in June 1998. Screening scores are presented that indicate numerically the degree to which an event meets, or does not meet, the Ms:mb and depth screening criteria. Seismic events are also categorized as onshore, offshore, or mixed, based on their 90% location error ellipses and an onshore/offshore grid with five-minute resolution, although this analysis is not used at this time to screen out events.Results are presented of applications to almost 42,000 events with mb>=3.5 in the PIDC Standard Event Bulletin (SEB) and to 121 underground nuclear explosions (UNE's) at the U.S. Nevada Test Site (NTS), the Semipalatinsk and Novaya Zemlya test sites in the Former Soviet Union, the Lop Nor test site in China, and the Indian, Pakistan, and French Polynesian test sites. The screening criteria appear to be quite conservative. None of the known UNE's are screened out, while about 41 percent of the presumed earthquakes in the SEB with mb>=3.5 are screened out. UNE's at the Lop Nor, Indian, and Pakistan test sites on 8 June 1996, 11 May 1998, and 28 May 1998, respectively, have among the lowest Ms:mb scores of all events in the SEB.To assess the validity of the depth screening results, comparisons are presented of SEB depth solutions to those in other bulletins that are presumed to be reliable and independent. Using over 1600 events, the comparisons indicate that the SEB depth confidence intervals are consistent with or shallower than over 99.8 percent of the corresponding depth estimates in the other bulletins. Concluding remarks are provided regarding the performance of the experimental event-screening criteria, and plans for future

The Savannah River Site's groundwater monitoring program

International Nuclear Information System (INIS)

1991-01-01

The Environmental Protection Department/Environmental Monitoring Section (EPD/EMS) administers the Savannah River Site's (SRS) Groundwater Monitoring Program. During third quarter 1990 (July through September) EPD/EMS conducted routine sampling of monitoring wells and drinking water locations. EPD/EMS established two sets of flagging criteria in 1986 to assist in the management of sample results. The flagging criteria do not define contamination levels; instead they aid personnel in sample scheduling, interpretation of data, and trend identification. The flagging criteria are based on detection limits, background levels in SRS groundwater, and drinking water standards. All analytical results from third quarter 1990 are listed in this report, which is distributed to all site custodians. One or more analytes exceeded Flag 2 in 87 monitoring well series. Analytes exceeded Flat 2 for the first since 1984 in 14 monitoring well series. In addition to groundwater monitoring, EPD/EMS collected drinking water samples from SRS drinking water systems supplied by wells. The drinking water samples were analyzed for radioactive constituents

Regional siting survey for thermal power plants in the state of Ohio

International Nuclear Information System (INIS)

Elkins, M.L.; DiNunno, J.J.

1975-01-01

The selection and evaluation of sites for power plants have become increasingly difficult in recent years as pressures from various societal segments have resulted in government restraints on selection and burning of fossil fuels, on methods of heat dissipation, on acquisition of transmission line rights-of-way, and on environmental impact in general. The key elements in successful application of power plant siting technology are the development of the proper balance among the basic siting considerations and the understanding that level of detail in a study varies in an inverse relationship with the siting area under examination. As the first step in the process of selection and eventual licensing of new thermal power plant sites for a utility in the State of Ohio, the entire state was screened to determine promising candidate regions large enough to offer several possible candidate sites for thermal power plants. Because of the size of the area under consideration and the advantages of developing sites with an ultimate capacity for more than one power plant, sites with an installed capacity of 1100 to 4400 MW(e) were considered for this study. As a result of the preliminary screening conducted in four distinct steps, three candidate regions showed the best overall promise for either nuclear or fossil-fueled power plant development. Tentative identification was made of candidate sites within these candidate regions, and follow-on studies conducted in an increasing level of detail are presently in progress to determine the candidate site(s) most promising for power plant siting. (U.S.)

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

Design criteria development for the structural stability of nuclear waste repository

Energy Technology Data Exchange (ETDEWEB)

Yun, C H [Korea Institute of Nuclear Safety, Taejon (Korea, Republic of); Yu, T S [Daewoo Engineering Company, Sungnam (Korea, Republic of); Ko, H M [Seoul National Univ., Seoul (Korea, Republic of)

1990-11-15

The objective of the present project is to develop design criteria for the structural stability of rock cavity for the underground repository are defined, according to which detailed descriptions for design methodologies, design stages and stability analysis of the cavity are made. The proposed criteria can be used as a guide for the preparation of design codes which are to be established as the site condition and technical emplacement procedure are fixed. The present report first reviews basic safety requirements and criteria of the underground disposal of nuclear wastes for the establishment of design concepts and stability analysis of the rock cavity. Important factors for the design are also described by considering characteristics of the wastes and underground facilities. The present project has investigated technical aspects on the design of underground structures based on the currently established underground construction technologies, and presented a proposal for design criteria for the structural stability of the nuclear waste repository. The proposed criteria consist of general provisions, geological exploration, rock classification, design process and methods, supporting system, analyses and instrumentation.

Geology, hydrology, thickness and quality of salt at three alternate sites for disposal of radioactive waste in Kansas

International Nuclear Information System (INIS)

Bayne, C.K.; Brinkley, C.

1972-09-01

The three sites selected by the AEC for additional study for the disposal of radioactive wastes in Kansas are; Site A located in south-central Lincoln County, Site D-2 located in south-central Wichita County, and Site A-1 located in north-western Lincoln County. Results of the study show that all sites failed to meet the detailed criteria. Areas A and A-1 fail to meet the criteria concerning thickness and quality. Area D-2 fails to meet the criteria concerning quality and mineability of the salt. Areas west of Site A-1 and in south-central Harper County, in the authors' opinion, appear to be the best prospects for future study in Kansas

Nuclear waste management technical support in the development of nuclear waste form criteria for the NRC. Task 1. Waste package overview

International Nuclear Information System (INIS)

Dayal, R.; Lee, B.S.; Wilke, R.J.; Swyler, K.J.; Soo, P.; Ahn, T.M.; McIntyre, N.S.; Veakis, E.

1982-02-01

In this report the current state of waste package development for high level waste, transuranic waste, and spent fuel in the US and abroad has been assessed. Specifically, reviewed are recent and on-going research on various waste forms, container materials and backfills and tentatively identified those which are likely to perform most satisfactorily in the repository environment. Radiation effects on the waste package components have been reviewed and the magnitude of these effects has been identified. Areas requiring further research have been identified. The important variables affecting radionuclide release from the waste package have been described and an evaluation of regulatory criteria for high level waste and spent fuel is presented. Finally, for spent fuel, high level, and TRU waste, components which could be used to construct a waste package having potential to meet NRC performance requirements have been described and identified

Nuclear waste management technical support in the development of nuclear waste form criteria for the NRC. Task 1. Waste package overview

Energy Technology Data Exchange (ETDEWEB)

Dayal, R.; Lee, B.S.; Wilke, R.J.; Swyler, K.J.; Soo, P.; Ahn, T.M.; McIntyre, N.S.; Veakis, E.

1982-02-01

In this report the current state of waste package development for high level waste, transuranic waste, and spent fuel in the US and abroad has been assessed. Specifically, reviewed are recent and on-going research on various waste forms, container materials and backfills and tentatively identified those which are likely to perform most satisfactorily in the repository environment. Radiation effects on the waste package components have been reviewed and the magnitude of these effects has been identified. Areas requiring further research have been identified. The important variables affecting radionuclide release from the waste package have been described and an evaluation of regulatory criteria for high level waste and spent fuel is presented. Finally, for spent fuel, high level, and TRU waste, components which could be used to construct a waste package having potential to meet NRC performance requirements have been described and identified.

Multi-criteria analysis for municipal solid waste management in a Brazilian metropolitan area.

Science.gov (United States)

Santos, Simone Machado; Silva, Maisa Mendonça; Melo, Renata Maciel; Gavazza, Savia; Florencio, Lourdinha; Kato, Mario T

2017-10-15

The decision-making process involved in municipal solid waste management (MSWM) must consider more than just financial aspects, which makes it a difficult task in developing countries. The Recife Metropolitan Region (RMR) in the Northeast of Brazil faces a MSWM problem that has been ongoing since the 1970s, with no common solution. In order to direct short-term solutions, three MSWM alternatives were outlined for the RMR, considering the current and future situations, the time and cost involved and social/environmental criteria. A multi-criteria approach, based on the Preference Ranking Organization Method for Enrichment Evaluations (PROMETHEE), was proposed to rank these alternatives. The alternative that included two private landfill sites and seven transfer, sorting and composting stations was confirmed as the most suitable and stable option for short-term MSWM, considering the two scenarios for the criteria weights. Sensitivity analysis was also performed to support the robustness of the results. The implementation of separate collections would minimize the amount of waste buried, while maximizing the useful life of landfill sites and increasing the timeframe of the alternative. Overall, the multi-criteria analysis was helpful and accurate during the alternative selection process, considering the similarities and restrictions of each option, which can lead to difficulties during the decision-making process.

Tentative design-philosophy for bellows in sodium cooled fast breeder reactors pipings

Energy Technology Data Exchange (ETDEWEB)

Scaller, K; Vrillon, B

1980-02-01

Expansion joints have proved to be reliable components, when properly designed and realized, in normal industrial equipment. But nevertheless bellows have not been employed widely in nuclear reactors and almost not in sodium cooled fast breeder reactors, where use of expansion-joints could considerably shorten the length of pipelines and, in consequence, lower the cost of the power plant. In the framework of its research and development program on fast reactors the French Atomic Energy.Commission, in cooperation with the industry, develops guidelines, backed up by experiments, to allow a safe design of pipe-lines and compensating-devices. The main points of these guidelines are discussed in this paper with the understanding, that they are tentative rules subject to changes. The guidelines are a complement to existing rules, like ASME - Code III, Code Case 1481, standards of the EJMA Preliminary Draft for Code Case Class I, Expansion Joints in Piping systems and suppliers' rules for the special case of application to sodium cooled fast breeder reactors. Relatively small diameters and easily accessible expansion joints, on control rods and valves for example, are not concerned. These guidelines do not apply to the bellows which are used as an integral part of a component.

Tentative design-philosophy for bellows in sodium cooled fast breeder reactors pipings

International Nuclear Information System (INIS)

Scaller, K.; Vrillon, B.

1980-01-01

Expansion joints have proved to be reliable components, when properly designed and realized, in normal industrial equipment. But nevertheless bellows have not been employed widely in nuclear reactors and almost not in sodium cooled fast breeder reactors, where use of expansion-joints could considerably shorten the length of pipelines and, in consequence, lower the cost of the power plant. In the framework of its research and development program on fast reactors the French Atomic Energy.Commission, in cooperation with the industry, develops guidelines, backed up by experiments, to allow a safe design of pipe-lines and compensating-devices. The main points of these guidelines are discussed in this paper with the understanding, that they are tentative rules subject to changes. The guidelines are a complement to existing rules, like ASME - Code III, Code Case 1481, standards of the EJMA Preliminary Draft for Code Case Class I, Expansion Joints in Piping systems and suppliers' rules for the special case of application to sodium cooled fast breeder reactors. Relatively small diameters and easily accessible expansion joints, on control rods and valves for example, are not concerned. These guidelines do not apply to the bellows which are used as an integral part of a component

Spatial effect of new municipal solid waste landfill siting using different guidelines.

Science.gov (United States)

Ahmad, Siti Zubaidah; Ahamad, Mohd Sanusi S; Yusoff, Mohd Suffian

2014-01-01

Proper implementation of landfill siting with the right regulations and constraints can prevent undesirable long-term effects. Different countries have respective guidelines on criteria for new landfill sites. In this article, we perform a comparative study of municipal solid waste landfill siting criteria stated in the policies and guidelines of eight different constitutional bodies from Malaysia, Australia, India, U.S.A., Europe, China and the Middle East, and the World Bank. Subsequently, a geographic information system (GIS) multi-criteria evaluation model was applied to determine new suitable landfill sites using different criterion parameters using a constraint mapping technique and weighted linear combination. Application of Macro Modeler provided in the GIS-IDRISI Andes software helps in building and executing multi-step models. In addition, the analytic hierarchy process technique was included to determine the criterion weight of the decision maker's preferences as part of the weighted linear combination procedure. The differences in spatial results of suitable sites obtained signifies that dissimilarity in guideline specifications and requirements will have an effect on the decision-making process.

Мотив искушений в драме Флобера «Искушение святого Антония» Le motif des tentations dans La Tentation de saint Antoine de Flaubert

Directory of Open Access Journals (Sweden)

Galina Modina

2009-01-01

Full Text Available Beaucoup d’œuvres de Flaubert ont des traits autobiographiques, mais c’est seulement avec le personnage de son drame philosophique La Tentation de saint Antoine que Flaubert s’identifie vraiment. L’image de saint Antoine accompagna l’écrivain pendant presque trente ans et se retrouve dans ses œuvres aux moments critiques de sa vie. Cependant, La Tentation de saint Antoine demeure l’un des drames les plus méconnus de Flaubert dans la critique littéraire russe. Cet article est un essai sur l’œuvre de Flaubert vue à travers le prisme du motif de la tentation. Celui-ci organise le contenu du drame et se développe de façon particulière dans ses différentes versions. Les deux premières datant de 1849 et 1856, et la version finale étant de 1874. Dans les premières versions de La Tentation de saint Antoine Flaubert montre de façon très visible le processus de transformation d’un homme mortel en Créateur. La formation de l’Artiste se déroule comme un sacrement mystérieux ressemblant aux anciens rituels. Les trois parties du drame, ainsi que leur enchaînement, rappellent les mystères d’Eleusis. Ici, les tentations sont des appels à l’abandon de la foi et de la possibilité de créer. La troisième version du drame est construite sur les motifs de la connaissance et de la foi, ainsi que de la vérité et du dogme. L’idée de la tentation est de décourager la recherche de la vérité. Le motif des tentations est très étroitement lié à la recherche de l’identité du personnage qui se veut Artiste. L’expérience intérieure de Flaubert se reflète dans les trois versions du drame : l’élimination de la vision tragique de l’antithèse « matériel et idéal », le passage du mysticisme de Pascal au panthéisme esthétique. Cette œuvre est l’histoire du développement de l’identité artistique de Flaubert où les tentations sont des éléments nécessaires à l’Artiste pour la connaissance de

Selection of suitable sites for NPP in Slovenia (stage 3)

International Nuclear Information System (INIS)

Grgic, M.; Fabjan, L.; Premru, U.

1977-01-01

Selection of suitable sites for nuclear power plants in Slovenia is considered. This includes the studies of available data on regional and local characteristics specified in general site suitability criteria for NPP. The most suitable selected sites will be included into land use urbanistic planning of Slovenia

Bioassay criteria for environmental restoration workers

International Nuclear Information System (INIS)

Carbaugh, E.H.; Bihl, D.E.

1993-01-01

Environmental restoration (ER) work at the U. S. Department of Energy Hanford Site posed questions concerning when to perform bioassay monitoring of workers for potential intakes of radioactivity. Application of criteria originally developed for use inside radionuclide processing facilities to ER work resulted in overly restrictive bioassay requirements. ER work typically involves site characterization or, excavating large quantities of potentially contaminated soil, rather than working with concentrated quantities of radioactivity as in a processing facility. An improved approach, tailored to ER work, provided soil contamination concentrations above which worker bioassay would be required. Soil concentrations were derived assuming acute or chronic intakes of 2% of an Annual Limit on Intake (ALI), or a potential committed effective dose equivalent of 100 mrem, and conservative dust loading of air from the work. When planning ER work, the anticipated soil concentration and corresponding need for bioassay could be estimated from work-site historical records. Once site work commenced, soil sampling and work-place surveys could be used to determine bioassay needs. This approach substantially reduced the required number of bioassay samples with corresponding reductions in analytical costs, schedules, and more flexible work-force management. (Work supported by the US Department of Energy under contract DOE-AC06-76RLO 1830.)

Licensed reactor nuclear safety criteria applicable to DOE reactors

International Nuclear Information System (INIS)

1991-04-01

The Department of Energy (DOE) Order DOE 5480.6, Safety of Department of Energy-Owned Nuclear Reactors, establishes reactor safety requirements to assure that reactors are sited, designed, constructed, modified, operated, maintained, and decommissioned in a manner that adequately protects health and safety and is in accordance with uniform standards, guides, and codes which are consistent with those applied to comparable licensed reactors. This document identifies nuclear safety criteria applied to NRC [Nuclear Regulatory Commission] licensed reactors. The titles of the chapters and sections of USNRC Regulatory Guide 1.70, Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants, Rev. 3, are used as the format for compiling the NRC criteria applied to the various areas of nuclear safety addressed in a safety analysis report for a nuclear reactor. In each section the criteria are compiled in four groups: (1) Code of Federal Regulations, (2) US NRC Regulatory Guides, SRP Branch Technical Positions and Appendices, (3) Codes and Standards, and (4) Supplemental Information. The degree of application of these criteria to a DOE-owned reactor, consistent with their application to comparable licensed reactors, must be determined by the DOE and DOE contractor

A framework of performance criteria defining sustainable construction technologies

International Nuclear Information System (INIS)

Sturges, W.G.

1992-01-01

As our global culture encounters accelerating rates of resource depletion, environmental degradation, and societal inequality, it increasingly needs tools to rate building systems by environmental and socioeconomic criteria. By investigating light frame structural systems based on principles of ecological design, it is possible to not only identify the structures' potential impacts on the health of their site and larger community, but also to establish a framework of performance criteria for comparatively evaluating a variety of construction technologies. This paper summarizes the development and application of such a framework, based upon the ecosystems and culture of the Pacific Northwest's Cascadia Bioregion. The framework has been comparatively applied to solid-sawn lumber, trusses, and composite wood I-joists. These three framing technologies together represent traditional, contemporary, and progressive structural systems. Their individual and collective performance, based upon the application of the hypothesized criteria, offer insights into what might be a more ideal framing system of the sustainable future

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

A systems analysis approach to nuclear facility siting

International Nuclear Information System (INIS)

Gros, J.G.; Avenhaus, R.; Linnerooth, J.; Pahner, P.D.; Otway, H.J.

1975-01-01

An attempt is made to demonstrate an application of the techniques of systems analysis, which have been successful in solving a variety of problems, to nuclear facility siting. Within the framework of an overall regional land-use plan, a methodology for establishing the acceptability of a combination of site and facility is discussed. The consequences (e.g. the energy produced, thermal and chemical discharges, radioactive releases, aeshetic values, etc.) of the site-facility combination are identified and compared with formalized criteria in order to ensure 'legal acceptability'. Failure of any consequences to satisfy standard requirements results in a feedback channel which works to effect design changes in the facility. When 'legal acceptability' has been assured, the project enters the public sector for consideration. The responses of individuals and of various interested groups to the external attributes of the nuclear facility gradually emerge. The criteria by which interest groups judge technological advances reflect both their rational assessment and unconscious motivations. This process operates on individual, group, societal and international levels and may result in two basic feedback loops: one which might act to change regulatory criteria; the other which might influence facility design or site selection. Such reactions and responses on these levels result in a continuing process of confrontation, collaborative interchange and possible resolution in the direction of an acceptable solution. Finally, a Paretian approach to optimizing the site-facility combination is presented for the case where there are several possible combinations of site and facility. A hypothetical example of the latter is given, based upon typical preference functions determined for four interest groups. The research effort of the IIASA Energy Systems Project and the Joint IAEA/IIASA Research Project in the area of nuclear siting is summarized. (author)

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

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.

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.

Monitored retrievable storage facility site screening and evaluation report

International Nuclear Information System (INIS)

1985-05-01

The Nuclear Waste Policy Act of 1982 directs the Department of Energy to ''complete a detailed study of the need for and feasibility of, and to submit to the Congress a proposal for, the construction of one or more monitored retrievable storage facilities for high level radioactive waste and spent nuclear fuel.'' The Act directs that the proposal includes site specific designs. Further, the proposal is to include, ''for the first such facility, at least three alternative sites and at least five alternative combinations of such proposed site and facility designs...'' as well as a recommendation of ''the combination among the alternatives that the Secretary deems preferable.'' An MRS Site Screening Task Force has been formed to help identify and evaluated potential MRS facility sites within a preferred region and with the application of a siting process and criteria developed by the DOE. The activities of the task force presented in this report includes: site screening (Sections 3, 4, and 5), the MRS facilities which are to be sited are described; the criteria, process and outcome of the screening process is presented; and descriptions of the candidate MRS facility sites are given, and site evaluations (Sections 6 through 9) where the rational for the site evaluations are presented, along with each evaluation and findings of the Task Force

Monitored retrievable storage facility site screening and evaluation report

Energy Technology Data Exchange (ETDEWEB)

none,

1985-05-01

The Nuclear Waste Policy Act of 1982 directs the Department of Energy to complete a detailed study of the need for and feasibility of, and to submit to the Congress a proposal for, the construction of one or more monitored retrievable storage facilities for high level radioactive waste and spent nuclear fuel.'' The Act directs that the proposal includes site specific designs. Further, the proposal is to include, for the first such facility, at least three alternative sites and at least five alternative combinations of such proposed site and facility designs...'' as well as a recommendation of the combination among the alternatives that the Secretary deems preferable.'' An MRS Site Screening Task Force has been formed to help identify and evaluated potential MRS facility sites within a preferred region and with the application of a siting process and criteria developed by the DOE. The activities of the task force presented in this report includes: site screening (Sections 3, 4, and 5), the MRS facilities which are to be sited are described; the criteria, process and outcome of the screening process is presented; and descriptions of the candidate MRS facility sites are given, and site evaluations (Sections 6 through 9) where the rational for the site evaluations are presented, along with each evaluation and findings of the Task Force.

Environmental analysis of a formerly utilized MED/AEC site: Site A and plot M, Palos Forest Preserve, Palos Park, Illinois

Energy Technology Data Exchange (ETDEWEB)

1979-09-01

This environmental analysis report describes the existing site environment and evaluates the environmental impacts of 8 options for remedial action, including allowing buried waste to remain undisturbed. Conformity or conflict with governmental statutes, regulations and standards was determined, especially with regard to compliance with contamination criteria and guidelines. The program of measurements, documentation, and control to demonstrate compliance with these criteria and guidelines was identified.

Environmental analysis of a formerly utilized MED/AEC site: Site A and plot M, Palos Forest Preserve, Palos Park, Illinois

International Nuclear Information System (INIS)

1979-09-01

This environmental analysis report describes the existing site environment and evaluates the environmental impacts of 8 options for remedial action, including allowing buried waste to remain undisturbed. Conformity or conflict with governmental statutes, regulations and standards was determined, especially with regard to compliance with contamination criteria and guidelines. The program of measurements, documentation, and control to demonstrate compliance with these criteria and guidelines was identified

Site investigations for final disposal of high-level nuclear waste

International Nuclear Information System (INIS)

Aeikaes, T.; Laine, T.

1982-12-01

Research concerning disposal of high-level nuclear waste of the Industrial Power Company Ltd has focused on deep underground disposal in Finnish precambrian bedrock. The present target is to have a repository for high-level waste in operation by 2020. Selection of the repository site is based on site investigations. In addition to geosciences, selection of appropriate site includes many branches of studies; engineering, safety analysis, ecology, transport, demography etc. The investigations required for site selection for high-level waste have been arranged in a sequence of four phases. The aim of the phases is that investigations become more and more detailed as the selection process continues. Phase I of the investigations is the characterization of potential areas. This comprises establishment of criteria for site selection and identification of areas that meet selection criteria. Objective of these studies is to determine areas for phase II field investigations. The studies are largely made by reviewing existing data and remote-sensing techniques. Phase II field investigations will be undertaken between 1986-1992. The number of potential candidates for repository site is reduced to few preferred areas by preceeding generic study. The site selection process culminates in phase III in site confirmation studies carried out at 2...3 most suitable sites during 1992-2010. This is then followed by phase IV, which comprises very detailed investigations at the selected site. An alternative for these investigations is to undertake them by using pilot shaft and drifts. Active development is taking place in all phases concerning investigation methods, criteria, parameters, data processing and modelling. The applicability of the various investigation methods and techniques is tested in a deep borehole in phase I. The co-operation with countries with similar geological conditions makes it possible to compare results obtained by different techniques

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

Final waste forms project: Performance criteria for phase I treatability studies

International Nuclear Information System (INIS)

Gilliam, T.M.; Hutchins, D.A.; Chodak, P. III

1994-06-01

This document defines the product performance criteria to be used in Phase I of the Final Waste Forms Project. In Phase I, treatability studies will be performed to provide open-quotes proof-of-principleclose quotes data to establish the viability of stabilization/solidification (S/S) technologies. This information is required by March 1995. In Phase II, further treatability studies, some at the pilot scale, will be performed to provide sufficient data to allow treatment alternatives identified in Phase I to be more fully developed and evaluated, as well as to reduce performance uncertainties for those methods chosen to treat a specific waste. Three main factors influence the development and selection of an optimum waste form formulation and hence affect selection of performance criteria. These factors are regulatory, process-specific, and site-specific waste form standards or requirements. Clearly, the optimum waste form formulation will require consideration of performance criteria constraints from each of the three categories. Phase I will focus only on the regulatory criteria. These criteria may be considered the minimum criteria for an acceptable waste form. In other words, a S/S technology is considered viable only if it meet applicable regulatory criteria. The criteria to be utilized in the Phase I treatability studies were primarily taken from Environmental Protection Agency regulations addressed in 40 CFR 260 through 265 and 268; and Nuclear Regulatory Commission regulations addressed in 10 CFR 61. Thus the majority of the identified criteria are independent of waste form matrix composition (i.e., applicable to cement, glass, organic binders etc.)