Procedural justice in wind facility siting: Recommendations for state-led siting processes

International Nuclear Information System (INIS)

Ottinger, Gwen; Hargrave, Timothy J.; Hopson, Eric

2014-01-01

Evidence suggests that state control of wind facility siting decisions fosters new project development more effectively than local control, yet the literature suggests that affected citizens tend to be more fairly represented in local siting processes. We argue that successful renewable energy policy must satisfy both the need for new project development and the obligation to procedural justice. To suggest how it can do so, we analyze existing state- and county-level siting processes in Washington state, finding that both fall short on measures of procedural justice. To overcome this limitation and address the tension between procedural justice and project development, we then propose a collaborative governance approach to wind facility siting, in which state governments retain ultimate authority over permitting decisions but encourage and support local-level deliberations as the primary means of making those decisions. Such an approach, we argue, would be more just, facilitate wind development by addressing community concerns constructively and result in better projects through the input of diverse stakeholders. - Highlights: • States have made wind energy development a priority. • Local opposition to new projects could hinder future wind energy development. • Procedural justice is necessary to resolve local issues and ensure timely wind facility siting. • Both state- and county-led siting processes fall short with respect to criteria for procedural justice, though local processes have some advantages. • States could instead induce counties, developers to engage in deliberation

Determination of import process during Yucca Mountain Site characterization

International Nuclear Information System (INIS)

Hastings, P.S.; Gwyn, D.W.; Wemheuer, R.F.

1996-01-01

Construction of an underground Exploratory Studies Facility (ESF) for characterizing the Yucca Mountain site precedes the design of a potential repository, with site characterization testing and ESF construction conducted as parallel activities. As a result of this fact, a program is required to: (1) provide for inclusion of the underground excavation into a potential repository, (2) minimize the potential impact of ESF construction on site characterization test results, and (3) minimize the potential impact of ESF construction and site characterization testing on the waste isolation capabilities of the site. At Yucca Mountain, the Determination of Importance (DI) process fulfills these goals. This paper addresses the evolution of the DI process; describes how the DI process fits into design, testing, and construction programs: and discusses how the process is implemented through specification requirements

The voluntary siting process: The solution to siting in the Northeast Compact

International Nuclear Information System (INIS)

Deshais, J.B.

1995-01-01

The date: June 10, 1991. The decision: the announcement of three 'candidate sites' for a low-level radioactive waste (LLRW) facility in Connecticut following statewide screening. The debate: the right of the citizens of the state to refuse to have this type of facility in their 'backyard' versus the State's responsibility to provide for the safe management of LLRW generated within its borders. The debacle: vigorous opposition, political involvement, no opportunity for effective dialogue with the candidate towns. The end: a legislative mandate to terminate the siting process. This series of events, familiar to those in the business of attempting to site and develop unwanted and unwelcome facilities, would have thwarted efforts to provide for disposal capacity in the Northeast Compact region. Connecticut's efforts to site a LLRW disposal facility pursuant to a traditional 'decide-announce-defend' approach had apparently failed. New Jersey, its partner in the Compact, was also ready to proceed with a similar process that would lead to the naming of several candidate sites, but suspended its efforts to review other siting alternatives. The problem: a new approach was needed. The answer: both states would pursue voluntary siting for the LLRW facilities. The result: the best chance for successful development of LLRW disposal capacity in the Northeast Compact region

Facility siting as a decision process at the Savannah River Site

International Nuclear Information System (INIS)

Wike, L.D.

1995-01-01

Site selection for new facilities at Savannah River Site (SRS) historically has been a process dependent only upon specific requirements of the facility. While this approach is normally well suited to engineering and operational concerns, it can have serious deficiencies in the modern era of regulatory oversight and compliance requirements. There are many issues related to the site selection for a facility that are not directly related to engineering or operational requirements; such environmental concerns can cause large schedule delays and budget impact,s thereby slowing or stopping the progress of a project. Some of the many concerns in locating a facility include: waste site avoidance, National Environmental Policy Act requirements, Clean Water Act, Clean Air Act, wetlands conservation, US Army Corps of Engineers considerations, US Fish and Wildlife Service statutes including threatened and endangered species issues, and State of South Carolina regulations, especially those of the Department of Health and Environmental Control. In addition, there are SRS restrictions on research areas set aside for National Environmental Research Park (NERP), Savannah River Ecology Laboratory, Savannah River Forest Station, University of South Carolina Institute of Archaeology and Anthropology, Southeastern Forest Experimental Station, and Savannah River Technology Center (SRTC) programs. As with facility operational needs, all of these siting considerations do not have equal importance. The purpose of this document is to review recent site selection exercises conducted for a variety of proposed facilities, develop the logic and basis for the methods employed, and standardize the process and terminology for future site selection efforts

Astrophysical site(s of r-process elements in galactic chemodynamical evolution model

Directory of Open Access Journals (Sweden)

Hirai Yutaka

2016-01-01

Full Text Available Astrophysical site(s of rapid neutron-capture process (r-process is (are not identified yet. Although core-collapse supernovae have been regarded as one of the possible candidates of the astrophysical site of r-process, nucleosynthesis studies suggest that serious difficulties in core-collapse supernovae to produce heavy elements with mass number of ≳110. Recent studies show that neutron star mergers (NSMs can synthesize these elements due to their neutron rich environment. Some chemical evolution studies of the Milky Way halo, however, hardly reproduce the observed star-to-star scatters of the abundance ratios of r-process elements (e.g., Eu in extremely metal-poor stars. This is because of their low rate (∼ 10−4 yr−1 for a Milky Way size galaxy and long merger time (≳ 100 Myr. This problem might be solved if the stars in the Galactic halo are consisted of the stars formed in dwarf galaxies where the star formation efficiencies were very low. In this study, we carry out numerical simulations of galactic chemo-dynamical evolution using an N-body/smoothed particle hydrodynamics code. We construct detailed chemo-dynamical evolution model for the Local Group dwarf spheroidal galaxies (dSphs assuming that the NSMs are the major source of r-process elements. Our models successfully reproduce the observed dispersion in [Eu/Fe] as a function of [Fe/H] if we set merger time of NSMs, ≲ 300 Myr with the Galactic NSM rate of ∼ 10−4 yr−1. In addition, our results are consistent with the observed metallicity distribution of dSphs. In the early phase (≲1 Gyr of galaxy evolution is constant due to low star formation efficiency of dSphs. This study supports the idea that NSMs are the major site of r-process nucleosynthesis.

Nuclear Material Processing at the Savannah River Site

International Nuclear Information System (INIS)

Severynse, T.F.

1998-07-01

Plutonium production for national defense began at Savannah River in the mid-1950s, following construction of production reactors and separations facilities. Following the successful completion of its production mission, the site's nuclear material processing facilities continue to operate to perform stabilization of excess materials and potentially support the disposition of these materials. A number of restoration and productivity improvement projects implemented in the 1980s, totaling nearly a billion dollars, have resulted in these facilities representing the most modern and only remaining operating large-scale processing facilities in the DOE Complex. Together with the Site's extensive nuclear infrastructure, and integrated waste management system, SRS is the only DOE site with the capability and mission of ongoing processing operations

Process for determining the remediation category of hazardous substance sites

International Nuclear Information System (INIS)

Sieben, A.K.

1994-01-01

An evaluation process has been developed that aids in selecting the appropriate remediation category of hazardous substance sites. Three general remediation categories have been established: No further Action: Potential Early Action: and Defer for RI/FS or Transition/Decontamination and Decommissioning. This evaluation method is a preliminary screening process only and will not identify the most appropriate remediation alternative for each site. The remedy selection process can proceed only after a remediation category is determined for each site. All sites are evaluated at a preliminary screening level to determine the general remediation category. After the first screen, a secondary evaluation is performed on both the PEA sites and the DEFER sites. For PEAs, this secondary evaluation will incorporate additional specific factors, such as a screening level risk assessment. For the DEFER sites feasibility factors will be used to distinguish between the sites which should undergo a normal RI/FS and the sites which will be recommended to be remediated in association with D ampersand D of buildings. Ultimately, all of the sites will be placed into one of four remediation categories

Review of site recommendation process in Draft Environmental Assessments

International Nuclear Information System (INIS)

Joy, H.; Longo, T.; Burton, E.S.

1985-01-01

In December 1984, the US Department of Energy (DOE) published Draft Environmental Assessments (EAs) on nine potentially acceptable nuclear waste repository sites. Five sites in the states of Mississippi, Nevada, Texas, Utah, and Washington were proposed in the Draft EAs for nomination under the Nuclear Waste Policy Act as suitable for further detailed study (site characterization). The Nevada, Texas, and Washington sites were further proposed for recommendation to the President as preferred for site characterization. This paper reviews the process that DOE used in selecting the three sites proposed for site characterization. The process is consistent with DOE's implementation guidelines for selecting repository sites, and proceeds in three steps. First, the sites are ranked in order of preference for each of twenty technical guidelines based on information in the Draft EAs. The second step combines the individual guideline rankings into postclosure and preclosure guideline group rankings, and, finally, into an overall ranking. In the third step, the sensitivity of the choice of the three preferred sites is examined for a range of guideline weightings

Site-specific analysis of radiological and physical parameters for cobbly soils at the Gunnison, Colorado, processing site

International Nuclear Information System (INIS)

1993-10-01

The remedial action at the Gunnison, Colorado, processing site is being performed under the Uranium Mill Tailings Radiation Control Act (UMTRCA) of 1978 [Public Law (PL) 95-6041]. Under UMTRCA, the US Environmental Protection Agency (EPA) is charged with the responsibility of developing appropriate and applicable standards for the cleanup of radiologically contaminated land and buildings at 24 designated sites, including the Gunnison, Colorado, inactive processing site. The remedial action at the processing site will be conducted to remove the tailings and contaminated materials to meet the EPA bulk soil cleanup standards for surface and subsurface soils. The site areas disturbed by remedial action excavation will be either contoured or backfilled with radiologically uncontaminated soil and contoured to restore the site. The final contours will produce a final surface grade that will create positive drainage from the site

Site-specific analysis of radiological and physical parameters for cobbly soils at the Gunnison, Colorado, processing site

International Nuclear Information System (INIS)

1994-01-01

The remedial action at the Gunnison, Colorado, processing site is being performed under the Uranium Mill Tailings Radiation Control Act (UMTRCA) of 1978. Under UMTRCA, the US Environmental Protection Agency (EPA) is charged with the responsibility of developing appropriate and applicable standards for the cleanup of radiologically contaminated land and buildings at 24 designated sites, including the Gunnison, Colorado, inactive processing site. Section 108 of Public Law 95-604 states that the US Department of Energy (DOE) shall ''select and perform remedial actions at the designated processing sites and disposal sites in accordance with the general standards'' prescribed by the EPA. Regulations governing the required remedial action at inactive uranium processing sites were promulgated by the EPA in 1983 and are contained in 40 CFR Part 192 (1993), Health and Environmental Protection Standards for Uranium and Thorium Mill Tailings. This document describes the radiological and physical parameters for the remedial action of the soil

Wind Energy Deployment Process and Siting Tools (Presentation)

Energy Technology Data Exchange (ETDEWEB)

Tegen, S.

2015-02-01

Regardless of cost and performance, some wind projects cannot proceed to completion as a result of competing multiple uses or siting considerations. Wind energy siting issues must be better understood and quantified. DOE tasked NREL researchers with depicting the wind energy deployment process and researching development considerations. This presentation provides an overview of these findings and wind siting tools.

Site-specific analysis of the cobbly soils at the Grand Junction processing site

International Nuclear Information System (INIS)

1992-06-01

This report describes a recent site-specific analysis to evaluate the necessity of a recommendation to install a slurry trench around the Grand Junction processing site. The following analysis addresses the cobbly nature of the site's radiologically contaminated foundation soil, reassesses the excavation depths based on bulk radionuclide concentrations, and presents data-based arguments that support the elimination of the initially proposed slurry trench. The slurry trench around the processing site was proposed by the Remedial Action Contractor (RAC) to minimize the amount of water encountered during excavation. The initial depths of excavation developed during conceptual design, which indicated the need for a slurry wall, were reexamined as part of this analysis. This reanalysis, based on bulk concentrations of a cobbly subsoil, supports decreasing the original excavation depth, limiting the dewatering quantities to those which can be dissipated by normal construction activities. This eliminates the need for a slurry trench andseparate water treatment prior to permitted discharge

Evaluating the potential of process sites for waste heat recovery

International Nuclear Information System (INIS)

Oluleye, Gbemi; Jobson, Megan; Smith, Robin; Perry, Simon J.

2016-01-01

Highlights: • Analysis considers the temperature and duties of the available waste heat. • Models for organic Rankine cycles, absorption heat pumps and chillers proposed. • Exploitation of waste heat from site processes and utility systems. • Concept of a site energy efficiency introduced. • Case study presented to illustrate application of the proposed methodology. - Abstract: As a result of depleting reserves of fossil fuels, conventional energy sources are becoming less available. In spite of this, energy is still being wasted, especially in the form of heat. The energy efficiency of process sites (defined as useful energy output per unit of energy input) may be increased through waste heat utilisation, thereby resulting in primary energy savings. In this work, waste heat is defined and a methodology developed to identify the potential for waste heat recovery in process sites; considering the temperature and quantity of waste heat sources from the site processes and the site utility system (including fired heaters and, the cogeneration, cooling and refrigeration systems). The concept of the energy efficiency of a site is introduced – the fraction of the energy inputs that is converted into useful energy (heat or power or cooling) to support the methodology. Furthermore, simplified mathematical models of waste heat recovery technologies using heat as primary energy source, including organic Rankine cycles (using both pure and mixed organics as working fluids), absorption chillers and absorption heat pumps are developed to support the methodology. These models are applied to assess the potential for recovery of useful energy from waste heat. The methodology is illustrated for an existing process site using a case study of a petroleum refinery. The energy efficiency of the site increases by 10% as a result of waste heat recovery. If there is an infinite demand for recovered energy (i.e. all the recoverable waste heat sources are exploited), the site

Revenue-based cost assignment: a potent but hidden threat to the survival of the multispecialty medical practice.

Science.gov (United States)

Cooper, Robin; Kramer, Theresa R

2010-03-01

To demonstrate detrimental effects of revenue-based cost assignment (RBCA) in clinical practice and to compare that system with activity-based costing (ABC). Four cost-allocation methods including RBCA were applied to a comprehensive ophthalmology practice using typical accounting methods. Data were obtained by a survey of practitioners or practices and/or extracted from decision support and practice management systems. Inaccuracies and distortions in reported costs were enumerated. Accounting scenario analysis was used to predict resultant provider and managerial decisions. A sampling survey was used to analyze other specialties. ABC was applied to the practice. RBCA causes procedures with higher profitability to appear less profitable and those with lower profitability to appear more profitable. The distortion in reported costs, in medical settings, is often sufficient to incentivize providers with higher profitability to exit a practice and those with lower profitability to remain in it. The departure of providers causes the residual practice profits to decline. These detrimental effects occur in many subspecialties, which suggests a national effect on health care. ABC allocation can reduce cost distortions and eliminate detrimental effects. RBCA leads to fragmentation of health care and a reduction in the profitability of multispecialty practices. Its use may slow the updating of reimbursement and help eliminate low-profitability specialties.

Geosphere process report for the safety assessment SR-Site

International Nuclear Information System (INIS)

Skagius, Kristina

2010-11-01

This report documents geosphere processes identified as relevant to the long-term safety of a KBS-3 repository, and forms an important part of the reporting of the safety assessment SR-Site. The detailed assessment methodology, including the role of the process reports in the assessment, is described in the SR-Site Main report /SKB 2011/

Geosphere process report for the safety assessment SR-Site

Energy Technology Data Exchange (ETDEWEB)

Skagius, Kristina (ed.) (Kemakta Konsult AB, Stockholm (Sweden))

2010-11-15

This report documents geosphere processes identified as relevant to the long-term safety of a KBS-3 repository, and forms an important part of the reporting of the safety assessment SR-Site. The detailed assessment methodology, including the role of the process reports in the assessment, is described in the SR-Site Main report /SKB 2011/

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''

Power plant siting; an application of the nominal group process technique

International Nuclear Information System (INIS)

Voelker, A.H.

1976-01-01

The application of interactive group processes to the problem of facility siting is examined by this report. Much of the discussion is abstracted from experience gained in applying the Nominal Group Process Technique, an interactive group technique, to the identification and rating of factors important in siting nuclear power plants. Through this experience, interactive group process techniques are shown to facilitate the incorporation of the many diverse factors which play a role in siting. In direct contrast to mathematical optimization, commonly represented as the ultimate siting technique, the Nominal Group Process Technique described allows the incorporation of social, economic, and environmental factors and the quantification of the relative importance of these factors. The report concludes that the application of interactive group process techniques to planning and resource management will affect the consideration of social, economic, and environmental concerns and ultimately lead to more rational and credible siting decisions

RECRUITMENT PROCESS IN MNC'S THROUGH SOCIAL MEDIA SITES - A STUDY

OpenAIRE

Dr. B. L. Sairam Subramaniam; B. Naveen Kumar

2017-01-01

Many organizations are carrying out recruitment process by using social media networking sites. Social networking sites are used to facilitate and improve process of recruitment method in HR management. Social networking sites address the needs of employers and job-seekers via internetworking on electronic platform likes face book, twitter, LinkedIn, naukri.com, and monster.com which increase the speed of employment, reducing the cost of recruitment, huge availability of jobseekers and improv...

Investigation of the site selection examples adopted local participation. The site selection processes in Belgium, UK and Switzerland

International Nuclear Information System (INIS)

Kageyama, Hitoshi; Suzuki, Shinji; Hirose, Ikuro; Yoshioka, Tatsuji

2014-06-01

In late years, local participation policies are being adopted in foreign countries at site selection for the disposal of the radioactive waste. We performed documents investigation about the examples of the site selection processes of Belgium, the U.K., and Switzerland to establish the site selection policy in Japan. In Belgium, after the failure of the site selection for the disposal of short-lived low and intermediate level radioactive waste (LILW) in an early stage, the idea of the local partnership (LP) was developed and three independent LPs were established between the implementing body and each municipality. About 7 years later, one site was decided as the disposal site in the cabinet meeting of the federal government. In the U.K., after the failure of the site selection for the rock characterization facility, the government policy was changed and the consultation process comprised of six phases was started. Though the process had been carried out for over 4 years since one combined partnership was established between the implementing body and the municipalities involved, they had to withdraw from the consulting process because a county council had not accepted that the process would step forward to the 4th phase. In Switzerland, the implementing body selected one site for LILW disposal at an early stage, but the project was denied by the referendum in the Canton having jurisdiction over the site area. After that the Federal Parliament established new Nuclear Energy Act and Nuclear Energy Ordinance precluding the veto of Canton. Now the site selection project is being carried out according to the process comprised of three phases with local participation policy. Reviewing the merits and demerits of each example through this investigation, we confirmed if we are to adopt local participation policy in our country in future, further prudent study would be necessary, considering current and future social conditions in Japan. (author)

Addendum to the Closure Report for Corrective Action Unit 404: Roller Coaster Sewage Lagoons and North Disposal Trench, Tonopah Test Range, Nevada, Revision 1

Energy Technology Data Exchange (ETDEWEB)

Lynn Kidman

2009-02-01

This document constitutes an addendum to the September 1998, Closure Report for Corrective Action Unit 404: Roller Coaster Lagoons and Trench, Tonopah Test Range, Nevada as described in the document Recommendations and Justifications for Modifications for Use Restrictions Established under the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office Federal Facility Agreement and Consent Order (UR Modification document) dated February 2008. The UR Modification document was approved by NDEP on February 26, 2008. The approval of the UR Modification document constituted approval of each of the recommended UR modifications. In conformance with the UR Modification document, this addendum consists of: • This cover page that refers the reader to the UR Modification document for additional information • The cover and signature pages of the UR Modification document • The NDEP approval letter • The corresponding section of the UR Modification document This addendum provides the documentation justifying the modification of the UR for CAS TA-03-001-TARC Roller Coaster Lagoons. This UR was established as part of Federal Facility Agreement and Consent Order (FFACO) corrective actions and was based on the presence of contaminants at concentrations greater than the action levels established at the time of the initial investigation (FFACO, 1996; as amended August 2006). Since this UR was established, practices and procedures relating to the implementation of risk-based corrective actions (RBCA) have changed. Therefore, this UR was re-evaluated against the current RBCA criteria as defined in the Industrial Sites Project Establishment of Final Action Levels (NNSA/NSO, 2006c). This reevaluation consisted of comparing the original data (used to define the need for the UR) to risk-based final action levels (FALs) developed using the current Industrial Sites RBCA process. The re-evaluation resulted in a recommendation to modify the UR for CAS TA-03

Hanford Site Composite Analysis Technical Approach Description: Radionuclide Inventory and Waste Site Selection Process.

Energy Technology Data Exchange (ETDEWEB)

Nichols, Will E.; Mehta, Sunil

2017-09-13

The updated Hanford Site Composite Analysis will provide an all-pathways dose projection to a hypothetical future member of the public from all planned low-level radioactive waste disposal facilities and potential contributions from all other projected end-state sources of radioactive material left at Hanford following site closure. Its primary purpose is to support the decision-making process of the U.S. Department of Energy (DOE) under DOE O 435.1-1, Radioactive Waste Management (DOE, 2001), related to managing low-level waste disposal facilities at the Hanford Site.

International workshop on site investigation and evaluation based on the siting process in Sweden

International Nuclear Information System (INIS)

Andersson, Johan; Stroem, A.

2001-06-01

SKB's goal is to commence surface based site investigations in 2002. Extensive preparations are now being made for this transition to the next phase in the siting process for the deep repository for spent nuclear fuel. The purpose of the international workshop on site characterisation held at Aespoe April 2001 was to: present the SKB site investigation and evaluation programme to a group of international experts; discuss whether the available toolbox of investigation methods for surface based site investigations is appropriate and state-of-the-art in an international perspective; and by working group sessions discuss the level of ambition in the programme for site investigation for each discipline. This report summarises the conclusions of the workshop in general terms. Many of the detailed comments and ideas obtained at the workshop have already inspired and will also directly inspire the on-going planning work for site characterisation. The core activity at the workshop was the work performed by working groups. They addressed what should be considered for a site characterisation programme, based on the generic planning made so far by SKB. The working groups also outlined site specific characterisation programmes for the sites suggested by SKB. The tasks were strictly confined to technical and scientific modelling issues. The working group chairmen presented the working group results at the workshop and have also submitted short memos to SKB. The present document is a compilation of these memos. The SKB generic programme as presented in the existing top level documents, 'Requirements and Criteria and Overall Programme', received general endorsement and was appreciated for being comprehensive and systematic. For example, it contains comprehensive lists of parameters to be measured. However, there is need for prioritisation and sequencing. This is actually included in the current planning process at SKB where the generic programme later this year will be adapted to

Applications of Ecological Engineering Remedies for Uranium Processing Sites, USA

Energy Technology Data Exchange (ETDEWEB)

Waugh, William [Navarro Research and Engineering

2016-05-23

The U.S. Department of Energy (USDOE) is responsible for remediation of environmental contamination and long-term stewardship of sites associated with the legacy of nuclear weapons production during the Cold War in the United States. Protection of human health and the environment will be required for hundreds or even thousands of years at many legacy sites. USDOE continually evaluates and applies advances in science and technology to improve the effectiveness and sustainability of surface and groundwater remedies (USDOE 2011). This paper is a synopsis of ecological engineering applications that USDOE is evaluating to assess the effectiveness of remedies at former uranium processing sites in the southwestern United States. Ecological engineering remedies are predicated on the concept that natural ecological processes at legacy sites, once understood, can be beneficially enhanced or manipulated. Advances in tools for characterizing key processes and for monitoring remedy performance are demonstrating potential. We present test cases for four ecological engineering remedies that may be candidates for international applications.

OPTIMIZING MAINTENANCE PROCESSES ON CUSTOMER SITE IN A DECENTRALIZED ORGANIZATION BASED ON MULTI-SITE TEAMS

Directory of Open Access Journals (Sweden)

Jorge Moutinho

2015-03-01

Full Text Available This lecture focuses on the complexity to manage and optimize maintenance processes, operations and service tasks to equipments and systems installed at customer sites. Different locations, access and working environment may compromise any standardization of setup's and operations. Multi-site teams based on geographic strategic locations, adds complexity to trainning, communication, supervising and monitoring processes. Logistics and information systems assume relevant rolls to consolidate global performance. Beside efficiency, effectiveness productivity and flexibility, field teams need skills on autonomy responsibility and proactivity. This lecture also explores the needed adaptation of most part of available literature, normally based on production sites, as also of Lean- Kaizen principles to the fact that services can not be stocked, quality is normally more difficult to measure and customer is normally present when and where service is produced.

Stability of choice in the honey bee nest-site selection process.

Science.gov (United States)

Nevai, Andrew L; Passino, Kevin M; Srinivasan, Parthasarathy

2010-03-07

We introduce a pair of compartment models for the honey bee nest-site selection process that lend themselves to analytic methods. The first model represents a swarm of bees deciding whether a site is viable, and the second characterizes its ability to select between two viable sites. We find that the one-site assessment process has two equilibrium states: a disinterested equilibrium (DE) in which the bees show no interest in the site and an interested equilibrium (IE) in which bees show interest. In analogy with epidemic models, we define basic and absolute recruitment numbers (R(0) and B(0)) as measures of the swarm's sensitivity to dancing by a single bee. If R(0) is less than one then the DE is locally stable, and if B(0) is less than one then it is globally stable. If R(0) is greater than one then the DE is unstable and the IE is stable under realistic conditions. In addition, there exists a critical site quality threshold Q(*) above which the site can attract some interest (at equilibrium) and below which it cannot. We also find the existence of a second critical site quality threshold Q(**) above which the site can attract a quorum (at equilibrium) and below which it cannot. The two-site discrimination process, in which we examine a swarm's ability to simultaneously consider two sites differing in both site quality and discovery time, has a stable DE if and only if both sites' individual basic recruitment numbers are less than one. Numerical experiments are performed to study the influences of site quality on quorum time and the outcome of competition between a lower quality site discovered first and a higher quality site discovered second. 2009 Elsevier Ltd. All rights reserved.

Summary of some feasibility studies for site-specific solar industrial process heat

Energy Technology Data Exchange (ETDEWEB)

None

1982-01-01

Some feasibility studies for several different site specific solar industrial process heat applications are summarized. The followng applications are examined. Leather Tanning; Concrete Production: Lumber and Paper Processing; Milk Processing; Molding, Curing or Drying; Automobile Manufacture; and Food Processing and Preparation. For each application, site and process data, system design, and performance and cost estimates are summarized.

Conflict between public perceptions and technical processes in site selection

International Nuclear Information System (INIS)

Avant, R.V. Jr.; Jacobi, L.R.

1985-01-01

U.S. Nuclear Regulatory Commission regulations and guidance on site selection are based on sound technical reasoning. Geology, hydrology, flora and fauna, transportation, demographics, and sociopolitical concerns, to name a few, have been factored into the process. Regardless of the technical objectivity of a site selection process, local opposition groups will challenge technical decisions using technical, nontechnical, and emotional arguments. This paper explores the many conflicts between public perceptions, technical requirements designed to protect the general public, and common arguments against site selection. Ways to deal with opposition are also discussed with emphasis placed on developing effective community relations

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.

Integrated Site Model Process Model Report

International Nuclear Information System (INIS)

Booth, T.

2000-01-01

The Integrated Site Model (ISM) provides a framework for discussing the geologic features and properties of Yucca Mountain, which is being evaluated as a potential site for a geologic repository for the disposal of nuclear waste. The ISM is important to the evaluation of the site because it provides 3-D portrayals of site geologic, rock property, and mineralogic characteristics and their spatial variabilities. The ISM is not a single discrete model; rather, it is a set of static representations that provide three-dimensional (3-D), computer representations of site geology, selected hydrologic and rock properties, and mineralogic-characteristics data. These representations are manifested in three separate model components of the ISM: the Geologic Framework Model (GFM), the Rock Properties Model (RPM), and the Mineralogic Model (MM). The GFM provides a representation of the 3-D stratigraphy and geologic structure. Based on the framework provided by the GFM, the RPM and MM provide spatial simulations of the rock and hydrologic properties, and mineralogy, respectively. Functional summaries of the component models and their respective output are provided in Section 1.4. Each of the component models of the ISM considers different specific aspects of the site geologic setting. Each model was developed using unique methodologies and inputs, and the determination of the modeled units for each of the components is dependent on the requirements of that component. Therefore, while the ISM represents the integration of the rock properties and mineralogy into a geologic framework, the discussion of ISM construction and results is most appropriately presented in terms of the three separate components. This Process Model Report (PMR) summarizes the individual component models of the ISM (the GFM, RPM, and MM) and describes how the three components are constructed and combined to form the ISM

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.

Communication activities for NUMO's site selection process

International Nuclear Information System (INIS)

Takeuchi, Mitsuo; Okuyama, Shigeru; Kitayama, Kazumi; Kuba, Michiyoshi

2004-01-01

A siting program for geological disposal of high-level radioactive waste (HLW) in Japan has just started and is moving into a new stage of communication with the public. A final repository site will be selected via a stepwise process, as stipulated in the Specified Radioactive Waste Final Disposal Act promulgated in June 2000. Based on the Act, the site selection process of the Nuclear Waste Management Organization of Japan (NUMO, established in October 2000) will be carried out in the three steps: selection of Preliminary Investigation Areas (PIAs), selection of Detailed Investigation Areas (DIAs) and selection of the Repository Site. The Act also defines NUMO's responsibilities in terms of implementing the HLW disposal program in an open and transparent manner. NUMO fully understands the importance of public participation in its activities and is aiming to promote public involvement in the process of site selection based on a fundamental policy, which consists of 'adopting a stepwise approach', 'respecting the initiative of municipalities' and 'ensuring transparency in information disclosure'. This policy is clearly reflected in the adoption of an open solicitation approach for volunteer municipalities for Preliminary Investigation Areas (PIAs). NUMO made the official announcement of the start of its open solicitation program on 19 December 2002. This paper outlines how NUMO's activities are currently carried out with a view to encouraging municipalities to volunteer as PIAs and how public awareness of the safety of the HLW disposal is evaluated at this stage

Fuel and canister process report for the safety assessment SR-Site

International Nuclear Information System (INIS)

Werme, Lars; Lilja, Christina

2010-12-01

This report documents fuel and canister processes identified as relevant to the long-term safety of a KBS-3 repository. It forms an important part of the reporting of the safety assessment SR-Site. The detailed assessment methodology, including the role of the process reports in the assessment, is described in the SR-Site Main report /SKB 2011/

Fuel and canister process report for the safety assessment SR-Site

Energy Technology Data Exchange (ETDEWEB)

Werme, Lars; Lilja, Christina (eds.)

2010-12-15

This report documents fuel and canister processes identified as relevant to the long-term safety of a KBS-3 repository. It forms an important part of the reporting of the safety assessment SR-Site. The detailed assessment methodology, including the role of the process reports in the assessment, is described in the SR-Site Main report /SKB 2011/

Risk assessment for nuclear processes at the Savannah River Site

International Nuclear Information System (INIS)

Durant, W.S.

1992-01-01

The Savannah River Site, one of the US Department of Energy's nuclear materials processing facilities, has for many years conducted risk-based safety analyses for the nuclear processes conducted at the facilities. This approach has allowed comparisons of risks to established criteria for acceptability. When the risk-based program was begun, it was evident that its success would depend upon having a compilation of data that was site specific. The decision was made to create a data bank of undesirable events that had occurred at the site's nuclear fuel reprocessing facilities. From this modest beginning, five data banks have been created for nuclear fuel reprocessing, waste management, nuclear fuel fabrication, tritium operations, and the Savannah River Technology Center. In addition to the primary purpose of providing a sound basis for risk-based safety analyses, these highly versatile data banks are routinely used for equipment breakdown histories, incident investigations, design studies, project justifications, reliability studies, process problem solving, training, and audits

Transport processes investigation: A necessary first step in site scale characterization plans

International Nuclear Information System (INIS)

Roepke, C.; Glass, R.J.; Brainard, J.; Mann, M.; Kriel, K.; Holt, R.; Schwing, J.

1995-01-01

We propose an approach, which we call the Transport Processes Investigation or TPI, to identify and verify site-scale transport processes and their controls. The TPI aids in the formulation of an accurate conceptual model of flow and transport, an essential first step in the development of a cost effective site characterization strategy. The TPI is demonstrated in the highly complex vadose zone of glacial tills that underlie the Fernald Environmental Remediation Project (FEMP) in Fernald, Ohio. As a result of the TPI, we identify and verify the pertinent flow processes and their controls, such as extensive macropore and fracture flow through layered clays, which must be included in an accurate conceptual model of site-scale contaminant transport. We are able to conclude that the classical modeling and sampling methods employed in some site characterization programs will be insufficient to characterize contaminant concentrations or distributions at contaminated or hazardous waste facilities sited in such media

Remedial action plan and site design for stabilization of the inactive uranium processing site at Naturita, Colorado

International Nuclear Information System (INIS)

1993-08-01

The uranium processing site near Naturita, Colorado, is one of 24 inactive uranium mill sites designated to be cleaned up by the US Department of Energy (DOE) under the Uranium Mill Tailings Radiation Control Act of 1978 (UMTRCA), Public Law 95-604. Part of the UMTRCA requires that the US Nuclear Regulatory Commission (NRC) concur with the DOE's remedial action plan (RAP) and certify that the remedial action conducted at the site complies with the standards promulgated by the US Environmental Protection Agency (EPA). Included in the RAP is this Remedial Action Selection Report (RAS), which serves two purposes. First, it describes the activities that are proposed by the DOE to accomplish remediation and long-term stabilization and control of the radioactive materials at the inactive uranium processing site near Naturita, Colorado. Second, this document and the rest of the RAP, upon concurrence and execution by the DOE, the state of Colorado, and the NRC, become Appendix B of the cooperative agreement between the DOE and the State of Colorado

THE SITE DEMONSTRATION OF CHEMFIX SOLIDIFICATION/ STABILIZATION PROCESS AT THE PORTABLE EQUIPMENT SALVAGE COMPANY SITE

Science.gov (United States)

A demonstration of the GHEMFIX solidification/stabilization process was conducted under the United States Environmental Protection Agency`s (EPA) Superfund Innovative Technology Evaluation (SITE) program. The demonstration was conducted in March 1989, at the Portable Equipment Sa...

Completion report for the UMTRA Project Vitro Processing Site. Revision 1

International Nuclear Information System (INIS)

1995-03-01

This completion report provides evidence that the final Salt Lake City, Utah, processing site property conditions are in accordance with the approved design and that all US Environmental Protection Agency (EPA) standards have been satisfied. Included as appendixes to support the stated conclusions are the record drawings; a summary of grid test results; contract specifications and construction drawings, the EPA standards (40 CFR Part 192); the audit, inspection, and surveillance summary; the permit information; and project photographs. The principal objective of the remedial action at Salt Lake City is to remove the tailings from the Vitro processing site, render the site free of contamination to EPA standards, and restore the site to the final design grade elevations. The final remedial action plan (RAP), which is approved by the US Department of Energy (DOE) and concurred upon by the US Nuclear Regulatory Commission (NRC) and the state of Utah, contains the conceptual design used to develop the final approved design. During remedial action construction operations, conditions were encountered that required design features that differed from the conceptual design. These conditions and the associated design changes are noted in the record drawings. All remedial action activities were completed in conformance with the specifications and drawings; the record drawings, in the state of Utah's opinion, reflect an accurate depiction of the existing property conditions at the processing site. 25 refs., 3 figs., 22 tabs

Site selection and characterization processes for deep geologic disposal of high level nuclear waste

International Nuclear Information System (INIS)

Costin, L.S.

1997-10-01

In this paper, the major elements of the site selection and characterization processes used in the US high level waste program are discussed. While much of the evolution of the site selection and characterization processes have been driven by the unique nature of the US program, these processes, which are well defined and documented, could be used as an initial basis for developing site screening, selection, and characterization programs in other countries. Thus, this paper focuses more on the process elements than the specific details of the US program

Remedial action plan and site design for stabilization of the inactive uranium processing site at Naturita, Colorado

International Nuclear Information System (INIS)

1994-03-01

Attachment 3 Groundwater Hydrology Report describes the hydrogeology, water quality, and water resources at the processing site and Dry Flats disposal site. The Hydrological Services calculations contained in Appendix A of Attachment 3, are presented in a separate report. Attachment 4 Water Resources Protection Strategy describes how the remedial action will be in compliance with the proposed EPA groundwater standards

The role of safety analyses in site selection. Some personal observations based on the experience from the Swiss site selection process

Energy Technology Data Exchange (ETDEWEB)

Zuidema, Piet [Nagra, Wettingen (Switzerland)

2015-07-01

In Switzerland, the site selection process according to the ''Sectoral Plan for Deep Geological Repositories'' (BFE 2008) is underway since 2008. This process takes place in three stages. In stage 1 geological siting regions (six for the L/ILW repository and three for the HLW repository) have been identified, in stage 2 sites for the surface facilities have been identified for all siting regions in close co-operation with the sting regions and a narrowing down of the number of siting regions based on geological criteria will take place. In stage 3 the sites for a general license application are selected and the general license applications will be submitted which eventually will lead to the siting decision for both repository types. In the Swiss site selection process, safety has the highest priority. Many factors affect safety and thus a whole range of safety-related issues are considered in the identification and screening of siting possibilities. Besides dose calculations a range of quantitative and qualitative issues are considered. Dose calculations are performed in all three stages of the site selection process. In stage 1 generic safety calculations were made to develop criteria to be used for the identification of potential siting regions. In stage 2, dose calculations are made for comparing the different siting regions according to a procedure prescribed in detail by the regulator. Combined with qualitative evaluations this will lead to a narrowing down of the number of siting regions to at least two siting regions for each repository type. In stage 3 full safety cases will be prepared as part of the documentation for the general license applications. Besides the dose calculations, many other issues related to safety are analyzed in a quantitative and qualitative manner. These consider the 13 criteria defined in the Sectoral Plan and the corresponding indicators. The features analyzed cover the following broad themes: efficiency of

The role of safety analyses in site selection. Some personal observations based on the experience from the Swiss site selection process

International Nuclear Information System (INIS)

Zuidema, Piet

2015-01-01

In Switzerland, the site selection process according to the ''Sectoral Plan for Deep Geological Repositories'' (BFE 2008) is underway since 2008. This process takes place in three stages. In stage 1 geological siting regions (six for the L/ILW repository and three for the HLW repository) have been identified, in stage 2 sites for the surface facilities have been identified for all siting regions in close co-operation with the sting regions and a narrowing down of the number of siting regions based on geological criteria will take place. In stage 3 the sites for a general license application are selected and the general license applications will be submitted which eventually will lead to the siting decision for both repository types. In the Swiss site selection process, safety has the highest priority. Many factors affect safety and thus a whole range of safety-related issues are considered in the identification and screening of siting possibilities. Besides dose calculations a range of quantitative and qualitative issues are considered. Dose calculations are performed in all three stages of the site selection process. In stage 1 generic safety calculations were made to develop criteria to be used for the identification of potential siting regions. In stage 2, dose calculations are made for comparing the different siting regions according to a procedure prescribed in detail by the regulator. Combined with qualitative evaluations this will lead to a narrowing down of the number of siting regions to at least two siting regions for each repository type. In stage 3 full safety cases will be prepared as part of the documentation for the general license applications. Besides the dose calculations, many other issues related to safety are analyzed in a quantitative and qualitative manner. These consider the 13 criteria defined in the Sectoral Plan and the corresponding indicators. The features analyzed cover the following broad themes: efficiency of

The Need to Assess Public Values in a Site Selection Process

International Nuclear Information System (INIS)

Sheng, Grant; Fortier, Michael

2001-01-01

Siting a nuclear fuel waste disposal facility is highly problematic for both technical and nontechnical reasons. The majority of countries using nuclear energy and many in the scientific community favour burying the spent fuel deep in a stable geological formation. It is our contention that site selection of a disposal facility must consider social, political, spatial and scientific perspectives in a comprehensive and integrated fashion in order to achieve a successful process. Moreover, we submit that people's values must be explicitly recognized and be taken into account through a formalized process during deliberations on the disposal concept, the process of evaluation of the concept, and the site selection process. The purpose of this paper is: (1) to identify the importance of recognizing people's values in the process of determining 'public acceptability', (2) to outline a possible framework by which public acceptability can be gauged through a formalized process of value elicitation, and (3) to introduce a novel method by which a web-based geographic information systems (GIS) application can be used as a tool for value elicitation. In order to assess effectively the public acceptability of Canada's nuclear waste disposal concept, we submit that such a process must examine the underlying values that are held by the public. Moreover, the evaluation process of Canada's concept demonstrates that an acceptable process is a pre-condition for an acceptable result, although such a process does not necessarily guarantee an acceptable result. However, the consequences of a flawed process can be very significant, as shown by Canada's experience. This paper also provides a brief overview of a value elicitation process that, in our opinion, could be used to assess the public acceptability of the Concept. We also describe how a web-based GIS application could be used to infer some of the underlying values held by the public

Site selection and characterization processes for deep geologic disposal of high level nuclear waste

International Nuclear Information System (INIS)

Costin, L.S.

1997-01-01

In this paper, the major elements of the site selection and characterization processes used in the U. S. high level waste program are discussed. While much of the evolution of the site selection and characterization processes have been driven by the unique nature of the U. S. program, these processes, which are well-defined and documented, could be used as an initial basis for developing site screening, selection, and characterization programs in other countries. Thus, this paper focuses more on the process elements than the specific details of the U. S. program. (author). 3 refs., 2 tabs., 5 figs

Site selection and characterization processes for deep geologic disposal of high level nuclear waste

Energy Technology Data Exchange (ETDEWEB)

Costin, L.S. [Sandia National Labs., Albuquerque, NM (United States)

1997-12-31

In this paper, the major elements of the site selection and characterization processes used in the U. S. high level waste program are discussed. While much of the evolution of the site selection and characterization processes have been driven by the unique nature of the U. S. program, these processes, which are well-defined and documented, could be used as an initial basis for developing site screening, selection, and characterization programs in other countries. Thus, this paper focuses more on the process elements than the specific details of the U. S. program. (author). 3 refs., 2 tabs., 5 figs.

Analytic hierarchy process helps select site for limestone quarry expansion in Barbados.

Science.gov (United States)

Dey, Prasanta Kumar; Ramcharan, Eugene K

2008-09-01

Site selection is a key activity for quarry expansion to support cement production, and is governed by factors such as resource availability, logistics, costs, and socio-economic-environmental factors. Adequate consideration of all the factors facilitates both industrial productivity and sustainable economic growth. This study illustrates the site selection process that was undertaken for the expansion of limestone quarry operations to support cement production in Barbados. First, alternate sites with adequate resources to support a 25-year development horizon were identified. Second, technical and socio-economic-environmental factors were then identified. Third, a database was developed for each site with respect to each factor. Fourth, a hierarchical model in analytic hierarchy process (AHP) framework was then developed. Fifth, the relative ranking of the alternate sites was then derived through pair wise comparison in all the levels and through subsequent synthesizing of the results across the hierarchy through computer software (Expert Choice). The study reveals that an integrated framework using the AHP can help select a site for the quarry expansion project in Barbados.

Investigations at the former sites of raw phosphate processing in Germany

International Nuclear Information System (INIS)

Reichelt, Andreas; Weiss, Dietmar; Feige, Sebastian; Wiegand, Jens; Gerler, Juergen

2008-01-01

Raw phosphates have been processed in an industrial scale in Germany approximately since the middle of the 19th century. During the centuries, huge amounts of residues with high mass specific activities have been accumulated. Within the framework of a historical study, we have determined the accumulated radionuclide inventory from 1865 to 2005. The consumption amounts to approx. 150 million tons raw phosphates (corresponds to approx. 2.22*10 14 Bq U-238) with a fraction of national production of approx. 1 million tons. A production of approx. 3 million tons of elemental phosphorus (calcium silicate slag: 3.6*10 13 Bq Ra-226) and approx. 12 million tons of phosphoric acid (phosphogypsum: 2.7*10 13 Bq Ra-226) had been achieved. In the next step, we have looked for the former sites with legacies of the raw phosphate processing industry. 92 sites of former production of phosphate fertilizers, 3 sites of former production of elemental phosphorus and 10 sites of former production of phosphoric acid had been identified. Some of them were selected for more detailed researches regarding the accumulated radionuclide inventory and on-site/laboratory radiological investigations. (author)

Canada's Deep Geological Repository for Used Nuclear Fuel - Geo-scientific Site Evaluation Process - 13117

International Nuclear Information System (INIS)

Blyth, Alec; Ben Belfadhel, Mahrez; Hirschorn, Sarah; Hamilton, Duncan; McKelvie, Jennifer

2013-01-01

The Nuclear Waste Management Organization (NWMO) is responsible for implementing Adaptive Phased Management (APM), the approach selected by the Government of Canada for long-term management of used nuclear fuel generated by Canadian nuclear reactors. The ultimate objective of APM is the centralized containment and isolation of Canada's used nuclear fuel in a Deep Geological Repository in a suitable rock formation at a depth of approximately 500 meters (m) (1,640 feet [ft]). In May 2010, the NWMO published a nine-step site selection process that serves as the road map to decision-making on the location for the deep geological repository. The safety and appropriateness of any potential site will be assessed against a number of factors, both technical and social in nature. The selected site will be one that can be demonstrated to be able to safely contain and isolate used nuclear fuel, protecting humans and the environment over the very long term. The geo-scientific suitability of potential candidate sites will be assessed in a stepwise manner following a progressive and thorough site evaluation process that addresses a series of geo-scientific factors revolving around five safety functions. The geo-scientific site evaluation process includes: Initial Screenings; Preliminary Assessments; and Detailed Site Evaluations. As of November 2012, 22 communities have entered the site selection process (three in northern Saskatchewan and 18 in northwestern and southwestern Ontario). (authors)

Radiological audit of remedial action activities at the processing site, transfer site, and Cheney disposal site Grand Junction, Colorado: Audit date, August 9--11, 1993

International Nuclear Information System (INIS)

1993-08-01

The Uranium Mill Tailing Remedial Action (UMTRA) Project's Technical Assistance Contractor (TAC) performed a radiological audit of the Remedial Action Contractor (RAC), MK-Ferguson and CWM Federal Environmental Services, Inc., at the processing site, transfer site, and Cheney disposal site in Grand Junction, Colorado. Jim Hylko and Bill James of the TAC conducted this audit August 9 through 11, 1993. Bob Cornish and Frank Bosiljevec represented the US Department of Energy (DOE). This report presents one programmatic finding, eleven site-specific observations, one good practice, and four programmatic observations

Environmental assessment of remedial action at the Naturita uranium processing site near Naturita, Colorado

International Nuclear Information System (INIS)

1994-02-01

The proposed remedial action for the Naturita processing site is relocation of the contaminated materials and debris to the Dry Flats disposal site, 6 road miles (mi) [10 kilometers (km)] to the southeast. At the disposal site, the contaminated materials would be stabilized and covered with layers of earth and rock. The proposed disposal site is on land administered by the Bureau of Land Management (BLM) and used primarily for livestock grazing. The final disposal site would cover approximately 57 ac (23 ha), which would be permanently transferred from the BLM to the DOE and restricted from future uses. The remedial action activities would be conducted by the DOE's Uranium Mill Tailings Remedial Action (UMTRA) Project. The proposed remedial action would result in the loss of approximately 162 ac (66 ha) of soils at the processing and disposal sites; however, 133 ac (55 ha) of these soils at and adjacent to the processing site are contaminated and cannot be used for other purposes. If supplemental standards are approved by the NRC and state of Colorado, approximately 112 ac (45 ha) of contaminated soils adjacent to the processing site would not be cleaned up. This area is steeply sloped. The cleanup of this contamination would have adverse environmental consequences and would be potentially hazardous to remedial action workers. Another 220 ac (89 ha) of soils would be temporarily disturbed during the remedial action. The final disposal site would result in approximately 57 ac (23 ha) being removed from livestock grazing and wildlife use

Hydrogeologic characterization of the former Vitro processing site, Salt Lake City, Utah

International Nuclear Information System (INIS)

1993-01-01

During fiscal year (FY) 1992, the US Department of Energy received Congressional direction to investigate whether contamination from former processing activities is present in groundwater and soils at the former Vitro processing site in Salt Lake City, Utah. A total of $100,000 was appropriated for this activity. The surface of the Vitro site was cleaned up by the state of Utah under the Uranium Mill Tailings Remedial Action (UMTRA) Project during the mid- to late 1980s. The basis for the directive was the desire of the site owners, the Central Valley Water Reclamation Facility (CVWRF), to develop the site. This report, as well as the final Vitro Site Certification Report and the Clive Completion Report (both to be prepared and submitted by the state of Utah), will have to be reviewed and concurred with by the US Nuclear Regulatory Commission (NRC) prior to release of the Vitro site for restricted development. The groundwater and soil investigation was performed by the Technical Assistance Contractor (TAC) to the DOE UMTRA Project Office during FY92. The investigation at the Vitro site consisted of the installation of monitoring wells and soil borings, aquifer testing, and the collection and analyses of groundwater and soil samples. This report presents the results of this hydrogeologic investigation

Progress in centralised ethics review processes: Implications for multi-site health evaluations.

Science.gov (United States)

Prosser, Brenton; Davey, Rachel; Gibson, Diane

2015-04-01

Increasingly, public sector programmes respond to complex social problems that intersect specific fields and individual disciplines. Such responses result in multi-site initiatives that can span nations, jurisdictions, sectors and organisations. The rigorous evaluation of public sector programmes is now a baseline expectation. For evaluations of large and complex multi-site programme initiatives, the processes of ethics review can present a significant challenge. However in recent years, there have been new developments in centralised ethics review processes in many nations. This paper provides the case study of an evaluation of a national, inter-jurisdictional, cross-sector, aged care health initiative and its encounters with Australian centralised ethics review processes. Specifically, the paper considers progress against the key themes of a previous five-year, five nation study (Fitzgerald and Phillips, 2006), which found that centralised ethics review processes would save time, money and effort, as well as contribute to more equitable workloads for researchers and evaluators. The paper concludes with insights for those charged with refining centralised ethics review processes, as well as recommendations for future evaluators of complex multi-site programme initiatives. Copyright © 2015 Elsevier Ltd. All rights reserved.

The Need to Assess Public Values in a Site Selection Process

Energy Technology Data Exchange (ETDEWEB)

Sheng, Grant; Fortier, Michael [York Univ., Toronto, ON (Canada). Faculty of Environmental Studies; Collins, Alison [York Centre for Applied Sustainability, Toronto, ON (Canada)

2001-07-01

Siting a nuclear fuel waste disposal facility is highly problematic for both technical and nontechnical reasons. The majority of countries using nuclear energy and many in the scientific community favour burying the spent fuel deep in a stable geological formation. It is our contention that site selection of a disposal facility must consider social, political, spatial and scientific perspectives in a comprehensive and integrated fashion in order to achieve a successful process. Moreover, we submit that people's values must be explicitly recognized and be taken into account through a formalized process during deliberations on the disposal concept, the process of evaluation of the concept, and the site selection process. The purpose of this paper is: (1) to identify the importance of recognizing people's values in the process of determining 'public acceptability', (2) to outline a possible framework by which public acceptability can be gauged through a formalized process of value elicitation, and (3) to introduce a novel method by which a web-based geographic information systems (GIS) application can be used as a tool for value elicitation. In order to assess effectively the public acceptability of Canada's nuclear waste disposal concept, we submit that such a process must examine the underlying values that are held by the public. Moreover, the evaluation process of Canada's concept demonstrates that an acceptable process is a pre-condition for an acceptable result, although such a process does not necessarily guarantee an acceptable result. However, the consequences of a flawed process can be very significant, as shown by Canada's experience. This paper also provides a brief overview of a value elicitation process that, in our opinion, could be used to assess the public acceptability of the Concept. We also describe how a web-based GIS application could be used to infer some of the underlying values held by the public.

The site selection process for a spent fuel repository in Finland. Summary report

Energy Technology Data Exchange (ETDEWEB)

McEwen, T. [EnvirosQuantiSci (United Kingdom); Aeikaes, T. [Posiva Oy, Helsinki (Finland)

2000-12-01

This Summary Report describes the Finnish programme for the selection and characterisation of potential sites for the deep disposal of spent nuclear fuel and explains the process by which Olkiluoto has been selected as the single site proposed for the development of a spent fuel disposal facility. Its aim is to provide an overview of this process, initiated almost twenty years ago, which has entered its final phase. It provides information in three areas: a review of the early site selection criteria, a description of the site selection process, including all the associated site characterisation work, up to the point at which a single site was selected and an outline of the proposed work, in particular that proposed underground, to characterise further the Olkiluoto site. In 1983 the Finnish Government made a policy decision on the management of nuclear waste in which the main goals and milestones for the site selection programme for the deep disposal of spent fuel were presented. According to this decision several site candidates, whose selection was to be based on careful studies of the whole country, should be characterised and the site for the repository selected by the end of the year 2000. This report describes the process by which this policy decision has been achieved. The report begins with a discussion of the definition of the geological and environmental site selection criteria and how they were applied in order to select a small number of sites, five in all, that were to be the subject of the preliminary investigations. The methods used to investigate these sites and the results of these investigations are described, as is the evaluation of the results of these investigations and the process used to discard two of the sites and continue more detailed investigations at the remaining three. The detailed site investigations that commenced in 1993 are described with respect to the overall strategy followed and the investigation techniques applied. The

Development of site selection process for an LILW repository in Slovenia

International Nuclear Information System (INIS)

Zeleznik, N.; Kralj, M.; Mele, I.; Veselic, M.

2005-01-01

The activities regarding the LILW repository site selection in Slovenia are planned to meet the requirements of the Act on Ionising Radiation Protection and Nuclear Safety, especially the requirement that the site for a repository should be selected by 2008 and the repository should be in operation by 2013. In November 2004, the official administrative procedure for the siting of the repository started with the first spatial public conference on spatial planning procedure. It was carried out by the Ministry of the Environment and Spatial Planning and ARAO. Immediately after the conference the Program for the preparation of the detailed plan of national importance for the LILW repository was accepted by the Ministry. At the beginning of December 2004, ARAO invited all Slovenian local communities to participate in the site selection process and volunteer a site or area in their local community for further investigation. At the beginning of April 2005 the first phase of the bidding process was concluded. ARAO received applications from eight local communities. A pre-feasibility study to define three of the most promising locations was conducted because only three locations are foreseen by the Program for the preparation of the detailed plan of national importance. Methodologies were prepared for assessment of different parameters of technical, financial, environmental and spatial suitability as well as public acceptability. Comparative, preferential and also exclusion criteria for the respective parameters were defined. The results of the cabinet and fieldwork research were compared and further assessed in order to obtain maximum three local communities with three potential sites in which the probability of siting the LILW repository seems to be the highest. Detailed plans of national importance will be prepared for these sites. (author)

Idaho Chemical Processing Plant Site Development Plan

International Nuclear Information System (INIS)

Ferguson, F.G.

1994-02-01

The Idaho Chemical Processing Plant (ICPP) mission is to receive and store spent nuclear fuels and radioactive wastes for disposition for Department of Energy (DOE) in a cost-effective manner that protects the safety of Idaho National Engineering Laboratory (INEL) employees, the public, and the environment by: Developing advanced technologies to process spent nuclear fuel for permanent offsite disposition and to achieve waste minimization. Receiving and storing Navy and other DOE assigned spent nuclear fuels. Managing all wastes in compliance with applicable laws and regulations. Identifying and conducting site remediation consistent with facility transition activities. Seeking out and implementing private sector technology transfer and cooperative development agreements. Prior to April 1992, the ICPP mission included fuel reprocessing. With the recent phaseout of fuel reprocessing, some parts of the ICPP mission have changed. Others have remained the same or increased in scope

Process for selecting a site for Canada's deep geological repository for used nuclear fuel

International Nuclear Information System (INIS)

Facella, J.; Belfadhel, M.B.

2011-01-01

The Nuclear Waste Management Organization (NWMO) is responsible for implementing Adaptive Phased Management, the approach selected by the Government of Canada for long-term management of used nuclear fuel waste generated by Canadian nuclear reactors. The ultimate objective of Adaptive Phased Management is the centralized containment and isolation of Canada's used nuclear fuel in a Deep Geological Repository in a suitable crystalline or sedimentary rock formation at a depth of about 500m. The repository will consist of a series of access and service shafts and a series of tunnels leading to placement rooms where used fuel will be placed and sealed in competent rock using a multi-barrier system which includes long lived specially designed containers, sealing materials such as bentonite and the rock itself. The used fuel will be monitored throughout all phases of implementation and will also remain retrievable for an extended period of time. In May 2010, the NWMO published the site selection process that serves as the road map to decision-making on the location for the deep geological repository. NWMO initiated the process with a first stage that invites communities to learn more about the project and the site selection process. NWMO is actively building awareness of the project and, on request of communities, is delivering briefings, supporting community capacity building and undertaking high-level screenings of site suitability. The paper provides a brief description of: Adaptive Phased Management including the deep geological repository which is its ultimate goal, and the design of the site selection process, and importantly the approach to assessing the suitability of sites from both a social and technical perspective. The paper will outline how NWMO sought to develop a socially-acceptable site selection process as a firm foundation for future decisions on siting. Through a two-year collaborative process, NWMO sought to understand the expectations of

Remedial action plan and site design for stabilization of the inactive uranium processing site at Naturita, Colorado

International Nuclear Information System (INIS)

1994-03-01

The uranium processing site near Naturita, Colorado, is one of 24 inactive uranium mill sites designated to be cleaned up by the US Department of Energy (DOE) under the Uranium Mill Tailings Radiation Control Act of 1978 (UMTRCA), 42 USC section 7901 et seq. Part of the UMTRCA requires that the US Nuclear Regulatory Commission (NRC) concur with the DOE's remedial action plan (RAP) and certify that the remedial action conducted at the site complies with the standards promulgated by the US Environmental Protection Agency (EPA). Included in the RAP is this Remedial Action Selection Report (RAS), which describes the proposed remedial action for the Naturita site. An extensive amount of data and supporting information has been generated and evaluated for this remedial action. These data and supporting information are not incorporated into this single document but are included or referenced in the supporting documents. The RAP consists of this RAS and four supporting documents or attachments. This Attachment 2, Geology Report describes the details of geologic, geomorphic, and seismic conditions at the Dry Flats disposal site

Multi-discipline Waste Acceptance Process at the Nevada National Security Site - 13573

Energy Technology Data Exchange (ETDEWEB)

Carilli, Jhon T. [US Department Of Energy, Nevada Site Office, P. O. Box 98518, Las Vegas, Nevada 89193-8518 (United States); Krenzien, Susan K. [Navarro-Intera, LLC, P. O. Box 98952, Las Vegas, Nevada 89193-8952 (United States)

2013-07-01

The Nevada National Security Site low-level radioactive waste disposal facility acceptance process requires multiple disciplines to ensure the protection of workers, the public, and the environment. These disciplines, which include waste acceptance, nuclear criticality, safety, permitting, operations, and performance assessment, combine into the overall waste acceptance process to assess low-level radioactive waste streams for disposal at the Area 5 Radioactive Waste Management Site. Four waste streams recently highlighted the integration of these disciplines: the Oak Ridge Radioisotope Thermoelectric Generators and Consolidated Edison Uranium Solidification Project material, West Valley Melter, and classified waste. (authors)

Environmental assessment of remedial action at the Naturita Uranium processing site near Naturita, Colorado

International Nuclear Information System (INIS)

1994-01-01

The proposed remedial action for the Naturita processing site is relocation of the contaminated materials and debris to the Dry Flats disposal sits, 6 road miles (mi) [10 kilometers (km)) to the southeast. At the disposal site, the contaminated materials would be stabilized and covered with layers of earth and rock. The proposed disposal site is on land administered by the Bureau of Land Management (BLM) and used primarily for livestock grazing. The final disposal sits would cover approximately 57 ac (23 ha), which would be permanently transferred from the BLM to the DOE and restricted from future uses. The remedial action activities would be conducted by the DOE's Uranium Mill Tailings Remedial Action (UMTRA) Project. The proposed remedial action would result in the loss of approximately 162 ac (66 ha) of soils at the processing and disposal sites; however, 133 ac (55 ha) of these soils at and adjacent to the processing site are contaminated and cannot be used for other purposes. If supplemental standards are approved by the NRC and state of Colorado, approximately 112 ac (45 ha) of contaminated soils adjacent to the processing site would not be cleaned up. This area is steeply sloped. The cleanup of this contamination would have adverse environmental consequences and would be potentially hazardous to remedial action workers. Another 220 ac (89 ha) of soils would be temporarily disturbed during the remedial action. The final disposal site would result in approximately 57 ac (23 ha) being removed from livestock grazing and wildlife use

Environmental assessment of remedial action at the Naturita uranium processing site near Naturita, Colorado: Revision 5

Energy Technology Data Exchange (ETDEWEB)

1994-10-01

Title 1 of the Uranium Mill Tailings Radiation Control Act (UMTRCA) of 1978, Public Law (PL) 95-604, authorized the US Department of Energy (DOE) to perform remedial action at the inactive Naturita, Colorado, uranium processing site to reduce the potential health effects from the radioactive materials at the site and at vicinity properties associated with the site. Title 2 of the UMTRCA authorized the US Nuclear Regulatory Commission (NRC) or agreement state to regulate the operation and eventual reclamation of active uranium processing sites. The uranium mill tailings at the site were removed and reprocessed from 1977 to 1979. The contaminated areas include the former tailings area, the mill yard, the former ore storage area, and adjacent areas that were contaminated by uranium processing activities and wind and water erosion. The Naturita remedial action would result in the loss of 133 acres (ac) of contaminated soils at the processing site. If supplemental standards are approved by the NRC and the state of Colorado, approximately 112 ac of steeply sloped contaminated soils adjacent to the processing site would not be cleaned up. Cleanup of this contamination would have adverse environmental consequences and would be potentially hazardous to remedial action workers.

Environmental assessment of remedial action at the Naturita uranium processing site near Naturita, Colorado: Revision 5

International Nuclear Information System (INIS)

1994-10-01

Title 1 of the Uranium Mill Tailings Radiation Control Act (UMTRCA) of 1978, Public Law (PL) 95-604, authorized the US Department of Energy (DOE) to perform remedial action at the inactive Naturita, Colorado, uranium processing site to reduce the potential health effects from the radioactive materials at the site and at vicinity properties associated with the site. Title 2 of the UMTRCA authorized the US Nuclear Regulatory Commission (NRC) or agreement state to regulate the operation and eventual reclamation of active uranium processing sites. The uranium mill tailings at the site were removed and reprocessed from 1977 to 1979. The contaminated areas include the former tailings area, the mill yard, the former ore storage area, and adjacent areas that were contaminated by uranium processing activities and wind and water erosion. The Naturita remedial action would result in the loss of 133 acres (ac) of contaminated soils at the processing site. If supplemental standards are approved by the NRC and the state of Colorado, approximately 112 ac of steeply sloped contaminated soils adjacent to the processing site would not be cleaned up. Cleanup of this contamination would have adverse environmental consequences and would be potentially hazardous to remedial action workers

Plutonium production story at the Hanford site: processes and facilities history

Energy Technology Data Exchange (ETDEWEB)

Gerber, M.S., Westinghouse Hanford

1996-06-20

This document tells the history of the actual plutonium production process at the Hanford Site. It contains five major sections: Fuel Fabrication Processes, Irradiation of Nuclear Fuel, Spent Fuel Handling, Radiochemical Reprocessing of Irradiated Fuel, and Plutonium Finishing Operations. Within each section the story of the earliest operations is told, along with changes over time until the end of operations. Chemical and physical processes are described, along with the facilities where these processes were carried out. This document is a processes and facilities history. It does not deal with the waste products of plutonium production.

Process for selecting a site for Canada's deep geological repository for used nuclear fuel

International Nuclear Information System (INIS)

Facella, J.; Ben Belfadhel, M.; Patton, P.

2012-01-01

'Full Text:' The Nuclear Waste Management Organization (NWMO) is responsible for implementing Adaptive Phased Management, the approach selected by the Government of Canada for long-term management of used nuclear fuel waste generated by Canadian nuclear reactors. The ultimate objective of Adaptive Phased Management is the centralized containment and isolation of Canada's used nuclear fuel in a Deep Geological Repository in a suitable crystalline or sedimentary rock formation at a depth of about 500m. The repository will consist of a series of access and service shafts and a series of tunnels leading to placement rooms where used fuel will be placed and sealed in competent rock using a multi-barrier system which includes long lived specially designed containers, sealing materials such as bentonite and the rock itself. The used fuel will be monitored throughout all phases of implementation and will also remain retrievable for an extended period of time. In May 2010, the NWMO published the site selection process that serves as the road map to decision-making on the location for the deep geological repository. NWMO initiated the process with a first stage that invites communities to learn more about the project and the site selection process. NWMO is actively building awareness of the project and, on request of communities, is delivering briefings, supporting community capacity building and undertaking screenings of site suitability. This panel presentation provides a brief description of: Adaptive Phased Management including the deep geological repository which is its ultimate goal, and the design of the site selection process, and importantly the approach to assessing the suitability of sites from both a social and technical perspective. The panel presentation will be conducted in three parts: site selection process and engagement, Aboriginal engagement and Technical evaluations, followed by a discussion. The presentation will outline how NWMO sought

Temporal dynamics of biogeochemical processes at the Norman Landfill site

Science.gov (United States)

Arora, Bhavna; Mohanty, Binayak P.; McGuire, Jennifer T.; Cozzarelli, Isabelle M.

2013-01-01

The temporal variability observed in redox sensitive species in groundwater can be attributed to coupled hydrological, geochemical, and microbial processes. These controlling processes are typically nonstationary, and distributed across various time scales. Therefore, the purpose of this study is to investigate biogeochemical data sets from a municipal landfill site to identify the dominant modes of variation and determine the physical controls that become significant at different time scales. Data on hydraulic head, specific conductance, δ2H, chloride, sulfate, nitrate, and nonvolatile dissolved organic carbon were collected between 1998 and 2000 at three wells at the Norman Landfill site in Norman, OK. Wavelet analysis on this geochemical data set indicates that variations in concentrations of reactive and conservative solutes are strongly coupled to hydrologic variability (water table elevation and precipitation) at 8 month scales, and to individual eco-hydrogeologic framework (such as seasonality of vegetation, surface-groundwater dynamics) at 16 month scales. Apart from hydrologic variations, temporal variability in sulfate concentrations can be associated with different sources (FeS cycling, recharge events) and sinks (uptake by vegetation) depending on the well location and proximity to the leachate plume. Results suggest that nitrate concentrations show multiscale behavior across temporal scales for different well locations, and dominant variability in dissolved organic carbon for a closed municipal landfill can be larger than 2 years due to its decomposition and changing content. A conceptual framework that explains the variability in chemical concentrations at different time scales as a function of hydrologic processes, site-specific interactions, and/or coupled biogeochemical effects is also presented.

Completion report for the UMTRA project Vitro processing site, Salt Lake City, Utah

International Nuclear Information System (INIS)

1996-08-01

This completion report provides evidence that the final Salt Lake City, Utah, processing site property conditions are in accordance with the approval design and that all U.S. Environmental Protection Agency (EPA) standards have been satisfied. Included as appendixes to support the stated conclusions are the record drawings; a summary of grid test results; contract specifications and construction drawing and the EPA standards; the audit, inspection, and surveillance summary; the permit information; and project photographs. The principal objectives of remedial action at Salt Lake City were to remove the tailings from the former processing site, render the site free of contamination to EPA standards, and restore the site to the final design grade elevations. The final remedial action plan, which is approved by the U.S. Department of Energy and concurred upon by the U.S. Nuclear Regulator Commission and the state of Utah, contains the conceptual design used to develop the final approved design. During remedial action construction operations, conditions were encountered that required design features that differed form the conceptual design. These conditions and the associated design changes are noted in the record drawings. All remedial action activities were completed in conformance with the specifications and drawings. In the opinion of the state of Utah, the record drawings accurately reflect existing property conditions at the processing site

Natural attenuation processes in landfill leachate plumes at three Danish sites

DEFF Research Database (Denmark)

Bjerg, Poul Løgstrup; Tuxen, Nina; Reitzel, Lotte

2011-01-01

This article provides an overview of comprehensive core and fringe field studies at three Danish landfill sites. The goal of the research activities is to provide a holistic description of core and fringe attenuation processes for xenobiotic organic compounds in landfill leachate plumes. The appr......This article provides an overview of comprehensive core and fringe field studies at three Danish landfill sites. The goal of the research activities is to provide a holistic description of core and fringe attenuation processes for xenobiotic organic compounds in landfill leachate plumes....... The approach used is cross-disciplinary, encompassing integration of field-scale observations at different scales, field injection experiments, laboratory experiments, and reactive solute transport modeling. This is illustrated in examples from the most recently investigated site-the Sjoelund Landfill...... approaches and tools used in the application of MNA. In particular, the use of in situ indicators to document mass removal in landfill leachate plumes is emphasized. In this article, we advocate the application of conceptual and numerical models as tools for the integration of data and testing of hypotheses....

Site-specific investigations of aquifer thermal energy storage for space and process cooling

International Nuclear Information System (INIS)

Brown, D.R.

1991-01-01

This paper reports on the Pacific Northwest Laboratory (PNL) that has completed three preliminary site-specific feasibility studies that investigated aquifer thermal energy storage (ATES) for reducing space and process cooling costs. Chilled water stored in an ATES system could be used to meet all or part of the process and/or space cooling loads at the three facilities investigated. Seasonal or diurnal chill ATES systems could be significantly less expensive than a conventional electrically-driven, load-following chiller system at one of the three sites, depending on the cooling water loop return temperature and presumed future electricity escalation rate. For the other two sites investigated, a chill ATES system would be economically competitive with conventional chillers if onsite aquifer characteristics were improved. Well flow rates at one of the sites were adequate, but the expected thermal recovery efficiency was too low. The reverse of this situation was found at the other site, where the thermal recovery efficiency was expected to be adequate, but well flow rates were too low

[Study on the quantitative and qualitative composition of moulds colonizing sunflower seeds (Helianthus annus L.)].

Science.gov (United States)

Janda, Katarzyna; Wolska, Jolanta; Debia, Kamila

2015-01-01

The aim of study was to estimate the qualitative and quantitative composition of moulds colonizing sunflower seeds on RBCA, YpSs, DG18 media at 25, 37, and 45°C. Twenty samples of sunflower seeds (not roasted and not salted) were used for the analysis. The highest number of moulds were xerophilic species isolated on DG18 at 25°C (33), followed by mesophilic species (29) on RBCA medium at 25°C, and mesophilic (22) and thermophilic species (10) on YpSs medium at 37, and 45°C, respectively. Eurotium herbariorum was isolated from all samples. A total of 287 strains belonging to 52 mould species were isolated from sunflower seeds. The study revealed new species not previously isolated from sunflower seeds mycobiota.

Data Validation Package September 2016 Groundwater and Surface Water Sampling at the Slick Rock, Colorado, Processing Sites January 2017

Energy Technology Data Exchange (ETDEWEB)

Traub, David [Navarro Research and Engineering, Inc., Oak Ridge, TN (United States); Nguyen, Jason [US Department of Energy, Washington, DC (United States)

2017-01-04

The Slick Rock, Colorado, Processing Sites are referred to as the Slick Rock West Processing Site (SRK05) and the Slick Rock East Processing Site (SRK06). This annual event involved sampling both sites for a total of 16 monitoring wells and 6 surface water locations as required by the 2006 Draft Final Ground Water Compliance Action Plan for the Slick Rock, Colorado, Processing Sites (GCAP). A domestic well was also sampled at a property adjacent to the Slick Rock East site at the request of the landowner.

77 FR 38033 - Notice of Establishment of a Commodity Import Approval Process Web Site

Science.gov (United States)

2012-06-26

... post the draft risk assessment on the Web site for 30 days to give stakeholders an opportunity to... Process Web Site AGENCY: Animal and Plant Health Inspection Service, USDA. ACTION: Notice. SUMMARY: We are announcing the creation of a new Plant Protection and Quarantine Web site that will provide stakeholders with...

Environmental assessment of remedial action at the inactive uraniferous lignite processing sites at Belfield and Bowman, North Dakota

International Nuclear Information System (INIS)

Beranich, S.; Berger, N.; Bierley, D.; Bond, T.M.; Burt, C.; Caldwell, J.A.; Dery, V.A.; Dutcher, A.; Glover, W.A.; Heydenburg, R.J.; Larson, N.B.; Lindsey, G.; Longley, J.M.; Millard, J.B.; Miller, M.; Peel, R.C.; Persson-Reeves, C.H.; Titus, F.B.; Wagner, L.

1989-09-01

The Uranium Mill Tailings Radiation Control Act of 1978 (UMTRCA), to clean up the Belfield and Bowman, North Dakota, uraniferous lignite processing sites to reduce the potential health impacts associated with the residual radioactive materials remaining at these sites. Remedial action at these sites must be performed in accordance with the US Environmental Protection Agency's (EPA) standards promulgated for the remedial action and with the concurrence of the US Nuclear Regulatory Commission (NRC) and the state of North Dakota. The inactive Belfield uraniferous lignite processing site is one mile southeast of Belfield, North Dakota. The inactive Bowman uraniferous lignite processing site at the former town of Griffin, is seven miles northwest of Bowman, North Dakota and 65 road miles south of Belfield. Lignite ash from the processing operations has contaminated the soils over the entire 10.7-acre designated Belfield site and the entire 12.1-acre designated Bowman site. Dispersion of the ash has contaminated an additional 20.6 acres surrounding the Belfield processing site and an additional 59.2 acres surrounding the Bowman processing site. The proposed remedial action is to relocate the contaminated materials at the Belfield processing site to the Bowman processing/disposal site for codisposal with the Bowman contaminated soils. The environmental impacts assessed in this EA were evaluated for the proposed remedial action and the no action alternative and demonstrate that the proposed action would not significantly affect the quality of the human environment and would be performed in compliance with applicable environmental laws. The no action alternative would not be consistent with the intent of Public Law 95-604 and would not comply with the EPA standards. 48 refs., 10 figs., 7 tabs

Dynamic Disturbance Processes Create Dynamic Lek Site Selection in a Prairie Grouse.

Directory of Open Access Journals (Sweden)

Torre J Hovick

Full Text Available It is well understood that landscape processes can affect habitat selection patterns, movements, and species persistence. These selection patterns may be altered or even eliminated as a result of changes in disturbance regimes and a concomitant management focus on uniform, moderate disturbance across landscapes. To assess how restored landscape heterogeneity influences habitat selection patterns, we examined 21 years (1991, 1993-2012 of Greater Prairie-Chicken (Tympanuchus cupido lek location data in tallgrass prairie with restored fire and grazing processes. Our study took place at The Nature Conservancy's Tallgrass Prairie Preserve located at the southern extent of Flint Hills in northeastern Oklahoma. We specifically addressed stability of lek locations in the context of the fire-grazing interaction, and the environmental factors influencing lek locations. We found that lek locations were dynamic in a landscape with interacting fire and grazing. While previous conservation efforts have treated leks as stable with high site fidelity in static landscapes, a majority of lek locations in our study (i.e., 65% moved by nearly one kilometer on an annual basis in this dynamic setting. Lek sites were in elevated areas with low tree cover and low road density. Additionally, lek site selection was influenced by an interaction of fire and patch edge, indicating that in recently burned patches, leks were located near patch edges. These results suggest that dynamic and interactive processes such as fire and grazing that restore heterogeneity to grasslands do influence habitat selection patterns in prairie grouse, a phenomenon that is likely to apply throughout the Greater Prairie-Chicken's distribution when dynamic processes are restored. As conservation moves toward restoring dynamic historic disturbance patterns, it will be important that siting and planning of anthropogenic structures (e.g., wind energy, oil and gas and management plans not view lek

Use of strategic environmental assessment in the site selection process for a radioactive waste disposal facility in Slovenia.

Science.gov (United States)

Dermol, Urška; Kontić, Branko

2011-01-01

The benefits of strategic environmental considerations in the process of siting a repository for low- and intermediate-level radioactive waste (LILW) are presented. The benefits have been explored by analyzing differences between the two site selection processes. One is a so-called official site selection process, which is implemented by the Agency for radwaste management (ARAO); the other is an optimization process suggested by experts working in the area of environmental impact assessment (EIA) and land-use (spatial) planning. The criteria on which the comparison of the results of the two site selection processes has been based are spatial organization, environmental impact, safety in terms of potential exposure of the population to radioactivity released from the repository, and feasibility of the repository from the technical, financial/economic and social point of view (the latter relates to consent by the local community for siting the repository). The site selection processes have been compared with the support of the decision expert system named DEX. The results of the comparison indicate that the sites selected by ARAO meet fewer suitability criteria than those identified by applying strategic environmental considerations in the framework of the optimization process. This result stands when taking into account spatial, environmental, safety and technical feasibility points of view. Acceptability of a site by a local community could not have been tested, since the formal site selection process has not yet been concluded; this remains as an uncertain and open point of the comparison. Copyright © 2010 Elsevier Ltd. All rights reserved.

Remedial action plan and site design for stabilization of the inactive uranium processing site at Naturita, Colorado

International Nuclear Information System (INIS)

1993-08-01

The US Environmental Protection Agency (EPA) has established health and environmental protection regulations to correct and prevent groundwater contamination resulting from processing activities at inactive uranium milling sites (40 CFR 192). The Uranium Mill Tailings Radiation Control Act (UMTRCA) of 1978 designated responsibility to the US Department of Energy (DOE) for assessing the inactive uranium milling sites. The DOE has determined that each assessment shall include information on site characterization, a description of the proposed action, and a summary of the water resources protection strategy that describes how the proposed action will comply with the EPA groundwater protection standards. To achieve compliance with the proposed US Environmental Protection Agency (EPA) groundwater protection standards, the US Department of Energy (DOE) proposes that supplemental standards be applied at the Dry Flats disposal site because of Class III (limited use) groundwater in the uppermost aquifer (the basal sandstone of the Cretaceous Burro Canyon Formation) based on low yield. The proposed remedial action will ensure protection of human health and the environment

A Systematic Study of Site-specific GalNAc-type O-Glycosylation Modulating Proprotein Convertase Processing

DEFF Research Database (Denmark)

Schjoldager, Katrine Ter-Borch Gram; Vester-Christensen, Malene B.; Goth, Christoffer K.

2011-01-01

Site-specific GalNAc-type O-glycosylation is emerging as an important co-regulator of proprotein convertase (PC) processing of proteins. PC processing is crucial in regulating many fundamental biological pathways and O-glycans in or immediately adjacent to processing sites may affect recognition...... and function of PCs. Thus, we previously demonstrated that deficiency in site-specific O-glycosylation in a PC site of the fibroblast growth factor, FGF23, resulted in marked reduction in secretion of active unprocessed FGF23, which cause familial tumoral calcinosis and hyperostosis hyperphosphatemia. GalNAc......-type O-glycosylation is found on serine and threonine amino acids and up to 20 distinct polypeptide GalNAc transferases catalyze the first addition of GalNAc to proteins making this step the most complex and differentially regulated steps in protein glycosylation. There is no reliable prediction model...

Poly(A)-tag deep sequencing data processing to extract poly(A) sites.

Science.gov (United States)

Wu, Xiaohui; Ji, Guoli; Li, Qingshun Quinn

2015-01-01

Polyadenylation [poly(A)] is an essential posttranscriptional processing step in the maturation of eukaryotic mRNA. The advent of next-generation sequencing (NGS) technology has offered feasible means to generate large-scale data and new opportunities for intensive study of polyadenylation, particularly deep sequencing of the transcriptome targeting the junction of 3'-UTR and the poly(A) tail of the transcript. To take advantage of this unprecedented amount of data, we present an automated workflow to identify polyadenylation sites by integrating NGS data cleaning, processing, mapping, normalizing, and clustering. In this pipeline, a series of Perl scripts are seamlessly integrated to iteratively map the single- or paired-end sequences to the reference genome. After mapping, the poly(A) tags (PATs) at the same genome coordinate are grouped into one cleavage site, and the internal priming artifacts removed. Then the ambiguous region is introduced to parse the genome annotation for cleavage site clustering. Finally, cleavage sites within a close range of 24 nucleotides and from different samples can be clustered into poly(A) clusters. This procedure could be used to identify thousands of reliable poly(A) clusters from millions of NGS sequences in different tissues or treatments.

Universality and the astrophysical sites for the r-process

International Nuclear Information System (INIS)

Otsuki, Kaori; Mathews, Grant J.; Wilson, James; Kajino, Toshitaka; Aoki, Wako; Honda, Satoshi

2003-01-01

Several observations of r-process elements in metal-deficient halo stars have been reported which show a Z>56 formed abundance distribution pattern similar to the Solar-system r-process distribution. It was believed that r-process elements for Z>56 in the same ratio and their astrophysical origin is unique because of this. However, quite recently, several controversial observational results have been reported. We calculated nucleosynthesis in various environments using a dynamical code. We find it is possible to reproduce the observed universal abundance distribution for stable Z>56 elements in various environments. Our results do not support a unique astrophysical site for Z>56 elements. These results significantly affect nuclear chronology using actinide elements. We also introduce a recent r-process nucleosynthesis calculation based on a supernovae simulation. Our tentative results indicate over-production of lighter elements and a shortage of actinide elements. (author)

HOW DO STUDENTS SELECT SOCIAL NETWORKING SITES? AN ANALYTIC HIERARCHY PROCESS (AHP MODEL

Directory of Open Access Journals (Sweden)

Chun Meng Tang

2015-12-01

Full Text Available Social networking sites are popular among university students, and students today are indeed spoiled for choice. New emerging social networking sites sprout up amid popular sites, while some existing ones die out. Given the choice of so many social networking sites, how do students decide which one they will sign up for and stay on as an active user? The answer to this question is of interest to social networking site designers and marketers. The market of social networking sites is highly competitive. To maintain the current user base and continue to attract new users, how should social networking sites design their sites? Marketers spend a fairly large percent of their marketing budget on social media marketing. To formulate an effective social media strategy, how much do marketers understand the users of social networking sites? Learning from website evaluation studies, this study intends to provide some answers to these questions by examining how university students decide between two popular social networking sites, Facebook and Twitter. We first developed an analytic hierarchy process (AHP model of four main selection criteria and 12 sub-criteria, and then administered a questionnaire to a group of university students attending a course at a Malaysian university. AHP analyses of the responses from 12 respondents provided an insight into the decision-making process involved in students’ selection of social networking sites. It seemed that of the four main criteria, privacy was the top concern, followed by functionality, usability, and content. The sub-criteria that were of key concern to the students were apps, revenue-generating opportunities, ease of use, and information security. Between Facebook and Twitter, the students thought that Facebook was the better choice. This information is useful for social networking site designers to design sites that are more relevant to their users’ needs, and for marketers to craft more effective

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

International Nuclear Information System (INIS)

1982-11-01

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

Japan's Siting Process for the Geological Disposal of High-level Radioactive Waste - An International Peer Review

International Nuclear Information System (INIS)

Brassinnes, Stephane; Fabbri, Olivier; Rubenstone, James; Seppaelae, Timo; Siemann, Michael; ); Kwong, Gloria; )

2016-01-01

The Nuclear Energy Agency carried out an independent peer review of Japan's siting process and criteria for the geological disposal of high-level radioactive waste in May 2016. The review concluded that Japan's site screening process is generally in accordance with international practices. As the goal of the siting process is to locate a site - that is both appropriate and accepted by the community - to host a geological disposal facility for high-level radioactive waste, the international review team emphasises in this report the importance of maintaining an open dialogue and interaction between the regulator, the implementer and the public. Dialogue should begin in the early phases and continue throughout the siting process. The international review team also underlines the importance of taking into account feasibility aspects when selecting a site for preliminary investigations, but suggests that it would be inappropriate to set detailed scientific criteria for nationwide screening at this stage. The team has provided extensive advisory remarks in the report as opportunities for improvement, including the recommendation to use clear and consistent terminology in defining the site screening criteria as it is a critical factor in a successful siting process. (authors)

Environmental assessment of remedial action at the Naturita uranium processing site near Naturita, Colorado. Revision 3

Energy Technology Data Exchange (ETDEWEB)

1994-02-01

The proposed remedial action for the Naturita processing site is relocation of the contaminated materials and debris to the Dry Flats disposal site, 6 road miles (mi) [10 kilometers (km)] to the southeast. At the disposal site, the contaminated materials would be stabilized and covered with layers of earth and rock. The proposed disposal site is on land administered by the Bureau of Land Management (BLM) and used primarily for livestock grazing. The final disposal site would cover approximately 57 ac (23 ha), which would be permanently transferred from the BLM to the DOE and restricted from future uses. The remedial action activities would be conducted by the DOE`s Uranium Mill Tailings Remedial Action (UMTRA) Project. The proposed remedial action would result in the loss of approximately 162 ac (66 ha) of soils at the processing and disposal sites; however, 133 ac (55 ha) of these soils at and adjacent to the processing site are contaminated and cannot be used for other purposes. If supplemental standards are approved by the NRC and state of Colorado, approximately 112 ac (45 ha) of contaminated soils adjacent to the processing site would not be cleaned up. This area is steeply sloped. The cleanup of this contamination would have adverse environmental consequences and would be potentially hazardous to remedial action workers. Another 220 ac (89 ha) of soils would be temporarily disturbed during the remedial action. The final disposal site would result in approximately 57 ac (23 ha) being removed from livestock grazing and wildlife use.

Site contractor participation in the DOE SWEIS process at Los Alamos, New Mexico

Energy Technology Data Exchange (ETDEWEB)

Pendergrass, A.; Garvey, D.

1997-12-01

The U.S. Department of Energy (DOE) prepares site-wide environmental impact statements (SWEIS) on sites that are to remain in operation in order to provide an estimate of the cumulative environmental impacts from projected future operations at the site. DOE has relied on outside contractors rather than the site management and operating (M&O) contractors to prepare EISs, in order to preclude the potential for conflict of interest. The site M&O contractors, who know the potential for conflict of interest. The site M&O contractors, who know the site best and are most familiar with existing information, are critical support for the contractor. The University of California (UC) is the site M&O contractor for Los Alamos National Laboratory (LANL) in Los Alamos, NM. The role of LANL (UC) personnel in DOE`s preparation process for the LANL SWEIS is described. 3 refs.

Canada's Deep Geological Repository for Used Nuclear Fuel - Geo-scientific Site Evaluation Process - 13117

Energy Technology Data Exchange (ETDEWEB)

Blyth, Alec; Ben Belfadhel, Mahrez; Hirschorn, Sarah; Hamilton, Duncan; McKelvie, Jennifer [Nuclear Waste Management Organization, 22 St. Clair Avenue East, Toronto, Ontario M4T 2S3 (Canada)

2013-07-01

The Nuclear Waste Management Organization (NWMO) is responsible for implementing Adaptive Phased Management (APM), the approach selected by the Government of Canada for long-term management of used nuclear fuel generated by Canadian nuclear reactors. The ultimate objective of APM is the centralized containment and isolation of Canada's used nuclear fuel in a Deep Geological Repository in a suitable rock formation at a depth of approximately 500 meters (m) (1,640 feet [ft]). In May 2010, the NWMO published a nine-step site selection process that serves as the road map to decision-making on the location for the deep geological repository. The safety and appropriateness of any potential site will be assessed against a number of factors, both technical and social in nature. The selected site will be one that can be demonstrated to be able to safely contain and isolate used nuclear fuel, protecting humans and the environment over the very long term. The geo-scientific suitability of potential candidate sites will be assessed in a stepwise manner following a progressive and thorough site evaluation process that addresses a series of geo-scientific factors revolving around five safety functions. The geo-scientific site evaluation process includes: Initial Screenings; Preliminary Assessments; and Detailed Site Evaluations. As of November 2012, 22 communities have entered the site selection process (three in northern Saskatchewan and 18 in northwestern and southwestern Ontario). (authors)

THE COLD AND DARK PROCESS AT THE SAVANNAH RIVER SITE

International Nuclear Information System (INIS)

Gilmour, J; William Austin, W; Cathy Sizemore, C

2007-01-01

The deactivation and decommissioning (D and D) of a facility exposes D and D workers to numerous hazards. One of the more serious hazards is coming into contact to hazardous energy sources (e.g. electrical, pressurized steam). At the Savannah River Site (SRS) a formal process for identifying and eliminating sources of hazardous energy was developed and is called ''Cold and Dark''. Several ''near miss'' events involving cutting of energized conductors during D and D work in buildings thought to be isolated identified the need to have a formal process to identify and isolate these potentially hazardous systems. This process was developed using lessons learned from D and D activities at the Rocky Flats Environmental Technology Site (Rocky Flats) in Colorado. The Cold and Dark process defines an isolation boundary (usually a building perimeter) and then systematically identifies all of the penetrations through this boundary. All penetrations that involve hazardous energy sources are then physically air-gapped. The final product is a documented declaration of isolation performed by a team involving operations, engineering, and project management. Once the Cold and Dark declaration is made for a building work can proceed without the usual controls used in an operational facility (e.g. lockout/tagout, arc flash PPE). It is important to note that the Cold and Dark process does not remove all hazards from a facility. Work planning and controls still need to address hazards that can be present from such things as chemicals, radiological contamination, residual liquids, etc., as well as standard industrial hazards

Autonomous cloud based site monitoring through hydro geophysical data assimilation, processing and result delivery

Science.gov (United States)

Versteeg, R.; Johnson, D. V.; Rodzianko, A.; Zhou, H.; Dafflon, B.; Leger, E.; de Kleine, M.

2017-12-01

Understanding of processes in the shallow subsurface requires that geophysical, biogeochemical, hydrological and remote sensing datasets are assimilated, processed and interpreted. Multiple enabling software capabilities for process understanding have been developed by the science community. These include information models (ODM2), reactive transport modeling (PFLOTRAN, Modflow, CLM, Landlab), geophysical inversion (E4D, BERT), parameter estimation (PEST, DAKOTA), visualization (ViSiT, Paraview, D3, QGIS) as well as numerous tools written in python and R for petrophysical mapping, stochastic modeling, data analysis and so on. These capabilities use data collected using sensors and analytical tools developed by multiple manufacturers which produce many different measurements. While scientists obviously leverage tools, capabilities and lessons learned from one site at other sites, the current approach to site characterization and monitoring is very labor intensive and does not scale well. Our objective is to be able to monitor many (hundreds - thousands) of sites. This requires that monitoring can be done in a near time, affordable, auditable and essentially autonomous manner. For this we have developed a modular vertically integrated cloud based software framework which was designed from the ground up for effective site and process monitoring. This software framework (PAF - Predictive Assimilation Framework) is multitenant software and provides automation of data ingestion, processing and visualization of hydrological, geochemical and geophysical (ERT/DTS) data. The core organizational element of PAF is a project/user one in which capabilities available to users are controlled by a combination of available data and access permissions. All PAF capabilities are exposed through APIs, making it easy to quickly add new components. PAF is fully integrated with newly developed autonomous electrical geophysical hardware and thus allows for automation of electrical

A voice from the high wire: Public involvement in a co-operative siting process

International Nuclear Information System (INIS)

Oates, D.J.L.

1995-01-01

The author is a public consultation and communications consultant to the Siting Task Force (STF), Low level Radioactive Waste Management. The STF is a Canadian government-appointed yet independent body implementing a voluntary, co-operative siting process for a long term storage or disposal facility for 1 million cubic metres of LLRW. The presentation will document the experiences of and lessons learned by the author during her role developing and implementing a public involvement program for the process. The Co-operative Siting Process is a new approach to siting controversial facilities. It is based on the belief that communities should accept such a facility in their backyard and not be forced against their will on technical or political grounds. A formal 'ground rules-up-front' process was developed and is now being carried out, with completion slated for April, 1995. Putting these rules and theories into practice has resulted in significant changes being made to the work plan for technical activities, and in a sober second look at the intricacies involved in planning and carrying out a thorough and efficient public involvement program that remain practical and cost-effective. There is a delicate balancing act between meaningful public participation that lays the foundation for trust, confidence and consensus, and public involvement that can result in the process being side-tracked and legitimate solutions and technical activities becoming mired in political and personal agendas

Exploring the feasibility of multi-site flow cytometric processing of gut associated lymphoid tissue with centralized data analysis for multi-site clinical trials.

Directory of Open Access Journals (Sweden)

Ian McGowan

Full Text Available The purpose of this study was to determine whether the development of a standardized approach to the collection of intestinal tissue from healthy volunteers, isolation of gut associated lymphoid tissue mucosal mononuclear cells (MMC, and characterization of mucosal T cell phenotypes by flow cytometry was sufficient to minimize differences in the normative ranges of flow parameters generated at two trial sites. Forty healthy male study participants were enrolled in Pittsburgh and Los Angeles. MMC were isolated from rectal biopsies using the same biopsy acquisition and enzymatic digestion protocols. As an additional comparator, peripheral blood mononuclear cells (PBMC were collected from the study participants. For quality control, cryopreserved PBMC from a single donor were supplied to both sites from a central repository (qPBMC. Using a jointly optimized standard operating procedure, cells were isolated from tissue and blood and stained with monoclonal antibodies targeted to T cell phenotypic markers. Site-specific flow data were analyzed by an independent center which analyzed all data from both sites. Ranges for frequencies for overall CD4+ and CD8+ T cells, derived from the qPBMC samples, were equivalent at both UCLA and MWRI. However, there were significant differences across sites for the majority of T cell activation and memory subsets in qPBMC as well as PBMC and MMC. Standardized protocols to collect, stain, and analyze MMC and PBMC, including centralized analysis, can reduce but not exclude variability in reporting flow data within multi-site studies. Based on these data, centralized processing, flow cytometry, and analysis of samples may provide more robust data across multi-site studies. Centralized processing requires either shipping of fresh samples or cryopreservation and the decision to perform centralized versus site processing needs to take into account the drawbacks and restrictions associated with each method.

Exploring the feasibility of multi-site flow cytometric processing of gut associated lymphoid tissue with centralized data analysis for multi-site clinical trials.

Science.gov (United States)

McGowan, Ian; Anton, Peter A; Elliott, Julie; Cranston, Ross D; Duffill, Kathryn; Althouse, Andrew D; Hawkins, Kevin L; De Rosa, Stephen C

2015-01-01

The purpose of this study was to determine whether the development of a standardized approach to the collection of intestinal tissue from healthy volunteers, isolation of gut associated lymphoid tissue mucosal mononuclear cells (MMC), and characterization of mucosal T cell phenotypes by flow cytometry was sufficient to minimize differences in the normative ranges of flow parameters generated at two trial sites. Forty healthy male study participants were enrolled in Pittsburgh and Los Angeles. MMC were isolated from rectal biopsies using the same biopsy acquisition and enzymatic digestion protocols. As an additional comparator, peripheral blood mononuclear cells (PBMC) were collected from the study participants. For quality control, cryopreserved PBMC from a single donor were supplied to both sites from a central repository (qPBMC). Using a jointly optimized standard operating procedure, cells were isolated from tissue and blood and stained with monoclonal antibodies targeted to T cell phenotypic markers. Site-specific flow data were analyzed by an independent center which analyzed all data from both sites. Ranges for frequencies for overall CD4+ and CD8+ T cells, derived from the qPBMC samples, were equivalent at both UCLA and MWRI. However, there were significant differences across sites for the majority of T cell activation and memory subsets in qPBMC as well as PBMC and MMC. Standardized protocols to collect, stain, and analyze MMC and PBMC, including centralized analysis, can reduce but not exclude variability in reporting flow data within multi-site studies. Based on these data, centralized processing, flow cytometry, and analysis of samples may provide more robust data across multi-site studies. Centralized processing requires either shipping of fresh samples or cryopreservation and the decision to perform centralized versus site processing needs to take into account the drawbacks and restrictions associated with each method.

Model of the best-of-N nest-site selection process in honeybees

Science.gov (United States)

Reina, Andreagiovanni; Marshall, James A. R.; Trianni, Vito; Bose, Thomas

2017-05-01

The ability of a honeybee swarm to select the best nest site plays a fundamental role in determining the future colony's fitness. To date, the nest-site selection process has mostly been modeled and theoretically analyzed for the case of binary decisions. However, when the number of alternative nests is larger than two, the decision-process dynamics qualitatively change. In this work, we extend previous analyses of a value-sensitive decision-making mechanism to a decision process among N nests. First, we present the decision-making dynamics in the symmetric case of N equal-quality nests. Then, we generalize our findings to a best-of-N decision scenario with one superior nest and N -1 inferior nests, previously studied empirically in bees and ants. Whereas previous binary models highlighted the crucial role of inhibitory stop-signaling, the key parameter in our new analysis is the relative time invested by swarm members in individual discovery and in signaling behaviors. Our new analysis reveals conflicting pressures on this ratio in symmetric and best-of-N decisions, which could be solved through a time-dependent signaling strategy. Additionally, our analysis suggests how ecological factors determining the density of suitable nest sites may have led to selective pressures for an optimal stable signaling ratio.

Sustainable Approach for Landfill Management at Final Processing Site Cikundul in Sukabumi City, Indonesia

OpenAIRE

Sri Darwati

2012-01-01

The main problem of landfill management in Indonesia is the difficulty in getting a location for Final Processing Sites (FPS) due to limited land and high land prices. Besides, about 95% of existing landfills are uncontrolled dumping sites, which could potentially lead to water, soil and air pollution. Based on data from the Ministry of Environment (2010), The Act of the Republic of Indonesia Number 18 Year 2008 Concerning Solid Waste Management, prohibits open dumping at final processing sit...

Final audit report of remedial action construction at the UMTRA Project, Grand Junction, Colorado, processing site

International Nuclear Information System (INIS)

1995-02-01

This final audit report (FAR) for remedial action at the Grand Junction, Colorado, Uranium Mill Tailings Remedial Action (UMTRA) Project processing site consists of a summary of the radiological surveillances/ audits, the quality assurance (QA) in-process surveillances, and the QA final close-out inspection performed by the US Department of Energy (DOE) and Technical Assistance Contractor (TAC). The FAR also summarizes other surveillances performed by the US Nuclear Regulatory Commission (NRC). To summarize, a total of one finding and 127 observations were noted during DOE/TAC audit and surveillance activities. The NRC noted general site-related observations during the OSCRs. Follow-up to responses required from MK-Ferguson for the DOE/TAC finding and observations indicated that all issues related to the Grand Junction processing site were resolved and closed out to the DOE's satisfaction. The NRC OSCRs resulted in no issues related to the Grand Junction processing site requiring a response from MK-Ferguson

Two citizen task forces and the challenge of the evolving nuclear waste siting process

International Nuclear Information System (INIS)

Peelle, E.B.

1990-01-01

Siting any nuclear waste facility is problematic in today's climate of distrust toward nuclear agencies and fear of nuclear waste. This study compares and contrasts the siting and public participation processes as two citizen task forces dealt with their difficult responsibilities. 10 refs., 3 tabs

Environmental assessment of remedial action at the Naturita Uranium Processing Site near Naturita, Colorado

International Nuclear Information System (INIS)

1994-05-01

The Uranium Mill Tailings Radiation Control Act (UMTRCA) of 1978, Public Law (PL) 95-604, authorized the US Department of Energy (DOE) to perform remedial action at the Naturita, Colorado, uranium processing site to reduce the potential health effects from the radioactive materials at the site and at vicinity properties associated with the site. The US Environmental Protection Agency (EPA) promulgated standards for the UMTRCA that contain measures to control the contaminated materials and to protect groundwater quality. Remedial action at the Naturita site must be performed in accordance with these standards and with the concurrence of the US Nuclear Regulatory Commission (NRC) and the state of Colorado. The proposed remedial action for the Naturita processing site is relocation of the contaminated materials and debris to either the Dry Flats disposal site, 6 road miles (mi) [10 kilometers (km)] to the southeast, or a licensed non-DOE disposal facility capable of handling RRM. At either disposal site, the contaminated materials would be stabilized and covered with layers of earth and rock. The proposed Dry Flats disposal site is on land administered by the Bureau of Land Management (BLM) and used primarily for livestock grazing. The final disposal site would cover approximately 57 ac (23 ha), which would be permanently transferred from the BLM to the DOE and restricted from future uses. The remedial action would be conducted by the DOE's Uranium Mill Tailings Remedial Action (UMTRA) Project. This report discusses environmental impacts associated with the proposed remedial action

Process Description for the Retrieval of Earth Covered Transuranic (TRU) Waste Containers at the Hanford Site

International Nuclear Information System (INIS)

DEROSA, D.C.

2000-01-01

This document describes process and operational options for retrieval of the contact-handled suspect transuranic waste drums currently stored below grade in earth-covered trenches at the Hanford Site. Retrieval processes and options discussed include excavation, container retrieval, venting, non-destructive assay, criticality avoidance, incidental waste handling, site preparation, equipment, and shipping

Process Description for the Retrieval of Earth Covered Transuranic (TRU) Waste Containers at the Hanford Site

Energy Technology Data Exchange (ETDEWEB)

DEROSA, D.C.

2000-01-13

This document describes process and operational options for retrieval of the contact-handled suspect transuranic waste drums currently stored below grade in earth-covered trenches at the Hanford Site. Retrieval processes and options discussed include excavation, container retrieval, venting, non-destructive assay, criticality avoidance, incidental waste handling, site preparation, equipment, and shipping.

The chert quarrying and processing industry at the Piatra Tomii site, Romania

Directory of Open Access Journals (Sweden)

Otis Norman Crandell

2015-03-01

Full Text Available Fieldwalking surveys in 2007 and 2008 revealed a moderate sized settlement on Piatra Tomii Hill (Alba County, Romania which was considered of interest because of its location on top of a natural source of chert, and the large amount of chert artefacts found on the surface. In 2009 the site was excavated during which one of the objectives was to learn more about the chert mining and processing at the site. The ratio of artefact types and lack of use-wear suggests that not only was raw material being extracted at the site, but tools were also being produced locally before being exported. The 2009 excavations also revealed what appear to be the remains of pit quarrying and possibly fire cracked limestone and debris. These finds provide technical insight into potential chert extraction techniques utilised in the Late Chalcolithic and Early Bronze Age. As well, this is as yet the only reported settlement in the Transylvanian basin involved in chert extraction (either quarrying or mining. Given the settlement’s affluence, especially considering its relative isolation, it is likely that the chert industry here was important to communities in the vicinity. Indeed artefacts found at contemporary sites in the Mureș Valley appear to have been made from the same or a similar chert. This paper gives an introductions to the site, describes the artefacts and features found there and provides possible interpretations  regarding the processing and export industry, as well as the methods of extracting the raw material during this period.

Hanford Site Treated Effluent Disposal Facility process flow sheet

International Nuclear Information System (INIS)

Bendixsen, R.B.

1993-04-01

This report presents a novel method of using precipitation, destruction and recycle factors to prepare a process flow sheet. The 300 Area Treated Effluent Disposal Facility (TEDF) will treat process sewer waste water from the 300 Area of the Hanford Site, located near Richland, Washington, and discharge a permittable effluent flow into the Columbia River. When completed and operating, the TEDF effluent water flow will meet or exceed water quality standards for the 300 Area process sewer effluents. A preliminary safety analysis document (PSAD), a preconstruction requirement, needed a process flow sheet detailing the concentrations of radionuclides, inorganics and organics throughout the process, including the effluents, and providing estimates of stream flow quantities, activities, composition, and properties (i.e. temperature, pressure, specific gravity, pH and heat transfer rates). As the facility begins to operate, data from process samples can be used to provide better estimates of the factors, the factors can be entered into the flow sheet and the flow sheet will estimate more accurate steady state concentrations for the components. This report shows how the factors were developed and how they were used in developing a flow sheet to estimate component concentrations for the process flows. The report concludes with how TEDF sample data can improve the ability of the flow sheet to accurately predict concentrations of components in the process

Environmental assessment of remedial action at the Naturita Uranium processing site near Naturita, Colorado. Revision 2

Energy Technology Data Exchange (ETDEWEB)

1994-01-01

The proposed remedial action for the Naturita processing site is relocation of the contaminated materials and debris to the Dry Flats disposal sits, 6 road miles (mi) [10 kilometers (km)) to the southeast. At the disposal site, the contaminated materials would be stabilized and covered with layers of earth and rock. The proposed disposal site is on land administered by the Bureau of Land Management (BLM) and used primarily for livestock grazing. The final disposal sits would cover approximately 57 ac (23 ha), which would be permanently transferred from the BLM to the DOE and restricted from future uses. The remedial action activities would be conducted by the DOE`s Uranium Mill Tailings Remedial Action (UMTRA) Project. The proposed remedial action would result in the loss of approximately 162 ac (66 ha) of soils at the processing and disposal sites; however, 133 ac (55 ha) of these soils at and adjacent to the processing site are contaminated and cannot be used for other purposes. If supplemental standards are approved by the NRC and state of Colorado, approximately 112 ac (45 ha) of contaminated soils adjacent to the processing site would not be cleaned up. This area is steeply sloped. The cleanup of this contamination would have adverse environmental consequences and would be potentially hazardous to remedial action workers. Another 220 ac (89 ha) of soils would be temporarily disturbed during the remedial action. The final disposal site would result in approximately 57 ac (23 ha) being removed from livestock grazing and wildlife use.

Description of a Multipurpose Processing and Storage Complex for the Hanford Site's radioactive material

International Nuclear Information System (INIS)

Nyman, D.H.; Wolfe, B.A.; Hoertkorn, T.R.

1993-05-01

The mission of the US Department of Energy's (DOE) Hanford Site has changed from defense nuclear materials production to that of waste management/disposal and environmental restoration. ne Multipurpose Processing and Storage Complex (MPSC) is being designed to process discarded waste tank internal hardware contaminated with mixed wastes, failed melters from the vitrification plant, and other Hanford Site high-level solid waste. The MPSC also will provide interim storage of other radioactive materials (irradiated fuel, canisters of vitrified high-level waste [HLW], special nuclear material [SNM], and other designated radioactive materials)

ANALYSIS OF REMEDIATION PROCESS OF THE GROUDWATER COTAMINATION IN AN ILLEGAL DUMPING SITE

Science.gov (United States)

Nishida, Norikazu; Furuichi, Toru; Ishii, Kazuei

Among on-site remediation technologies applied to illegal dumping sites, a technology to remedy contaminated groundwater without removal of the dumped waste is expected to provide a great opportunity to fulfill a societal need due to its economic advantage compared to removal of all waste. However heterogeneously-distributed waste makes the remedial process difficult. In this study, an in situflushing technology was applied to an illegal dumping site in Kuwana city, Mie, in order to remedy groundwater contaminated with several volatile organic compounds (VOCs) within five years. The key to successfully achieve the target was to conduct a series of advanced remediation processes; introducing a new indicator by which multiple VOCs can be estimated integratelly, monitoring the progress of remediation with a contour map of VOC concentration as well as the weighted averages of the concentration derived from the indicator, pinpointing residual contaminants area, reexamining the plan, and taking additional steps that promote further remediation.

Hydrology and Oceanography Analysis Regarding The NPP Site Screening Process at Banten Province

International Nuclear Information System (INIS)

Yarianto-S-Budi-Susilo

2007-01-01

Regarding the NPP development in the future, it is needed to make inventory of potential site in the Java Island as well as in the outside Java Island. The NPP site inventory availability is to answer the energy demand challenge. Site screening process should be performed in accordance with the IAEA safety standard regarding the site selection, investigating several aspects related to the NPP safety (exclusion, safety and suitability factor) in the large area to obtain potential site candidates. For the site survey stage of hydrology and oceanography aspects, the analysis are more focused on the tidal phenomena along the north coastline, bathymetry, water resource, and hydrology system in the Banten Province. The method used are secondary data collection, field confirmation and internet searching. The result of the study showed that Tanjung Pujut and Tanjung Pasir are suitable based on the bathymetry and water intake facility consideration. Meanwhile Tanjung Kait and Tanjung Pasir more suitable considering tsunami aspects that may be generated by Krakatau Volcano. (author)

A complete remediation process for a uranium-contaminated site and application to other sites

International Nuclear Information System (INIS)

Mason, C.F.V.; Lu, N.; Kitten, H.D.; Williams, M.; Turney, W.R.J.R.

1998-01-01

During the summer of 1996 the authors were able to test, at the pilot scale, the concept of leaching uranium (U) from contaminated soils. The results of this pilot scale operation showed that the system they previously had developed at the laboratory scale is applicable at the pilot scale. The paper discusses these results, together with laboratory scale results using soil from the Fernald Environmental Management Project (FEMP), Ohio. These FEMP results show how, with suitable adaptations, the process is widely applicable to other sites. The purpose of this paper is to describe results that demonstrate remediation of uranium-contaminated soils may be accomplished through a leach scheme using sodium bicarbonate

A complete remediation process for a uranium-contaminated site and application to other sites

Energy Technology Data Exchange (ETDEWEB)

Mason, C.F.V.; Lu, N.; Kitten, H.D.; Williams, M.; Turney, W.R.J.R.

1998-12-31

During the summer of 1996 the authors were able to test, at the pilot scale, the concept of leaching uranium (U) from contaminated soils. The results of this pilot scale operation showed that the system they previously had developed at the laboratory scale is applicable at the pilot scale. The paper discusses these results, together with laboratory scale results using soil from the Fernald Environmental Management Project (FEMP), Ohio. These FEMP results show how, with suitable adaptations, the process is widely applicable to other sites. The purpose of this paper is to describe results that demonstrate remediation of uranium-contaminated soils may be accomplished through a leach scheme using sodium bicarbonate.

Problems of developing remedial strategy for the uranium ore processing legacy site Pridneprovsky Chemical Plant site (Dneprodzerginsk, Ukraine)

International Nuclear Information System (INIS)

Riazantsev, V.; Bugai, D.; Skalskyy, A.; Tkachenko, E.

2014-01-01

In this paper we present results of works and studies carried out in the frame of ongoing national and international projects aimed at developing the remedial strategy for the Soviet era legacy uranium production site Pridneprovsky Chemical Plant, Dneprodzerginsk, Ukraine. The site includes several uranium mill tailings, contaminated buildings, ore storage grounds and other contaminated facilities. Taking into account the necessity to implement provisions of the new IAEA standards (Radiation Protection and Safety of Radiation Sources: International Basic Safety Standards, No. GSR Part 3 (Interim) and others) as well as the provisions of the ICRP 103 publication, the State Nuclear Regulatory Inspectorate Ukraine developed the draft of the new licensing requirements for activities of uranium ores processing.

Lessons learned from the Siting Process of an Interim Storage Facility in Spain - 12024

Energy Technology Data Exchange (ETDEWEB)

Lamolla, Meritxell Martell [MERIENCE Strategic Thinking, 08734 Olerdola, Barcelona (Spain)

2012-07-01

On 29 December 2009, the Spanish government launched a site selection process to host a centralised interim storage facility for spent fuel and high-level radioactive waste. It was an unprecedented call for voluntarism among Spanish municipalities to site a controversial facility. Two nuclear municipalities, amongst a total of thirteen municipalities from five different regions, presented their candidatures to host the facility in their territories. For two years the government did not make a decision. Only in November 30, 2011, the new government elected on 20 November 2011 officially selected a non-nuclear municipality, Villar de Canas, for hosting this facility. This paper focuses on analysing the factors facilitating and hindering the siting of controversial facilities, in particular the interim storage facility in Spain. It demonstrates that involving all stakeholders in the decision-making process should not be underestimated. In the case of Spain, all regional governments where there were candidate municipalities willing to host the centralised interim storage facility, publicly opposed to the siting of the facility. (author)

Technical database and management system (DBMS) for the UMTRA project processing sites

International Nuclear Information System (INIS)

Hillman, R.L.; Mohr, D.E.

1985-01-01

The technical DBMS is a structured and organized method for collecting, storing, retrieving, and analyzing technical data based upon standard operating procedures and quality control measures. The automated environment created by this design exists both as a repository for processing site technical data and the analysis techniques used against this data for site characterization, evaluation, and design. The system is composed of diverse technical subjects that are collectively used to address remedial action problems associated with mill tailings disposal. These technical subjects include hydrology, geology, geochemistry, radiology, and engineering

Buffer, backfill and closure process report for the safety assessment SR-Site

International Nuclear Information System (INIS)

Sellin, Patrik

2010-11-01

This report gives an account of how processes in buffer, deposition tunnel backfill and the closure important for the long-term evolution of a KBS-3 repository for spent nuclear fuel, will be documented in the safety assessment SR-Site

Buffer, backfill and closure process report for the safety assessment SR-Site

Energy Technology Data Exchange (ETDEWEB)

Sellin, Patrik (ed.)

2010-11-15

This report gives an account of how processes in buffer, deposition tunnel backfill and the closure important for the long-term evolution of a KBS-3 repository for spent nuclear fuel, will be documented in the safety assessment SR-Site

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

International Nuclear Information System (INIS)

1993-01-01

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

Evaluation of regulatory processes affecting nuclear power plant early site approval and standardization

International Nuclear Information System (INIS)

1983-12-01

This report presents the results of a survey and evaluation of existing federal, state and local regulatory considerations affecting siting approval of power plants in the United States. Those factors that may impede early site approval of nuclear power plants are identified, and findings related to the removal of these impediments and the general improvement of the approval process are presented. A brief evaluation of standardization of nuclear plant design is also presented

Protein carbonylation sites in bovine raw milk and processed milk products.

Science.gov (United States)

Milkovska-Stamenova, Sanja; Mnatsakanyan, Ruzanna; Hoffmann, Ralf

2017-08-15

During thermal treatment of milk, proteins are oxidized, which may reduce the nutritional value of milk, abolish protein functions supporting human health, especially important for newborns, and yield potentially harmful products. The side chains of several amino acids can be oxidized to reactive carbonyls, which are often used to monitor oxidative stress in organisms. Here we mapped protein carbonylation sites in raw milk and different brands of pasteurized, ultra high temperature (UHT) treated milk, and infant formulas (IFs) after digesting the precipitated proteins with trypsin. Reactive carbonyls were derivatized with O-(biotinylcarbazoylmethyl)hydroxylamine to enrich the modified peptides by avidin-biotin affinity chromatography and analyze them by nanoRP-UPLC-ESI-MS. Overall, 53 unique carbonylated peptides (37 carbonylation sites, 15 proteins) were identified. Most carbonyls were derived from dicarbonyls (mainly glyoxal). The number of carbonylation sites increased with the harsher processing from raw milk (4) to pasteurized (16) and UHT milk (16) and to IF (24). Copyright © 2017 Elsevier Ltd. All rights reserved.

Accident simulation in a chemical process facility at the Savannah River Site

International Nuclear Information System (INIS)

Hope, E.P.

1993-01-01

The US Department of Energy requires Westinghouse Savannah River Company to safely operate the chemical separations facilities at the Savannah River Site (SRS). As part of the safety analysis program, simulation of a proposed frame waste recovery (FWR) system is needed to determine the possible accident consequences that may affect public safety. This paper details the simulation process for the proposed frame waste recovery process and describes the analytical tools used in order to make estimates of accident consequences. Since the process in question has been operated, historical data and statistics about its operation are available. Software tools have been developed to allow analysis of the frame waste recovery system, including the generation of system specific dose conversion factors for a number of unique situations. Accident scenarios involving spilled liquid material are analyzed and account for the specific floor geometry of the facility. Confinement and filtration systems are considered. Analysis of source terms is a limiting factor which affects the entire evaluation process. In the past, facility source terms were generally constant with occasional variations from established patterns. As new site missions unfold, significant variations in source terms can be expected. The impact of these variations on the safety analysis is discussed

Processing Tritiated Water at the Savannah River Site: A Production-Scale Demonstration of a palladium membrane reactor

International Nuclear Information System (INIS)

Sessions, K

2004-01-01

The Palladium Membrane Reactor (PMR) process was installed in the Tritium Facilities at the Savannah River Site to perform a production-scale demonstration for the recovery of tritium from tritiated water adsorbed on molecular sieve (zeolite). Unlike the current recovery process that utilizes magnesium, the PMR offers a means to process tritiated water in a more cost effective and environmentally friendly manner. The design and installation of the large-scale PMR process was part of a collaborative effort between the Savannah River Site and Los Alamos National Laboratory. The PMR process operated at the Savannah River Site between May 2001 and April 2003. During the initial phase of operation the PMR processed thirty-four kilograms of tritiated water from the Princeton Plasma Physics Laboratory. The water was processed in fifteen separate batches to yield approximately 34,400 liters (STP) of hydrogen isotopes. Each batch consisted of round-the-clock operations for approximately nine days. In April 2003 the reactor's palladium-silver membrane ruptured resulting in the shutdown of the PMR process. Reactor performance, process performance and operating experiences have been evaluated and documented. A performance comparison between PMR and current magnesium process is also documented

New emissions targeting strategy for site utility of process industries

International Nuclear Information System (INIS)

Manesh, Mohamamd Hasan Khoshgoftar; Amidpour, Majid; Hamedi, Mohammad Hosein; Abadi, Sajad Khamis; Ghalami, Hooman

2013-01-01

A new procedure for environmental targeting of co-generation system is presented. The proposed method is based on the concepts of pinch technology for total site targeting of fuel, power, steam, environmental impacts and total annualized cost with considering emissions taxes. This approach provides a consistent, general procedure for determining mass flow rates and efficiencies of the applied turbines. This algorithm utilizes the relationship of entropy with enthalpy and isentropic efficiency. Also, the life cycle assessment (LCA) as a well-known tool for analyzing environmental impacts on a wide perspective with reference to a product system and the related environmental and economic impacts have been applied. In this regard, a damage-oriented impact analysis method based on Eco-indicator 99 and footprints analysis was considered. In addition, the present work demonstrates the effect of including both sensible and latent heating of steam in the extended Site Utility Grand Composite Curve (ESUGCC). It is shown that including sensible heating allows for better thermal matching between the processes. Furthermore, the other representation YSUGCC as the other form of Site Utility Grand Composite has been proposed. Two case studies were used to illustrate the usefulness of the new environmental targeting method

Community dynamics in the siting process for a low to intermediate level nuclear waste facility in Kincardine, Ontario

International Nuclear Information System (INIS)

Al-Haydari, D.

2007-01-01

The use of nuclear technology to generate electricity inevitably produces waste that is detrimental to the environment and human health. Finding communities that will accept nuclear waste disposal facilities is extremely challenging. Furthermore, the siting of a nuclear waste disposal facility is more than a technological analysis, but a matter that includes a variety of social, ethical and political considerations. This study is aimed to assess the role of the place-based community, communities of interest and communities of identity involved in the voluntary siting process for a low to intermediate level nuclear waste disposal facility in Ontario. To accomplish this, a framework was developed and applied though a case study evaluation of the siting process for the Deep Geologic Repository in Kincardine, Ontario. The framework highlights four key procedural principles that were used to analyze the siting process: trust, public participation, equity and risk. The data revealed that the positions of the communities involved in the siting process varied depending on the meaningful fulfillment the four key procedural principles. (author)

Bayesian site selection for fast Gaussian process regression

KAUST Repository

Pourhabib, Arash; Liang, Faming; Ding, Yu

2014-01-01

Gaussian Process (GP) regression is a popular method in the field of machine learning and computer experiment designs; however, its ability to handle large data sets is hindered by the computational difficulty in inverting a large covariance matrix. Likelihood approximation methods were developed as a fast GP approximation, thereby reducing the computation cost of GP regression by utilizing a much smaller set of unobserved latent variables called pseudo points. This article reports a further improvement to the likelihood approximation methods by simultaneously deciding both the number and locations of the pseudo points. The proposed approach is a Bayesian site selection method where both the number and locations of the pseudo inputs are parameters in the model, and the Bayesian model is solved using a reversible jump Markov chain Monte Carlo technique. Through a number of simulated and real data sets, it is demonstrated that with appropriate priors chosen, the Bayesian site selection method can produce a good balance between computation time and prediction accuracy: it is fast enough to handle large data sets that a full GP is unable to handle, and it improves, quite often remarkably, the prediction accuracy, compared with the existing likelihood approximations. © 2014 Taylor and Francis Group, LLC.

Bayesian site selection for fast Gaussian process regression

KAUST Repository

Pourhabib, Arash

2014-02-05

Gaussian Process (GP) regression is a popular method in the field of machine learning and computer experiment designs; however, its ability to handle large data sets is hindered by the computational difficulty in inverting a large covariance matrix. Likelihood approximation methods were developed as a fast GP approximation, thereby reducing the computation cost of GP regression by utilizing a much smaller set of unobserved latent variables called pseudo points. This article reports a further improvement to the likelihood approximation methods by simultaneously deciding both the number and locations of the pseudo points. The proposed approach is a Bayesian site selection method where both the number and locations of the pseudo inputs are parameters in the model, and the Bayesian model is solved using a reversible jump Markov chain Monte Carlo technique. Through a number of simulated and real data sets, it is demonstrated that with appropriate priors chosen, the Bayesian site selection method can produce a good balance between computation time and prediction accuracy: it is fast enough to handle large data sets that a full GP is unable to handle, and it improves, quite often remarkably, the prediction accuracy, compared with the existing likelihood approximations. © 2014 Taylor and Francis Group, LLC.

Data Validation Package - April and July 2015 Groundwater and Surface Water Sampling at the Gunnison, Colorado, Processing Site

Energy Technology Data Exchange (ETDEWEB)

Linard, Joshua [Dept. of Energy (DOE), Washington, DC (United States). Office of Legacy Management; Campbell, Sam [Navarro Research and Engineering, Inc., Oak Ridge, TN (United States)

2016-02-01

This event included annual sampling of groundwater and surface water locations at the Gunnison, Colorado, Processing Site. Sampling and analyses were conducted as specified in Sampling and Analysis Plan for U.S. Department of Energy Office of Legacy Management Sites. Samples were collected from 28 monitoring wells, three domestic wells, and six surface locations in April at the processing site as specified in the 2010 Ground Water Compliance Action Plan for the Gunnison, Colorado, Processing Site. Domestic wells 0476 and 0477 were sampled in July because the homes were unoccupied in April, and the wells were not in use. Duplicate samples were collected from locations 0113, 0248, and 0477. One equipment blank was collected during this sampling event. Water levels were measured at all monitoring wells that were sampled. No issues were identified during the data validation process that requires additional action or follow-up.

Operational Implementation of the MARSSIM Process at the Wayne Interim Storage Site

International Nuclear Information System (INIS)

Hays, D. C. Jr.; Trujillo, P. A. IV.; Zoller, S. G.

2002-01-01

This paper describes the methodologies behind the operational implementation of the Multi Agency Radiation Site Survey and Investigation Manual (MARSSIM) process at the Wayne Interim Storage Site (WISS). The United States Army Corps of Engineers (USACE) and Environmental Chemical Corporation (ECC) have implemented the MARSSIM process using various surveys producing raw data. The final remedial status of a survey unit is derived through data reduction, while maintaining a high degree of efficiency in the construction aspects of the remedial action. Data reduction of field measurements is accomplished by merging the data outputs of a Digital Global Positioning System, an exposure rate meter, and laboratory analyses to produce maps which present exposure rates, elevations, survey unit boundaries, direct measurement locations, and sampling locations on a single map. The map serves as a data-posting plot and allows the project team to easily judge the survey unit's remedial status. The operational implementation of the MARSSIM process has been successful in determining the eligibility of survey units for final status surveys at the WISS and also in demonstrating final status radiological and chemical conditions while maintaining an efficient remedial action effort

Report of ground water monitoring for expansion of the golf course, Salt Lake City, Utah, vitro processing site

International Nuclear Information System (INIS)

1995-06-01

To determine the potential impacts of the proposed golf course expansion on the south side of the Vitro site, ground water data from the UMTRA Vitro processing site were evaluated in response to the U.S. Department of Energy (DOE) Uranium Mill Tailings Remedial Action (UMTRA) Project Office request. Golf in the Round, Inc., has proposed an expansion of the present driving range to include a 9-hole golf course on the UMTRA Vitro processing site, which is owned by the Central Valley Water Reclamation Facility (CVWRF). An expanded golf course would increase irrigation and increase the amount of water that could infiltrate the soil, recharging the unconfined aquifer. Increased water levels in the aquifer could alter the ground water flow regime; contaminants in the shallow ground water could then migrate off the site or discharge to surface water in the area. Dewatering of the unconfined aquifer on CVWRF property could also impact site contaminant migration; a significant amount of ground water extraction at CVWRF could reduce the amount of contaminant migration off the site. Since 1978, data have been collected at the site to determine the distribution of tailings materials (removed from the site from 1985 to 1987) and to characterize the presence and migration of contaminants in sediments, soils, surface water, and ground water at the former Vitro processing site. Available data suggest that irrigating an expanded golf course may cause contamination to spread more rapidly within the unconfined aquifer. The public is not at risk from current Vitro processing site activities, nor is risk expected due to golf course expansion. However, ecological risk could increase with increased surface water contamination and the development of ground water seeps

Actinide solution processing at the Rocky Flats Environmental Technology Site

International Nuclear Information System (INIS)

1995-04-01

The Department of Energy (DOE) has prepared an Environmental Assessment (EA), DOE/EA-1039, for radioactive solution removal and processing at Rocky Flats Environmental Technology Site, Golden, Colorado. The proposal for solution removal and processing is in response to independent safety assessments and an agreement with the State of Colorado to remove mixed residues at Rocky Flats and reduce the risk of future accidents. Monthly public meetings were held during the scoping and preparation of the EA. The scope of the EA included evaluations of alternative methods and locations of solution processing. A comment period from February 20, 1995 through March 21, 1995 was provided to the public and the State of Colorado to offer written comment on the EA. Comments were received from the State of Colorado and the U.S. Environmental Protection Agency. A response to the agency comments is included in the Final EA

Processing of tetraphenylborate precipitates in the Savannah River Site Defense Waste Processing Facility

International Nuclear Information System (INIS)

Eibling, R.E.

1990-01-01

The Savannah River Site has generated 77 million gallons of high level radioactive waste since the early 1950's. By 1987, evaporation had reduced the concentration of the waste inventory to 35 million gallons. Currently, the wastes reside in large underground tanks as a soluble fraction stored, crystallized salts, and an insoluble fraction, sludge, which consists of hydrated transition metal oxides. The bulk of the radionuclides, 67 percent, are in the sludge while the crystallized salts and supernate are composed of the nitrates, nitrites, sulfates and hydroxides of sodium, potassium, and cesium. The principal radionuclide in the soluble waste is 137 Cs with traces of 90 Sr. The transformation of the high level wastes into a borosilicate glass suitable for permanent disposal is the goal of the Defense Waste Processing Facility (DWPF). To minimize the volume of glass produced, the soluble fraction of the waste is treated with sodium tetraphenylborate and sodium titanate in the waste tanks to precipitate the radioactive cesium ion and absorb the radioactive strontium ion. The precipitate is washed in the waste tanks and is then pumped to the DWPF. The precipitate, as received, is incompatible with the vitrification process because of the high aromatic carbon content and requires further chemical treatment. Within the DWPF, the precipitate is processed in the Salt Processing Cell to remove the aromatic carbon as benzene. The precipitate hydrolysis process hydrolyzes the tetraphenylborate anion to produce borate anion and benzene. The benzene is removed by distillation, decontaminated and transferred out of the DWPF for disposal

Rehabilitation of the Mary Kathleen uranium mining and processing site

International Nuclear Information System (INIS)

Ward, T.A.

1985-09-01

A detailed plan for the rehabilitation of the Mary Kathleen mining and processing site was developed prior to the closure of operations in late 1982. The plan was based on three basic principles of: making all areas safe for public access; removing all structures which could deteriorate and become unsightly or unsafe with time; and encouraging natural revegetation on erosion resistant surfaces. The aim was to leave the site in a safe and satisfactory condition, consistent with future land use in the area, requiring no foreseeable ongoing maintenance and a minimum of precautionary monitoring. When the programme has been completed, the only constraint on future land use will be the need to control building construction in the tailings/ evaporation, dumps and mine areas as a precaution against possible exposure to radon daughters. Appropriate radiation and water quality monitoring programmes were incorporated in the plan

European sites contaminated by residues from the ore extracting and processing industries

International Nuclear Information System (INIS)

Vandenhove, H.

2000-01-01

Activities linked with the ore extraction and processing industries may lead to enhanced levels of naturally occurring radionuclides (NORs) in products, by-products and waste and at the installations and in the surroundings of the facility. In the framework of the EC-DGXI CARE project (Common Approach for REstoration of contaminated sites) nine important categories of industries were identified and discussions were summarized on the industrial processes and the levels of NORs in parent material, waste and by-products. The most contaminating industries are uranium mining and milling, metal mining and smelting and the phosphate industry. Radionuclide levels in products and/or waste products from the oil and gas extraction industry and of the rare earth, zirconium and ceramics industries may be particularly elevated, but waste streams are limited. The impact on the public from coal mining and power production from coal is commonly considered low. No typical values are available for contaminant levels in materials, buildings and surroundings of radium extraction and luminizing plants, nor for thorium extraction and processing plants. An attempt to give an overview of sites in Europe contaminated with NORs, with emphasis on past practices, was only partly successful since information was often limited or unavailable. The most prominent case of environmental contamination due to mining and processing activities (uranium, metal and coal mining) is in eastern Germany. (author)

High-level waste processing at the Savannah River Site: An update

International Nuclear Information System (INIS)

Marra, J.E.; Bennett, W.M.; Elder, H.H.; Lee, E.D.; Marra, S.L.; Rutland, P.L.

1997-01-01

The Defense Waste Processing Facility (DWPF) at the Savannah River Site (SRS) in Aiken, SC mg began immobilizing high-level radioactive waste in borosilicate glass in 1996. Currently, the radioactive glass is being produced as a ''sludge-only'' composition by combining washed high-level waste sludge with glass frit. The glass is poured in stainless steel canisters which will eventually be disposed of in a permanent, geological repository. To date, DWPF has produced about 100 canisters of vitrified waste. Future processing operations will, be based on a ''coupled'' feed of washed high-level waste sludge, precipitated cesium, and glass frit. This paper provides an update of the processing activities completed to date, operational/flowsheet problems encountered, and programs underway to increase production rates

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

Energy Technology Data Exchange (ETDEWEB)

1993-03-24

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

10 CFR Appendix III to Part 960 - Application of the System and Technical Guidelines During the Siting Process

Science.gov (United States)

2010-01-01

... 960—Application of the System and Technical Guidelines During the Siting Process 1. This appendix... 10 Energy 4 2010-01-01 2010-01-01 false Application of the System and Technical Guidelines During the Siting Process III Appendix III to Part 960 Energy DEPARTMENT OF ENERGY GENERAL GUIDELINES FOR THE...

Effect of self-deflection on a totally asymmetric simple exclusion process with functions of site assignments

Science.gov (United States)

Tsuzuki, Satori; Yanagisawa, Daichi; Nishinari, Katsuhiro

2018-04-01

This study proposes a model of a totally asymmetric simple exclusion process on a single-channel lane with functions of site assignments along the pit lane. The system model attempts to insert a new particle to the leftmost site at a certain probability by randomly selecting one of the empty sites in the pit lane, and reserving it for the particle. Thereafter, the particle is directed to stop at the site only once during its travel. Recently, the system was determined to show a self-deflection effect, in which the site usage distribution biases spontaneously toward the leftmost site, and the throughput becomes maximum when the site usage distribution is slightly biased to the rightmost site. Our exact analysis describes this deflection effect and show a good agreement with simulations.

Generation, on-site storage; handling and processing of industrial waste of Tehran

International Nuclear Information System (INIS)

Abduli, M.A.

1997-01-01

This paper describes out the present status of generation, on-site handling, processing and storage of industrial waste in Tehran. In this investigation, 67 large scale factories of different industrial groups were randomly selected. Above cited functional elements of these factories were surveyed. In this investigation a close contact with each factory was required, thus a questionnaire was prepared and distributed among these factories. The relationship between daily weight of the industrial waste (Y) and number of employer of each factory (x) is found to be Y=547.4 + 0.58 x. The relationship between daily volume of industrial waste (V), and daily weight of waste generated in each factory (Y) can be described by V=1.56 + 0.00078 Y. About 68% of the factories have their own interim storage site and the rest of the factories do not possess any on-site storage facility

Asymmetric exclusion processes with site sharing in a one-channel transport system

International Nuclear Information System (INIS)

Liu Mingzhe; Hawick, Ken; Marsland, Stephen

2010-01-01

This Letter investigates two-species totally asymmetric simple exclusion process (TASEP) with site sharing in a one-channel transport system. In the model, different species of particles may share the same sites, while particles of the same species may not (hard-core exclusion). The site-sharing mechanism is applied to the bulk as well as the boundaries. Such sharing mechanism within the framework of the TASEP has been largely ignored so far. The steady-state phase diagrams, currents and bulk densities are obtained using a mean-field approximation and computer simulations. The presence of three stationary phases (low-density, high-density, and maximal current) are identified. A comparison on the stationary current with the Bridge model [M.R. Evans, et al., Phys. Rev. Lett. 74 (1995) 208] has shown that our model can enhance the current. The theoretical calculations are well supported by Monte Carlo simulations.

Multicriteria decision analysis based on analytic hierarchy process in GIS environment for siting nuclear power plant in Egypt

International Nuclear Information System (INIS)

Abudeif, A.M.; Abdel Moneim, A.A.; Farrag, A.F.

2015-01-01

Highlights: • The binary overlay method was used in Phase I through OR operator for selecting the candidate areas. • The WLC and AHP methods was used to screen and select the potential sites (phase II) in Arc GIS 10.1 software. • In phase III, four sites, all located on the North western coast and Red Sea, of highest scores were chosen as Candidate sites after eliminating the lowest score sites. • The AHP method was applied to select preferred candidate site and calculating the eigenvectors in Expert Choice Software Package. - Abstract: Due to increasing demand of electrical energy and freshwater in Egypt, it is safe to assume that the decision makers will turn to nuclear power as the feasible alternative for energy. However, as time goes by, fewer sites will be available and suitable for nuclear power plant development. Site selection is a key phase of the siting process of a nuclear plant and may significantly affect the safety and cost of the facility during its entire life cycle. The siting of nuclear power plants is one of multi-criteria problems, which makes it complex. Many interrelated factors affect the process. Six constraints and twenty-two factors corresponding to safety, environment and socio-economy were considered in the siting study presented in this paper. Multi-Criteria Decision Analysis was applied during the selection of nuclear power plants site using GIS software. Three spatial decision making models were applied in this paper during site selection stage. The binary overlay (Boolean logic) with Low Risk approach in which the logical OR operator is used to determine the candidate areas. All constraints were represented in binary maps, combined and a masking layer was created to eliminate the lands considered as constraints in Arc GIS Software. The 22 factors were represented in normalized maps after unifying all of them to 0–1 score scales based on the philosophy of suitability criteria (factors) using the Weighted Linear Combination

GenBank blastx search result: AK104780 [KOME

Lifescience Database Archive (English)

Full Text Available AK104780 001-039-C06 AY026914.1 Pseudomonas putida strain P111 czrBA operon, partial sequence; ben operon... and ant operon, complete sequence; and catRBCA operon, partial sequence; and unknown gene.|BCT BCT 3e-11 +2 ...

GenBank blastx search result: AK287557 [KOME

Lifescience Database Archive (English)

Full Text Available AK287557 J065021C17 AY026914.1 AY026914 Pseudomonas putida strain P111 czrBA operon..., partial sequence; ben operon and ant operon, complete sequence; and catRBCA operon, partial sequence; and unknown gene. BCT 0.0 0 ...

GenBank blastx search result: AK109330 [KOME

Lifescience Database Archive (English)

Full Text Available AK109330 006-201-C10 AY026914.1 Pseudomonas putida strain P111 czrBA operon, partial sequence; ben operon... and ant operon, complete sequence; and catRBCA operon, partial sequence; and unknown gene.|BCT BCT 3e-11 +2 ...

GenBank blastx search result: AK289020 [KOME

Lifescience Database Archive (English)

Full Text Available AK289020 J090090F09 AY026914.1 AY026914 Pseudomonas putida strain P111 czrBA operon..., partial sequence; ben operon and ant operon, complete sequence; and catRBCA operon, partial sequence; and unknown gene. BCT 0.0 0 ...

Resolving public conflict in site selection process - a risk communication approach

International Nuclear Information System (INIS)

Ishizaka, Kaoru; Tanaka, Masaru

2003-01-01

In Japan, conflicts regarding the siting of waste disposal facilities occur frequently. In particular, siting of incinerators and landfills has become increasingly difficult because the public is highly concerned about the dioxin issues. Inefficient siting of waste disposal facilities causes several social problems, such as the shortage of waste treatment and disposal facilities, the rising of waste management costs and an increase in the consumption of resources. While dealing with a similar situation, the Chemical Society of Japan adopted a risk communication technique successfully. Hence, the pragmatic use of a risk communication technique is proposed to avoid conflicts and for a smooth information exchange to seek cooperation in waste management. In order to achieve this, a study was conducted to resolve conflicts between residents and the municipality for the selection of site for a solid waste treatment and disposal facility. This study aims to discuss the subject of risk communication for the waste disposal system in Japan. This study is performed through personal interviews and a questionnaire covering opposing parties in the town. As a result of the survey, a risk communication approach for a waste treatment and disposal system is presented in the paper addressing issues such as building of social trust, pragmatic use of the communication process, installation of credible information sources, and environmental education and awareness

Environmental assessment of remedial action at the Naturita Uranium Processing Site near Naturita, Colorado. Revision 4

Energy Technology Data Exchange (ETDEWEB)

1994-05-01

The Uranium Mill Tailings Radiation Control Act (UMTRCA) of 1978, Public Law (PL) 95-604, authorized the US Department of Energy (DOE) to perform remedial action at the Naturita, Colorado, uranium processing site to reduce the potential health effects from the radioactive materials at the site and at vicinity properties associated with the site. The US Environmental Protection Agency (EPA) promulgated standards for the UMTRCA that contain measures to control the contaminated materials and to protect groundwater quality. Remedial action at the Naturita site must be performed in accordance with these standards and with the concurrence of the US Nuclear Regulatory Commission (NRC) and the state of Colorado. The proposed remedial action for the Naturita processing site is relocation of the contaminated materials and debris to either the Dry Flats disposal site, 6 road miles (mi) [10 kilometers (km)] to the southeast, or a licensed non-DOE disposal facility capable of handling RRM. At either disposal site, the contaminated materials would be stabilized and covered with layers of earth and rock. The proposed Dry Flats disposal site is on land administered by the Bureau of Land Management (BLM) and used primarily for livestock grazing. The final disposal site would cover approximately 57 ac (23 ha), which would be permanently transferred from the BLM to the DOE and restricted from future uses. The remedial action would be conducted by the DOE`s Uranium Mill Tailings Remedial Action (UMTRA) Project. This report discusses environmental impacts associated with the proposed remedial action.

Photochemical processing of organic aerosol at nearby continental sites: contrast between urban plumes and regional aerosol

Science.gov (United States)

Slowik, J. G.; Brook, J.; Chang, R. Y.-W.; Evans, G. J.; Hayden, K.; Jeong, C.-H.; Li, S.-M.; Liggio, J.; Liu, P. S. K.; McGuire, M.; Mihele, C.; Sjostedt, S.; Vlasenko, A.; Abbatt, J. P. D.

2011-03-01

As part of the BAQS-Met 2007 field campaign, Aerodyne time-of-flight aerosol mass spectrometers (ToF-AMS) were deployed at two sites in southwestern Ontario from 17 June to 11 July 2007. One instrument was located at Harrow, ON, a rural, agriculture-dominated area approximately 40 km southeast of the Detroit/Windsor/Windsor urban area and 5 km north of Lake Erie. The second instrument was located at Bear Creek, ON, a rural site approximately 70 km northeast of the Harrow site and 50 km east of Detroit/Windsor. Positive matrix factorization analysis of the combined organic mass spectral dataset yields factors related to secondary organic aerosol (SOA), direct emissions, and a factor tentatively attributed to the reactive uptake of isoprene and/or condensation of its early generation reaction products. This is the first application of PMF to simultaneous AMS measurements at different sites, an approach which allows for self-consistent, direct comparison of the datasets. Case studies are utilized to investigate processing of SOA from (1) fresh emissions from Detroit/Windsor and (2) regional aerosol during periods of inter-site flow. A strong correlation is observed between SOA/excess CO and photochemical age as represented by the NOx/NOy ratio for Detroit/Windsor outflow. Although this correlation is not evident for more aged air, measurements at the two sites during inter-site transport nevertheless show evidence of continued atmospheric processing by SOA production. However, the rate of SOA production decreases with airmass age from an initial value of ~10.1 μg m-3 ppmvCO-1 h-1 for the first ~10 h of plume processing to near-zero in an aged airmass (i.e. after several days). The initial SOA production rate is comparable to the observed rate in Mexico City over similar timescales.

Restoration of an urban site affected by a monazite processing plant

International Nuclear Information System (INIS)

Lauria, D.C.; Zenaro, R.; Sachett, I.A.

2000-01-01

For half a century the Santo Amaro Mill, USAM, processed monazite sand in order to isolate rare earth elements. At the beginning of its operation, the mill was located far from the centre of Sao Paulo city. However, over the years the city spread and engulfed the mill, which, together with economical and radiological problems, led to its being shutdown and later decommissioned. After the dismantling the equipment and the demolition of the buildings, a radiological survey was carried out, leading to the release of the site for unrestricted use. Based on a future residential occupation scenario complying with a dose limit of 1 mSv/y, it was concluded that a 0.65 Bq/g value of activity concentration of 228 Ra in the soil was the allowable residual limit of contamination for the site. The strategy to verify this requirement for site release comprised a preliminary soil survey by direct total gamma measurement with a sodium iodine scintillator detector, direct local gross alpha and beta counting of soil samples for monitoring during cleanup, and germanium detector gamma spectrometry of soil grab samples for the validation of monitoring methods. (author)

Hanford Integrated Planning Process: 1993 Hanford Site-specific science and technology plan

International Nuclear Information System (INIS)

1993-12-01

This document is the FY 1993 report on Hanford Site-specific science and technology (S ampersand T) needs for cleanup of the Site as developed via the Hanford Integrated Planning Process (HIPP). It identifies cleanup problems that lack demonstrated technology solutions and technologies that require additional development. Recommendations are provided regarding allocation of funding to address Hanford's highest-priority technology improvement needs, technology development needs, and scientific research needs, all compiled from a Sitewide perspective. In the past, the S ampersand T agenda for Hanford Site cleanup was sometimes driven by scientists and technologists, with minimal input from the ''problem owners'' (i.e., Westinghouse Hanford Company [WHC] staff who are responsible for cleanup activities). At other times, the problem-owners made decisions to proceed with cleanup without adequate scientific and technological inputs. Under both of these scenarios, there was no significant stakeholder involvement in the decision-making process. One of the key objectives of HIPP is to develop an understanding of the integrated S ampersand T requirements to support the cleanup mission, (a) as defined by the needs of the problem owners, the values of the stakeholders, and the technology development expertise that exists at Hanford and elsewhere. This requires a periodic, systematic assessment of these needs and values to appropriately define a comprehensive technology development program and a complementary scientific research program. Basic to our success is a methodology that is defensible from a technical perspective and acceptable to the stakeholders

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

International Nuclear Information System (INIS)

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

1999-01-01

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

New photocatalytic process provides 99.9+% reduction of VOC at Superfund site

Energy Technology Data Exchange (ETDEWEB)

Anon.

1999-03-01

A new photocatalytic process, dubbed the A-I-R-2000 Process, is described. The process is said to offer marked economic advantages, while providing consistent 99.9+% reduction of volatile organic compounds (VOCs) from soil vapours and groundwater at the Stamina Mills Superfund site in North Smithfield, Rhode Island. The A-I-R-2000 process has been developed by KSE Inc., of Amherst, Massachusetts, and has been licensed exclusively worldwide to Trojan Technologies, Inc., of London, Ontario. The process consists essentially of adsorption of VOCs onto a UV light-activated proprietary catalysts, for breakdown to carbon dioxide and water, and also to hydrochloric acid and a small amount of chlorine gas when the VOCs are chlorinated. With a maximum internal operating temperature of 125 degrees F, it is a low-energy system when compared to other catalytic technologies that feature thermal catalytic equipment. 1 photo.

A mixed integer linear programming model for integrating thermodynamic cycles for waste heat exploitation in process sites

International Nuclear Information System (INIS)

Oluleye, Gbemi; Smith, Robin

2016-01-01

Highlights: • MILP model developed for integration of waste heat recovery technologies in process sites. • Five thermodynamic cycles considered for exploitation of industrial waste heat. • Temperature and quantity of multiple waste heat sources considered. • Interactions with the site utility system considered. • Industrial case study presented to illustrate application of the proposed methodology. - Abstract: Thermodynamic cycles such as organic Rankine cycles, absorption chillers, absorption heat pumps, absorption heat transformers, and mechanical heat pumps are able to utilize wasted thermal energy in process sites for the generation of electrical power, chilling and heat at a higher temperature. In this work, a novel systematic framework is presented for optimal integration of these technologies in process sites. The framework is also used to assess the best design approach for integrating waste heat recovery technologies in process sites, i.e. stand-alone integration or a systems-oriented integration. The developed framework allows for: (1) selection of one or more waste heat sources (taking into account the temperatures and thermal energy content), (2) selection of one or more technology options and working fluids, (3) selection of end-uses of recovered energy, (4) exploitation of interactions with the existing site utility system and (5) the potential for heat recovery via heat exchange is also explored. The methodology is applied to an industrial case study. Results indicate a systems-oriented design approach reduces waste heat by 24%; fuel consumption by 54% and CO_2 emissions by 53% with a 2 year payback, and stand-alone design approach reduces waste heat by 12%; fuel consumption by 29% and CO_2 emissions by 20.5% with a 4 year payback. Therefore, benefits from waste heat utilization increase when interactions between the existing site utility system and the waste heat recovery technologies are explored simultaneously. The case study also shows

Comparison of the incidence of Listeria on equipment versus environmental sites within dairy processing plants.

Science.gov (United States)

Pritchard, T J; Flanders, K J; Donnelly, C W

1995-08-01

This study was undertaken to compare the incidence of Listeria contamination of processing equipment with that of the general dairy processing environment. A total of 378 sponge samples obtained from 21 dairy plants were analyzed for Listeria using three different enrichment media. Use of extended microbiological analysis allowed us to identify 26 Listeria positive sites which would have not been identified had a single test format been employed. Eighty (80) of 378 sites (21.2%) were identified as Listeria positive. Listeria innocua was isolated from 59 of the 80 (73.8%) positive samples, L. monocytogenes was identified in 35 (43.8%) of the positive samples, and L. seeligeri was isolated from 5 (6.3%) of the Listeria positive samples. Positive equipment samples were obtained from 6 of the 21 (28.6%) plants and 19 of the 21 (90.5%) plants had positive environmental sites. Seventeen of the 215 (7.9%) samples from equipment were positive for Listeria species. Eleven of these sites, including 3 holding tanks, 2 table tops, 3 conveyor/chain systems, a pasta filata wheel, a pint milk filler and a brine pre-filter machine, were positive for L. monocytogenes. Nineteen of the 21 (90.5%) plants had positive environmental sites. Sixty-three of the 163 (41.1%) samples from environmental sites were Listeria positive and 24 were positive for L. monocytogenes. Two-tailed student t-test analysis of the mean frequencies indicated that the level of contamination was significantly higher (p plant, and that greater emphasis needs to be placed on the cleaning and sanitizing of the plant environment.

Estimating HAPs and radionuclide emissions from a laboratory complex at a nuclear processing site

International Nuclear Information System (INIS)

Paul, R.A.; Faugl, T.

1993-01-01

A unique methodology was developed for conducting an air emission inventory (AEI) at a DOE nuclear processing facility. This methodology involved the use of computer-assisted design (CAD) drawings to document emission points, computerized process drawings to document industrial processes leading to emissions, and a computerized data base of AEI forms to document emission estimates and related process data. A detailed air emissions inventory for operating years 1985--1991 was recently implemented for the entire site using this methodology. One industrial area at the DOE Site is comprised of laboratory facilities that provide direct support to the nuclear reactor and recovery operations, developmental studies to support reactor and separation operations, and developmental studies to support waste handling and storage. The majority of the functions are conducted in a single large building complex wherein bench scale and pilot scale experiments are carried out involving radionuclides, hazardous air pollutants (HAP), and other chemicals reportable under the Clean Air Act Amendments (CAAA) and Superfund Amendments and Re-authorization Act (SARA) Title 111. The results of the inventory showed that HAP and radionuclide emissions from the laboratory complex were relatively minor

Photochemical processing of organic aerosol at nearby continental sites: contrast between urban plumes and regional aerosol

Directory of Open Access Journals (Sweden)

J. G. Slowik

2011-03-01

Full Text Available As part of the BAQS-Met 2007 field campaign, Aerodyne time-of-flight aerosol mass spectrometers (ToF-AMS were deployed at two sites in southwestern Ontario from 17 June to 11 July 2007. One instrument was located at Harrow, ON, a rural, agriculture-dominated area approximately 40 km southeast of the Detroit/Windsor/Windsor urban area and 5 km north of Lake Erie. The second instrument was located at Bear Creek, ON, a rural site approximately 70 km northeast of the Harrow site and 50 km east of Detroit/Windsor. Positive matrix factorization analysis of the combined organic mass spectral dataset yields factors related to secondary organic aerosol (SOA, direct emissions, and a factor tentatively attributed to the reactive uptake of isoprene and/or condensation of its early generation reaction products. This is the first application of PMF to simultaneous AMS measurements at different sites, an approach which allows for self-consistent, direct comparison of the datasets. Case studies are utilized to investigate processing of SOA from (1 fresh emissions from Detroit/Windsor and (2 regional aerosol during periods of inter-site flow. A strong correlation is observed between SOA/excess CO and photochemical age as represented by the NO_x/NO_y ratio for Detroit/Windsor outflow. Although this correlation is not evident for more aged air, measurements at the two sites during inter-site transport nevertheless show evidence of continued atmospheric processing by SOA production. However, the rate of SOA production decreases with airmass age from an initial value of ~10.1 μg m⁻³ ppmv_CO⁻¹ h⁻¹ for the first ~10 h of plume processing to near-zero in an aged airmass (i.e. after several days. The initial SOA production rate is comparable to the observed rate in Mexico City over similar timescales.

Robust multi-site MR data processing: iterative optimization of bias correction, tissue classification, and registration.

Science.gov (United States)

Young Kim, Eun; Johnson, Hans J

2013-01-01

A robust multi-modal tool, for automated registration, bias correction, and tissue classification, has been implemented for large-scale heterogeneous multi-site longitudinal MR data analysis. This work focused on improving the an iterative optimization framework between bias-correction, registration, and tissue classification inspired from previous work. The primary contributions are robustness improvements from incorporation of following four elements: (1) utilize multi-modal and repeated scans, (2) incorporate high-deformable registration, (3) use extended set of tissue definitions, and (4) use of multi-modal aware intensity-context priors. The benefits of these enhancements were investigated by a series of experiments with both simulated brain data set (BrainWeb) and by applying to highly-heterogeneous data from a 32 site imaging study with quality assessments through the expert visual inspection. The implementation of this tool is tailored for, but not limited to, large-scale data processing with great data variation with a flexible interface. In this paper, we describe enhancements to a joint registration, bias correction, and the tissue classification, that improve the generalizability and robustness for processing multi-modal longitudinal MR scans collected at multi-sites. The tool was evaluated by using both simulated and simulated and human subject MRI images. With these enhancements, the results showed improved robustness for large-scale heterogeneous MRI processing.

Evaluation of Mineral Deposits Along the Little Wind River, Riverton, WY, Processing Site

Energy Technology Data Exchange (ETDEWEB)

Campbell, Sam [Navarro Research and Engineering, Oak Ridge, TN (United States); Dam, Wiliam [US Department of Energy, Washington, DC (United States). Office of Legacy Management

2014-12-01

In 2012, the U.S.Department of Energy (DOE) began reassessing the former Riverton, Wyoming, Processing Site area for potential contaminant sources impacting groundwater. A flood in 2010 along the Little Wind River resulted in increases in groundwater contamination (DOE 2013).This investigation is a small part of continued efforts by DOE and other stakeholders to update human health and ecological risk assessments, to make a comprehensive examination of all exposure pathways to ensure that the site remains protective through established institutional controls. During field inspections at the Riverton Site in 2013, a white evaporitic mineral deposit was identified along the bank of the Little Wind River within the discharge zone of the groundwater contamination plume. In December 2013, Savannah River National Laboratory (SRNL) personnel collected a sample for analysis by X-ray fluorescence (Figure 1 shows the type of material sampled). The sample had a uranium concentration of approximately 64 to 73 parts per million. Although the uranium in this mineral deposit is within the expected range for evaporatic minerals in the western United States (SRNL 2014), DOE determined that additional assessment of the mineral deposit was warranted. In response to the initial collection and analysis of a sample of the mineral deposit, DOE developed a work plan (Work Plan to Sample Mineral Deposits Along the Little Wind River, Riverton, Wyoming, Processing Site [DOE 2014]) to further define the extent of these mineral deposits and the concentration of the associated contaminants (Appendix A). The work plan addressed field reconnaissance, mapping, sampling, and the assessment of risk associated with the mineral deposits adjacent to the Little Wind River.

Case study: remediation of a former uranium mining/processing site in Hungary

International Nuclear Information System (INIS)

Csovari, M. et al.

2004-01-01

The Hungarian uranium mining activities near Pecs lasted from 1958 to 1997. Approximately 46 Mt of rock were mined, from which 18.8 Mt of upgraded ore were processed. Some ore had been exported prior to the construction of the processing plant at the site. Remediation of the former uranium-related industrial sites is being carried out by the Mecsek Ore Environment Ltd. and started in the 1990s. Today the former mines and their surroundings are rehabilitated, former heap piles and a number of smaller waste rock piles have been relocated to a more protected area (waste rock pile N 3). Ongoing core remediation activities are directed to the remediation of the tailings ponds, and also water treatment issues are most important. Three water treatment facilities are currently in operation: a mine water treatment system with the objective to remove uranium and gain a marketable by-product; a pump-and-treat system to restore the groundwater quality in the vicinity of the tailing ponds; a pilot-scale, experimental passive in-situ groundwater treatment system to avoid migration of uranium contaminated groundwater. Refs. 5 (author)

Potentially disruptive hydrologic features, events and processes at the Yucca Mountain Site, Nevada

International Nuclear Information System (INIS)

Hoxie, D.T.

1995-01-01

Yucca Mountain, Nevada, has been selected by the United States to be evaluated as a potential site for the development of a geologic repository for the disposal of spent nuclear fuel and high-level radioactive waste. If the site is determined to be suitable for repository development and construction is authorized, the repository at the Yucca Mountain site is planned to be constructed in unsaturated tuff at a depth of about 250 meters below land surface and at a distance of about 250 meters above the water table. The intent of locating a repository in a thick unsaturated-zone geohydrologic setting, such as occurs at Yucca Mountain under the arid to semi-arid climatic conditions that currently prevail in the region, is to provide a natural setting for the repository system in which little ground water will be available to contact emplaced waste or to transport radioactive material from the repository to the biosphere. In principle, an unsaturated-zone repository will be vulnerable to water entry from both above and below. Consequently, a major effort within the site-characterization program at the Yucca Mountain site is concerned with identifying and evaluating those features, events, and processes, such as increased net infiltration or water-table rise, whose presence or future occurrence could introduce water into a potential repository at the site in quantities sufficient to compromise the waste-isolation capability of the repository system

Priority Determination of Underwater Tourism Site Development in Gorontalo Province using Analytical Hierarchy Process (AHP)

Science.gov (United States)

Rohandi, M.; Tuloli, M. Y.; Jassin, R. T.

2018-02-01

This research aims to determine the development of priority of underwater tourism in Gorontalo province using the Analytical Hierarchy Process (AHP) method which is one of DSS methods applying Multi-Attribute Decision Making (MADM). This method used 5 criteria and 28 alternatives to determine the best priority of underwater tourism site development in Gorontalo province. Based on the AHP calculation it appeared that the best priority development of underwater tourism site is Pulau Cinta whose total AHP score is 0.489 or 48.9%. This DSS produced a reliable result, faster solution, time-saving, and low cost for the decision makers to obtain the best underwater tourism site to be developed.

Conserved Epigenetic Mechanisms Could Play a Key Role in Regulation of Photosynthesis and Development-Related Genes during Needle Development of Pinus radiata.

Science.gov (United States)

Valledor, Luis; Pascual, Jesús; Meijón, Mónica; Escandón, Mónica; Cañal, María Jesús

2015-01-01

Needle maturation is a complex process that involves cell growth, differentiation and tissue remodelling towards the acquisition of full physiological competence. Leaf induction mechanisms are well known; however, those underlying the acquisition of physiological competence are still poorly understood, especially in conifers. We studied the specific epigenetic regulation of genes defining organ function (PrRBCS and PrRBCA) and competence and stress response (PrCSDP2 and PrSHMT4) during three stages of needle development and one de-differentiated control. Gene-specific changes in DNA methylation and histone were analysed by bisulfite sequencing and chromatin immunoprecipitation (ChIP). The expression of PrRBCA and PrRBCS increased during needle maturation and was associated with the progressive loss of H3K9me3, H3K27me3 and the increase in AcH4. The maturation-related silencing of PrSHMT4 was correlated with increased H3K9me3 levels, and the repression of PrCSDP2, to the interplay between AcH4, H3K27me3, H3K9me3 and specific DNA methylation. The employ of HAT and HDAC inhibitors led to a further determination of the role of histone acetylation in the regulation of our target genes. The integration of these results with high-throughput analyses in Arabidopsis thaliana and Populus trichocarpa suggests that the specific epigenetic mechanisms that regulate photosynthetic genes are conserved between the analysed species.

Conserved Epigenetic Mechanisms Could Play a Key Role in Regulation of Photosynthesis and Development-Related Genes during Needle Development of Pinus radiata.

Directory of Open Access Journals (Sweden)

Luis Valledor

Full Text Available Needle maturation is a complex process that involves cell growth, differentiation and tissue remodelling towards the acquisition of full physiological competence. Leaf induction mechanisms are well known; however, those underlying the acquisition of physiological competence are still poorly understood, especially in conifers. We studied the specific epigenetic regulation of genes defining organ function (PrRBCS and PrRBCA and competence and stress response (PrCSDP2 and PrSHMT4 during three stages of needle development and one de-differentiated control. Gene-specific changes in DNA methylation and histone were analysed by bisulfite sequencing and chromatin immunoprecipitation (ChIP. The expression of PrRBCA and PrRBCS increased during needle maturation and was associated with the progressive loss of H3K9me3, H3K27me3 and the increase in AcH4. The maturation-related silencing of PrSHMT4 was correlated with increased H3K9me3 levels, and the repression of PrCSDP2, to the interplay between AcH4, H3K27me3, H3K9me3 and specific DNA methylation. The employ of HAT and HDAC inhibitors led to a further determination of the role of histone acetylation in the regulation of our target genes. The integration of these results with high-throughput analyses in Arabidopsis thaliana and Populus trichocarpa suggests that the specific epigenetic mechanisms that regulate photosynthetic genes are conserved between the analysed species.

SKI's engagement in the process for siting a spent nuclear fuel repository

Energy Technology Data Exchange (ETDEWEB)

Paeivioe Jonsson, Josefin; Westerlind, Magnus [Swedish Nuclear Power Inspectorate, Stockholm (Sweden)

2006-09-15

In Sweden, issues concerning the disposal of nuclear waste historically required co-operation among primarily two main actors: The nuclear industry and the state. Municipalities involved in SKB's feasibility studies objected to the fact that they lacked resources to keep the people in the municipality informed about the ongoing work. As a result the Parliament decided that municipalities involved in SKB's siting process should receive money from the nuclear waste fund for their engagement. Since 2005 resources also have been made available for NGO's participating in SKB's ongoing EIA-process. In total they can yearly receive up to 2.5 million Swedish kronor. The fact that new actors continuously have been engaged in disposal of spent nuclear fuel has meant that 'old' actors, particularly SKB, the regulators (the Swedish Nuclear Power Inspectorate, SKI, and the Swedish Radiation Protection Authority, SSI) have had to evaluate, develop and clarify their roles and strategies for dialogue and regulatory oversight. This paper presents the effects the increased engagement has had on SKI's regulatory activities. Looking back it is possible to identify two well-defined break points in SKI's views on communication and active participation in the siting process. The first was the so-called DIALOGUE-project, which was initiated by SKI in the early 1990s. In this research project there were participants from e.g. SKI and SSI, municipalities and environmental organisations. The two most important conclusions for SKI were firstly that regulators can and should participate already in the early stages of a siting process, and that this can be done without loosing credibility as an independent reviewer of a licence application and secondly that actors (in the siting process) with conflicting interests and views can reach agreement on the basis for decisions. The second break point occurred in the mid 1990s when SKB announced that the

Assessment of Public Acceptability in LILW Repository Site Selection Process in Slovenia

International Nuclear Information System (INIS)

Zeleznik, N.; Kralj, M.; Polic, M.; Kos, D.

2006-01-01

Slovenian national agency for radioactive waste management ARAO has after longer period of preparation activities started with the more direct work on the site selection process for low and intermediate level waste (LILW) repository. In November 2004, the official administrative procedure for the siting of the repository started with the First public conference on spatial planning issues carried out by the Ministry of Environment and Spatial Planning together with ARAO. Just after the conference the Program for the preparation of the Detailed plan of national importance for the LILW repository was accepted by the Ministry. ARAO invited in the beginning of December 2004 all local communities in Slovenia (except 3 of them which have already refused to cooperate) to participate and volunteer a site or area in their local community for further investigation. The invitation for the application of local communities provided clear instructions on how to participate in further determination of potentially suitable sites and under what conditions. By the beginning of April 2005 ARAO finished the bidding process with 8 applications of local communities which decided to participate in the further site selection for LILW repository. Due to the financial and other limitations (human resources, spatial planning procedure, etc.) only in maximum three local communities further characterization could be performed. Therefore prefeasibility study of all volunteer local communities was conducted in which besides technical, environmental and spatial availability also public acceptability should be assessed. For assessment of public acceptability the methodology has been prepared which includes objective parameters of local environment (such as demographic data, economy, infrastructure and social issues in relation to the repository) as well as subjective values (attitudes of individual groups - opinion makers, politicians and all residents - to the sitting and construction of LILW

Independent technical review of Savannah River Site Defense Waste Processing Facility technical issues

International Nuclear Information System (INIS)

1992-07-01

The Savannah River Site (SRS) Defense Waste Processing Facility (DWPF) will vitrify high-level radioactive waste that is presently stored as liquid, salt-cake, and sludge in 51 waste-storage tanks. Construction of the DWPF began in 1984, and the Westinghouse Savannah Company (WSRC) considers the plant to be 100% turned over from construction and 91% complete. Cold-chemical runs are scheduled to begin in November 1992, and hot start up is projected for June 1994. It is estimated that the plant lifetime must exceed 15 years to complete the vitrification of the current, high-level tank waste. In a memo to the Assistant Secretary for Defense Programs (DP-1), the Assistant Secretary for Environmental Restoration and Waste management (EM-1) established the need for an Independent Technical Review (ITR), or the Red Team, to ''review process technology issues preventing start up of the DWPF.'' This report documents the findings of an Independent Technical Review (ITR) conducted by the Department of Energy (DOE), Office of Environmental Restoration and Waste Management (EM), at the request of the Assistant Secretary for Environmental Restoration and Waste Management, of specified aspects of Defense Waste Process Facility (DWPF) process technology. Information for the assessment was drawn from documents provided to the ITR Team by the Westinghouse Savannah River Company (WSRC), and presentations, discussions, interviews, and tours held at the Savannah River Site (SRS) during the weeks of February and March 9, 1992

Advanced LIGO constraints on neutron star mergers and r-process sites

International Nuclear Information System (INIS)

Côté, Benoit; Belczynski, Krzysztof; Fryer, Chris L.; Ritter, Christian

2017-01-01

The role of compact binary mergers as the main production site of r-process elements is investigated by combining stellar abundances of Eu observed in the Milky Way, galactic chemical evolution (GCE) simulations, and binary population synthesis models, and gravitational wave measurements from Advanced LIGO. We compiled and reviewed seven recent GCE studies to extract the frequency of neutron star–neutron star (NS–NS) mergers that is needed in order to reproduce the observed [Eu/Fe] versus [Fe/H] relationship. We used our simple chemical evolution code to explore the impact of different analytical delay-time distribution functions for NS–NS mergers. We then combined our metallicity-dependent population synthesis models with our chemical evolution code to bring their predictions, for both NS–NS mergers and black hole–neutron star mergers, into a GCE context. Finally, we convolved our results with the cosmic star formation history to provide a direct comparison with current and upcoming Advanced LIGO measurements. When assuming that NS–NS mergers are the exclusive r-process sites, and that the ejected r-process mass per merger event is 0.01 M_⊙, the number of NS–NS mergers needed in GCE studies is about 10 times larger than what is predicted by standard population synthesis models. Here, these two distinct fields can only be consistent with each other when assuming optimistic rates, massive NS–NS merger ejecta, and low Fe yields for massive stars. For now, population synthesis models and GCE simulations are in agreement with the current upper limit (O1) established by Advanced LIGO during their first run of observations. Upcoming measurements will provide an important constraint on the actual local NS–NS merger rate, will provide valuable insights on the plausibility of the GCE requirement, and will help to define whether or not compact binary mergers can be the dominant source of r-process elements in the universe.

Stormwater Pollutant Process Analysis with Long-Term Online Monitoring Data at Micro-Scale Sites

Directory of Open Access Journals (Sweden)

Dominik Leutnant

2016-07-01

Full Text Available Stormwater runoff quality was measured with online turbidity sensors at four common types of small urban subcatchments: (i a flat roof; (ii a parking lot; (iii a residential catchment; and (iv a high-traffic street. Samples were taken to estimate site-specific correlations between total suspended solids (TSS and turbidity. Continuous TSS time series were derived from online turbidity measurements and were used to estimate event loads and event mean concentrations. Rainfall runoff event characteristics were subjected to correlation analysis to TSS loads. Significant correlations were found for rainfall intensities at sites with high imperviousness and decrease with increasing catchment size. Antecedent dry weather periods are only correlated at the parking lot site. Intra-event TSS load distributions were studied with M (V-curves. M (V-curves are grouped at runoff quantiles and statistically described with boxplots. All sites show, in general, a more pronounced first-flush effect. While wash-off of the flat roof tends to be source-limited, the parking lot and high-traffic street sites show a more transport-limited behavior. Wash-off process of the residential catchment appears to be influenced by a composition of different subcatchments.

Automatic web site authoring with SiteGuide

NARCIS (Netherlands)

de Boer, V.; Hollink, V.; van Someren, M.W.; Kłopotek, M.A.; Przepiórkowski, A.; Wierzchoń, S.T.; Trojanowski, K.

2009-01-01

An important step in the design process for a web site is to determine which information is to be included and how the information should be organized on the web site’s pages. In this paper we describe ’SiteGuide’, a tool that automatically produces an information architecture for a web site that a

Tritium confinement in a new tritium processing facility at the Savannah River Site

International Nuclear Information System (INIS)

Heung, L.K.; Owen, J.H.; Hsu, R.H.; Hashinger, R.F.; Ward, D.E.; Bandola, P.E.

1991-01-01

A new tritium processing facility, named the Replacement Tritium Facility (RTF), has been completed and is being prepared for startup at the Savannah River Site (SRS). The RTF has the capability to recover, purify and separate hydrogen isotopes from recycled gas containers. A multilayered confinement system is designed to reduce tritium losses to the environment. This confinement system is expected to confine and recover any tritium that might escape the process equipment, and to maintain the tritium concentration in the nitrogen glovebox atmosphere to less than 10 -2 μCi/cc tritium

Integral Public Activities as a Support to the Site Selection Process for LILW Repository

International Nuclear Information System (INIS)

Zeleznik, N.; Kralj, M.

2008-01-01

The first site selection process for low and intermediate level radioactive waste (LILW) repository took place between 1990 and 1993 in Slovenia was stopped unsuccessfully with very strong public opposition at local level, followed by political withdrawal on national level. As one of the consequences ARAO started to develop new approach to the site selection based also on the findings from sociology, psychology and other human sciences. The recommendations on public involvement and transparency were so strong that ARAO started with first limited public relation (PR) activities which later grew to the PR process which supports all technical activities in ARAO. Presently the PR process covers communication, information and research activities and assures careful planning, prompt responds and involvement of the highest responsible persons at ARAO. Integral public relation activities are divided in several parts. Majority of activities support the on-going site selection process where activities are presently focused on functioning of local partnerships developed as a basic communication tool to involve as much citizens and public as possible on local level. Presently two local partnerships are working in Krsko and Brezice community with clear role to enhance public involvement according to Aarchus convention. Each of the partnerships is organized in a specific way adjusted to the local needs. Communication activities are organized also for different other projects and are preparing the necessary basis for the work with different groups of stake holders and in different situations. As a foundation very broad information material, such as books, leaflets, reports, magazines, video cassettes, CD and DVD on the radioactive waste management is prepared and used for different purposes. We also try to be proactive with web pages and have a well organized visitors' center. Improvement of public relation process is achieved through constant survey and feed-back information

Comment and response document for the UMTRA Project vitro processing site completion report Salt Lake City, Utah. Revision 1

International Nuclear Information System (INIS)

1995-03-01

This Comment and Response Document is a series of UMTRA document review forms regarding the UMTRA Project Vitro Processing Site Completion Report for Salt Lake City, Utah in March, 1995. The completion report provides evidence that the final Salt Lake City, Utah, processing site property conditions are in accordance with the approved design and that all U.S. Environmental Protection Agency (EPA) standards have been satisfied. Included as appendices to support the stated conclusions are the record drawings; a summary of grid test results; contract specifications and construction drawings, the EPA standards (40 CFR Part 192); the audit, inspection, and surveillance summary; the permit information; and project photographs. The principal objective of the remedial action at Salt Lake City is to remove the tailings from the processing site, render the site free of contamination to EPA standards, and restore the site to the final design grade elevations. Each section is evaluated in detail to check all aspects of above report, especially the inclusion of adequate verification data. Each review form contains a section entitled State of Utah Response and Action, which is an explanation or correction of DOE criticisms of the report

Public involvement in the siting of contentious facilities; Lessons from the radioactive waste repository siting programmes in Canada and the United States, with special reference to the Swedish repository siting process

International Nuclear Information System (INIS)

Richardson, P.J.

1997-08-01

This report describes the conclusion of a two-part programme, begun in 1994 with the overall aim of assisting in the development of an acceptable public participation strategy for use in Sweden for the siting of contentious facilities, with particular reference to the ongoing siting programme for a deep repository for spent nuclear fuel. The first part of the work programme, a global review of siting practice, was reported as SSI Rapport 94-15, in November 1994. This recommended further detailed studies of at least two individual programmes, which have now been carried out in Canada and the United States, and are reported on here. They involved face to face meetings with many of the main stake holders in the two programmes and enabled valuable insight to be gained into the potential problems associated with increased public participation, as well as identifying good practice where it exists. The lessons learned have then been applied to the evolving repository siting process in Sweden. 35 refs

Public involvement in the siting of contentious facilities; Lessons from the radioactive waste repository siting programmes in Canada and the United States, with special reference to the Swedish repository siting process

Energy Technology Data Exchange (ETDEWEB)

Richardson, P J [Geosciences for Development and the Environment (United Kingdom)

1997-08-01

This report describes the conclusion of a two-part programme, begun in 1994 with the overall aim of assisting in the development of an acceptable public participation strategy for use in Sweden for the siting of contentious facilities, with particular reference to the ongoing siting programme for a deep repository for spent nuclear fuel. The first part of the work programme, a global review of siting practice, was reported as SSI Rapport 94-15, in November 1994. This recommended further detailed studies of at least two individual programmes, which have now been carried out in Canada and the United States, and are reported on here. They involved face to face meetings with many of the main stake holders in the two programmes and enabled valuable insight to be gained into the potential problems associated with increased public participation, as well as identifying good practice where it exists. The lessons learned have then been applied to the evolving repository siting process in Sweden. 35 refs.

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

Canada's deep geological repository for used nuclear fuel - the geoscientific site evaluation process

Energy Technology Data Exchange (ETDEWEB)

Belfadhel, M.B.; Blyth, A.; Desroches, A.; Hirschorn, S.; Mckelvie, J.; Sanchez-Rico Castejon, M.; Parmenter, A.; Urrutia-Bustos, A.; Vorauer, A., E-mail: mbenbelfadhel@nwmo.ca [Nuclear Waste Management Organization, Toronto, ON (Canada)

2014-07-01

The Nuclear Waste Management Organization (NWMO) is responsible for implementing Adaptive Phased Management (APM), the approach selected by the Government of Canada for the long-term management of used nuclear fuel generated by Canadian nuclear reactors. The ultimate objective of APM is the centralized containment and isolation of Canada's used nuclear fuel in a Deep Geological Repository in a suitable crystalline or sedimentary rock formation. In May 2010, the NWMO initiated a nine-step site selection process to find an informed and willing community to host the project. This paper describes the approach, methods and criteria being used to assess the geoscientific suitability of communities currently involved in the site selection process. The social, cultural and economic aspects of the assessment are discussed in a companion paper. (author)

Active-Site Hydration and Water Diffusion in Cytochrome P450cam: A Highly Dynamic Process

Energy Technology Data Exchange (ETDEWEB)

Miao, Yinglong [ORNL; Baudry, Jerome Y [ORNL

2011-01-01

Long-timescale molecular dynamics simulations (300 ns) are performed on both the apo- (i.e., camphor-free) and camphor-bound cytochrome P450cam (CYP101). Water diffusion into and out of the protein active site is observed without biased sampling methods. During the course of the molecular dynamics simulation, an average of 6.4 water molecules is observed in the camphor-binding site of the apo form, compared to zero water molecules in the binding site of the substrate-bound form, in agreement with the number of water molecules observed in crystal structures of the same species. However, as many as 12 water molecules can be present at a given time in the camphor-binding region of the active site in the case of apo-P450cam, revealing a highly dynamic process for hydration of the protein active site, with water molecules exchanging rapidly with the bulk solvent. Water molecules are also found to exchange locations frequently inside the active site, preferentially clustering in regions surrounding the water molecules observed in the crystal structure. Potential-of-mean-force calculations identify thermodynamically favored trans-protein pathways for the diffusion of water molecules between the protein active site and the bulk solvent. Binding of camphor in the active site modifies the free-energy landscape of P450cam channels toward favoring the diffusion of water molecules out of the protein active site.

Potential for a process-based monitoring method above geologic carbon storage sites using dissolved gases in freshwater aquifers

Energy Technology Data Exchange (ETDEWEB)

Romanak, Katherine [Gulf Coast Carbon Center, Bureau of Economic Geology, The University of Texas at Austin, TX 78713 (United States); Dobeck, Laura; Spangler, Lee [Department of Chemistry and Biochemistry, Montana State University, Bozeman, MT 59717 (United States); Dixon, Tim [IEA Greenhouse Gas R and D Programme, Cheltenham GL52 7RZ (United Kingdom)

2013-07-01

The process-based method is a new technique for monitoring CO{sub 2} storage permanence in the vadose zone above geologic carbon storage (GCS) sites. This method uses ratios of coexisting gas species to understand geochemical processes rather than comparing CO{sub 2} concentrations with large baseline data sets, thereby making monitoring more efficient. In the vadose zone, ratios among coexisting gases (CO{sub 2}, O{sub 2}, N{sub 2} and CH{sub 4}) have been used to distinguish biologic respiration, water-rock-CO{sub 2} interaction, and methane oxidation from a leakage signal. We report the preliminary results of a feasibility test conducted in July 2012 at the Zero Emission Research and Technology Center (ZERT) controlled release site in Montana, USA to discern whether the method could be applied to dissolved gases in groundwater, thereby enhancing groundwater monitoring. Preliminary results are favorable, making the process-based approach potentially useful for monitoring shallow freshwater aquifers above GCS sites. (authors)

Processing sites in the human immunodeficiency virus type 1 (HIV-1) Gag-Pro-Pol precursor are cleaved by the viral protease at different rates.

Science.gov (United States)

Pettit, Steve C; Lindquist, Jeffrey N; Kaplan, Andrew H; Swanstrom, Ronald

2005-11-01

We have examined the kinetics of processing of the HIV-1 Gag-Pro-Pol precursor in an in vitro assay with mature protease added in trans. The processing sites were cleaved at different rates to produce distinct intermediates. The initial cleavage occurred at the p2/NC site. Intermediate cleavages occurred at similar rates at the MA/CA and RT/IN sites, and to a lesser extent at sites upstream of RT. Late cleavages occurred at the sites flanking the protease (PR) domain, suggesting sequestering of these sites. We observed paired intermediates indicative of half- cleavage of RT/RH site, suggesting that the RT domain in Gag-Pro-Pol was in a dimeric form under these assay conditions. These results clarify our understanding of the processing kinetics of the Gag-Pro-Pol precursor and suggest regulated cleavage. Our results further suggest that early dimerization of the PR and RT domains may serve as a regulatory element to influence the kinetics of processing within the Pol domain.

Implementation of hearings in the Swedish process for siting a spent nuclear fuel repository

International Nuclear Information System (INIS)

Westerlind, Magnus; Wiklund, Aasa

2001-01-01

The problem of bringing all stakeholders on the scene to penetrate an issue of great complexity is not unique for nuclear waste management. There are an increasing number of site selection processes for disposal of nuclear waste around the world. During the 90's many of these siting processes have gone into a more decisive phase where public participation and transparency get more and more attention. Municipalities, NGOs and the public do no longer accept ready-made solutions but have legitimate claims to be part of the decision making and siting processes at an early stage. The attempts to increase the level of transparency and public involvement differ from country to country and depend e.g. on culture, history and societal conditions as well as on the precise phase in the siting process. However, many processes include public hearings as one tool to enhance transparency. In general, Sweden has not a long history of using hearings in decision making. In the area of nuclear waste management and disposal hearings have so far been rarely used. In 1997 and 1998 two public hearings were arranged by the Swedish Nuclear Power Inspectorate, SKI, in conjunction with the licensing of the enlargement of the Central Interim Storage for Spent Nuclear Fuel, CLAB. These hearings showed that hearings could improve the decision making process. SKI and SSI strongly believe the effort was worthwhile and that hearings will continue to be used in the nuclear waste programme. The hearings provided a forum for local stakeholders to pose questions and stretch both the implementer and to some extent also the authorities. The hearings managed to focus on relevant issues at this stage of the siting process and gave the audience a chance to evaluate and challenge the trustworthiness of the implementer and authorities. In this respect the hearings contributed to transparent and democratic decision making. Some of the keys to the success were: Unbiased and skilled moderators with capacity to

Sites that Can Produce Left-handed Amino Acids in the Supernova Neutrino Amino Acid Processing Model

Science.gov (United States)

Boyd, Richard N.; Famiano, Michael A.; Onaka, Takashi; Kajino, Toshitaka

2018-03-01

The Supernova Neutrino Amino Acid Processing model, which uses electron anti-neutrinos and the magnetic field from a source object such as a supernova to selectively destroy one amino acid chirality, is studied for possible sites that would produce meteoroids with partially left-handed amino acids. Several sites appear to provide the requisite magnetic field intensities and electron anti-neutrino fluxes. These results have obvious implications for the origin of life on Earth.

Ecological studies related to construction of the Defense Waste Processing Facility on the Savannah River Site

International Nuclear Information System (INIS)

Scott, D.E.; Pechmann, J.H.K.; Knox, J.N.; Estes, R.A.; McGregor, J.H.; Bailey, K.

1988-12-01

The Savannah River Ecology Laboratory has completed 10 years of ecological studies related to the construction of the Defense Waste Processing Facility (DWPF) on the Savannah River Site. This progress report examines water quality studies on streams peripheral to the DWPF construction site and examines the effectiveness of ''refuge ponds'' in ameliorating the effects of construction on local amphibians. Individual papers on these topics are indexed separately. 93 refs., 15 figs., 15 tabs

Site selection process for new nuclear power plants - a method to support decision making and improving public participation

International Nuclear Information System (INIS)

Martins, Vivian B.; Cunha, Tatiana S. da; Simoes Filho, Francisco Fernando Lamego; Lapa, Celso Marcelo F.

2011-01-01

The Brazilian Energy Plan (PNE 2030) that guides the Government in formulating its strategy for expanding energy supply by 2030 highlights the need for the Brazilian electrical system have more than 4,000 MW from nuclear sources by 2025. Therefore, the Government presented a proposal to build four more nuclear power plants with capacity of 1,000 MW each, at first, two in the Northeast and two in Southeast. The selection and site assessment are key parts of the installation process of a nuclear plant and may significantly affect the cost, public acceptance and safety of the facility during its entire life cycle. The result of this initial stage, it can even seriously affect program success. Wrong decisions in the process of site selection may also require a financial commitment to higher planned in a later phase of the project, besides causing extensive and expensive downtime. Select the location where these units will be built is not a trivial process, because involves the consideration of multiple criteria and judgments in addition to obtaining, organizing and managing a diverse range of data, both qualitative and quantitative, to assist in decision making and ensure that the site selected is the most appropriate in relation to safety and technical, economic and environmental feasibility. This paper presents an overview of the site selection process and its stages, the criteria involved in each step, the tools to support decision making that can be used and the difficulties in applying a formal process of decision making. Also discussed are ways to make the process more transparent and democratic, increasing public involvement as a way to improve acceptance and reduce opposition from various sectors of society, trying to minimize the expense and time involved in the implementation of undertakings of this kind. (author)

Further development of public participation in the site-selection and approval process of a final repository in Germany

Energy Technology Data Exchange (ETDEWEB)

Barth, Regine; Kallenbach-Herbert, Beate [OeEo-Institute e.V., Inst. for Applied Ecology, Darmstadt (Germany); Arens, Georg [Federal Office for Radiation Protection (BfS), Salzgitter (Germany)

2006-09-15

This paper reflects the first findings of a current research project funded by the German Federal Office for Radiation Protection and conducted by an interdisciplinary working group of the OEko-Institute. One focus of this project is the systematic analysis of past and existing participatory processes in different nuclear and non-nuclear projects. On the basis of this analysis and a literature review a specific concept for public participation in the site-selection and approval process of a repository for high radioactive waste (HAW repository) in Germany will be derived. The concept shall foster transparency and acceptance. The working group of the OEko-Institute combines long standing research experience and an intimate knowledge of radioactive waste management including political, technical, management and social problems of final disposal on the one hand. On the other hand members play an active role in stakeholder processes of different non-nuclear projects as well as experience with a wide range of participative measures and their impact. This allows an approach which integrates the specific features of radioactive waste disposal with a wider perspective on the demands and opportunities of stakeholder processes. The procedure of site selection for a HAW repository in Germany still has to be specified. The procedure introduced by the 'Committee on a Site Selection Procedure for Repository Sites' (Arbeitskreis Auswahlverfahren Endlagerstandorte - AkEnd) has not been adopted. The Committee had suggested installing a negotiation group to discuss the AkEnd proposals in the so called 'Phase II'. This suggestion could not be followed because not all relevant stakeholders were willing to participate. An internal draft for a federal law implementing main elements of the AkEnd findings was developed by the Ministry for Environment in 2005, but has never been brought to the cabinet. Due to the change of Government in Germany, the next steps still are

Further development of public participation in the site-selection and approval process of a final repository in Germany

International Nuclear Information System (INIS)

Barth, Regine; Kallenbach-Herbert, Beate; Arens, Georg

2006-01-01

This paper reflects the first findings of a current research project funded by the German Federal Office for Radiation Protection and conducted by an interdisciplinary working group of the OEko-Institute. One focus of this project is the systematic analysis of past and existing participatory processes in different nuclear and non-nuclear projects. On the basis of this analysis and a literature review a specific concept for public participation in the site-selection and approval process of a repository for high radioactive waste (HAW repository) in Germany will be derived. The concept shall foster transparency and acceptance. The working group of the OEko-Institute combines long standing research experience and an intimate knowledge of radioactive waste management including political, technical, management and social problems of final disposal on the one hand. On the other hand members play an active role in stakeholder processes of different non-nuclear projects as well as experience with a wide range of participative measures and their impact. This allows an approach which integrates the specific features of radioactive waste disposal with a wider perspective on the demands and opportunities of stakeholder processes. The procedure of site selection for a HAW repository in Germany still has to be specified. The procedure introduced by the 'Committee on a Site Selection Procedure for Repository Sites' (Arbeitskreis Auswahlverfahren Endlagerstandorte - AkEnd) has not been adopted. The Committee had suggested installing a negotiation group to discuss the AkEnd proposals in the so called 'Phase II'. This suggestion could not be followed because not all relevant stakeholders were willing to participate. An internal draft for a federal law implementing main elements of the AkEnd findings was developed by the Ministry for Environment in 2005, but has never been brought to the cabinet. Due to the change of Government in Germany, the next steps still are under consideration

Accelerated cleanup of the 316-5 process trenches at the Hanford Site

International Nuclear Information System (INIS)

Henckel, G.C.; Johnson, W.L.

1991-01-01

In October, 1990, the US Department of Energy, the US Environmental Protection Agency, and the Washington State Department of Ecology signed an Agreement in Principle to accelerate remedial actions on the Hanford Site. Removal of contaminated sediments from the 300 Area (316-5) Process Trenches was one of the three initial candidate locations identified for the accelerated remediation. The trenches have received small quantities of radioactive and hazardous wastes in large volumes of process water (up to 11,360,000 L/day). The trenches are approximately 300 m west of the Columbia River and 7 m above the water table. The trenches are an active interim permitted disposal facility that may remain active for the next few years. In order to reduce the potential for migration of contaminants from the trench sediments into the groundwater, an expedited response action to remove approximately 2,500 m 2 of soil from the active portion of the trenches is being performed. Field activities were initiated in July 1991 with site preparation. The first trench to be excavated was completed by August 15, 1991. Approximately 2 weeks were needed to begin removal activities in the second trench. The second trench should be completed by October 1, 1991, with the subsequent construction of an interim cover over the consolidated materials completed by December 1991

Accelerated cleanup of the 316-5 Process Trenches at the Hanford Site

International Nuclear Information System (INIS)

Henckel, G.C.; Johnson, W.L.

1991-09-01

In October, 1990, the US Department of Energy, the US Environmental Protection Agency, and the Washington State Department of Ecology signed an Agreement in Principle to accelerate remedial actions on the Hanford Site. Removal of contaminated sediments from the 300 Area (316-5) Process Trenches was on of the three initial candidate locations identified for the accelerated remediation. The trenches have received small quantities of radioactive and hazardous wastes in large volumes of process water (up to 11,360,000 L/day). The trenches are approximately 300 m west of the Columbia River and 7 m above the water table. The trenches are an active interim permitted disposal facility that may remain active for the next few years. In order to reduce the potential for migration of contaminants from the trench sediments into the groundwater, an expedited response action to remove approximately 2,500 m 2 of soil from the active portion of the trenches is being performed. Field activities were initiated in July 1991 with site preparation. The first trench to be excavated was completed by August 15, 1991. Approximately 2 weeks were needed to begin removal activities in the second trench. The second trench should be completed by October 1, 1991, with the subsequent construction of an interim cover over the consolidated materials completed by December 1991

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

Energy Technology Data Exchange (ETDEWEB)

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

2013-07-01

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

Testing of Air Pulse Agitators to Support Design of Savannah River Site Highly Radioactive Processing at the Salt Waste Processing Facility

International Nuclear Information System (INIS)

Gallego, R.M.; Stephens, A.B.; Wilkinson, R.H.; Dev, H.; Suggs, P.C.

2006-01-01

The Salt Waste Processing Facility (SWPF) is intended to concentrate the highly radioactive constituents from waste salt solutions at the Savannah River Site (SRS). Air Pulse Agitators (APAs) were selected for process mixing in high-radiation locations at the SWPF. This technology has the advantage of no moving parts within the hot cell, eliminating potential failure modes and the need for maintenance within the high-radiation environment. This paper describes the results of APA tests performed to gain operational and performance data for the SWPF design. (authors)

Ecological studies related to construction of the Defense Waste Processing Facility on the Savannah River Site

Energy Technology Data Exchange (ETDEWEB)

Scott, D.E.; Pechmann, J.H.K.; Knox, J.N.; Estes, R.A.; McGregor, J.H.; Bailey, K. (ed.)

1988-12-01

The Savannah River Ecology Laboratory has completed 10 years of ecological studies related to the construction of the Defense Waste Processing Facility (DWPF) on the Savannah River Site. This progress report examines water quality studies on streams peripheral to the DWPF construction site and examines the effectiveness of refuge ponds'' in ameliorating the effects of construction on local amphibians. Individual papers on these topics are indexed separately. 93 refs., 15 figs., 15 tabs. (MHB)

Processing sites in the human immunodeficiency virus type 1 (HIV-1 Gag-Pro-Pol precursor are cleaved by the viral protease at different rates

Directory of Open Access Journals (Sweden)

Lindquist Jeffrey N

2005-11-01

Full Text Available Abstract We have examined the kinetics of processing of the HIV-1 Gag-Pro-Pol precursor in an in vitro assay with mature protease added in trans. The processing sites were cleaved at different rates to produce distinct intermediates. The initial cleavage occurred at the p2/NC site. Intermediate cleavages occurred at similar rates at the MA/CA and RT/IN sites, and to a lesser extent at sites upstream of RT. Late cleavages occurred at the sites flanking the protease (PR domain, suggesting sequestering of these sites. We observed paired intermediates indicative of half- cleavage of RT/RH site, suggesting that the RT domain in Gag-Pro-Pol was in a dimeric form under these assay conditions. These results clarify our understanding of the processing kinetics of the Gag-Pro-Pol precursor and suggest regulated cleavage. Our results further suggest that early dimerization of the PR and RT domains may serve as a regulatory element to influence the kinetics of processing within the Pol domain.

Remaining Sites Verification Package for the 100-F-26:12, 1.8-m (72-in.) Main Process Sewer Pipeline. Attachment to Waste Site Reclassification Form 2007-034

International Nuclear Information System (INIS)

Capron, J.M.

2008-01-01

The 100-F-26:12 waste site was an approximately 308-m-long, 1.8-m-diameter east-west-trending reinforced concrete pipe that joined the North Process Sewer Pipelines (100-F-26:1) and the South Process Pipelines (100-F-26:4) with the 1.8-m reactor cooling water effluent pipeline (100-F-19). In accordance with this evaluation, the verification sampling results support a reclassification of this site to Interim Closed Out. The results of verification sampling show that residual contaminant concentrations do not preclude any future uses and allow for unrestricted use of shallow zone soils. The results also demonstrate that residual contaminant concentrations are protective of groundwater and the Columbia River

A case study of optimization in the decision process: Siting groundwater monitoring wells

International Nuclear Information System (INIS)

Cardwell, H.; Huff, D.; Douthitt, J.; Sale, M.

1993-12-01

Optimization is one of the tools available to assist decision makers in balancing multiple objectives and concerns. In a case study of the siting decision for groundwater monitoring wells, we look at the influence of the optimization models on the decisions made by the responsible groundwater specialist. This paper presents a multi-objective integer programming model for determining the location of monitoring wells associated with a groundwater pump-and-treat remediation. After presenting the initial optimization results, we analyze the actual decision and revise the model to incorporate elements of the problem that were later identified as important in the decision-making process. The results of a revised model are compared to the actual siting plans, the recommendations from the initial optimization runs, and the initial monitoring network proposed by the decision maker

Establishment of a Cost-Effective and Robust Planning Basis for the Processing of M-91 Waste at the Hanford Site

International Nuclear Information System (INIS)

Johnson, Wayne L.; Parker, Brian M.

2004-01-01

This report identifies and evaluates viable alternatives for the accelerated processing of Hanford Site transuranic (TRU) and mixed low-level wastes (MLLW) that cannot be processed using existing site capabilities. Accelerated processing of these waste streams will lead to earlier reduction of risk and considerable life-cycle cost savings. The processing need is to handle both oversized MLLW and TRU containers as well as containers with surface contact dose rates greater than 200 mrem/hr. This capability is known as the ''M-91'' processing capability required by the Tri-Party Agreement milestone M-91--01. The new, phased approach proposed in this evaluation would use a combination of existing and planned processing capabilities to treat and more easily manage contact-handled waste streams first and would provide for earlier processing of these wastes

Site Effect Assessment of Earthquake Ground Motion Based on Advanced Data Processing of Microtremor Array Measurements

Science.gov (United States)

Liu, L.; He, K.; Mehl, R.; Wang, W.; Chen, Q.

2008-12-01

High-resolution near-surface geologic information is essential for earthquake ground motion prediction. The near-surface geology forms the critical constituent to influence seismic wave propagation, which is known as the local site effects. We have collected microtremor data over 1000 sites in Beijing area for extracting the much needed earthquake engineering parameters (primarily sediment thickness, with the shear wave velocity profiling at a few important control points) in this heavily populated urban area. Advanced data processing algorithms are employed in various stages in assessing the local site effect on earthquake ground motion. First, we used the empirical mode decomposition (EMD), also known as the Hilbert-Huang transform (HHT), to enhance the microtremor data analysis by excluding the local transients and continuous monochromic industrial noises. With this enhancement we have significantly increased the number of data points to be useful in delineating sediment thickness in this area. Second, we have used the cross-correlation of microtremor data acquired for the pairs of two adjacent sites to generate a 'pseudo-reflection' record, which can be treated as the Green function of the 1D layered earth model at the site. The sediment thickness information obtained this way is also consistent with the results obtained by the horizontal to vertical spectral ratio method (HVSR). For most sites in this area, we can achieve 'self consistent' results among different processing skechems regarding to the sediment thickness - the fundamental information to be used in assessing the local site effect. Finally, the pseudo-spectral time domain method was used to simulate the seismic wave propagation caused by a scenario earthquake in this area - the 1679 M8 Sanhe-pinggu earthquake. The characteristics of the simulated earthquake ground motion have found a general correlation with the thickness of the sediments in this area. And more importantly, it is also in agreement

Pathways analyses and their role in the decision making process for selection of low-level waste disposal sites

International Nuclear Information System (INIS)

Pin, F.G.; Oblow, E.M.

1985-01-01

Pathways analyses have been extensively used to evaluate the suitability of proposed sites for disposal of low-level radioactive waste. The analyses rely on conservative scenarios to describe potential human exposure to the waste. Conceptual and numerical models are used to simulate the long-term transport of contamination to man and additional conservatism generally is built into the analysis when assumptions concerning future events have to be made or when uncertainties concerning site or waste characteristics exist. This conservatism is useful in ascertaining whether the site provides an adequate buffer to persons outside the site boundary. In reaching conclusions concerning site capacity and site acceptability, however, considerations must be given to the uncertainties involved in the analysis. Analytical methods to quantitatively assess the sensitivity of the results to data uncertainties may prove useful in the decision making process for site suitability. 7 references, 1 figure

Finding of No Significant Impact, proposed remediation of the Maybell Uranium Mill Processing Site, Maybell, Colorado

International Nuclear Information System (INIS)

1995-01-01

The U.S. Department of Energy (DOE) has prepared an environmental assessment (EA) (DOE/EA-0347) on the proposed surface remediation of the Maybell uranium mill processing site in Moffat County, Colorado. The mill site contains radioactively contaminated materials from processing uranium ore that would be stabilized in place at the existing tailings pile location. Based on the analysis in the EA, DOE has determined that the proposed action does not constitute a major federal action significantly affecting the quality of the human environment within the meaning of the National Environmental Policy Act (NEPA) of 1969, Public Law 91-190 (42 U.S.C. section 4321 et seq.), as amended. Therefore, preparation of an environmental impact statement is not required and DOE is issuing this Finding of No Significant Impact (FONSI)

Ferromanganese nodules from MANOP Sites H, S, and R-Control of mineralogical and chemical composition by multiple accretionary processes

Science.gov (United States)

Dymond, J.; Lyle, M.; Finney, B.; Piper, D.Z.; Murphy, K.; Conard, R.; Pisias, N.

1984-01-01

The chemical composition of ferromanganese nodules from the three nodule-bearing MANOP sites in the Pacific can be accounted for in a qualitative way by variable contributions of distinct accretionary processes. These accretionary modes are: 1. (1) hydrogenous, i.e., direct precipitation or accumulation of colloidal metal oxides in seawater, 2. (2) oxic diagenesis which refers to a variety of ferromanganese accretion processes occurring in oxic sediments; and 3. (3) suboxic diagenesis which results from reduction of Mn+4 by oxidation of organic matter in the sediments. Geochemical evidence suggests processes (1) and (2) occur at all three MANOP nodule-bearing sites, and process (3) occurs only at the hemipelagic site, H, which underlies the relatively productive waters of the eastern tropical Pacific. A normative model quantitatively accounts for the variability observed in nearly all elements. Zn and Na, however, are not well explained by the three end-member model, and we suggest that an additional accretionary process results in greater variability in the abundances of these elements. Variable contributions from the three accretionary processes result in distinct top-bottom compositional differences at the three sites. Nodule tops from H are enriched in Ni, Cu, and Zn, instead of the more typical enrichments of these elements in nodule bottoms. In addition, elemental correlations typical of most pelagic nodules are reversed at site H. The three accretionary processes result in distinct mineralogies. Hydrogenous precipitation produces ??MnO2. Oxic diagenesis, however, produces Cu-Ni-rich todorokite, and suboxic diagenesis results in an unstable todorokite which transforms to a 7 A?? phase ("birnessite") upon dehydration. The presence of Cu and Ni as charge-balancing cations influence the stability of the todorokite structure. In the bottoms of H nodules, which accrete dominantly by suboxic diagenesis, Na+ and possibly Mn+2 provide much of the charge balance for

Site Suitability Analysis for Beekeeping via Analythical Hyrearchy Process, Konya Example

Science.gov (United States)

Sarı, F.; Ceylan, D. A.

2017-11-01

Over the past decade, the importance of the beekeeping activities has been emphasized in the field of biodiversity, ecosystems, agriculture and human health. Thus, efficient management and deciding correct beekeeping activities seems essential to maintain and improve productivity and efficiency. Due to this importance, considering the economic contributions to the rural area, the need for suitability analysis concept has been revealed. At this point, Multi Criteria Decision Analysis (MCDA) and Geographical Information Systems (GIS) integration provides efficient solutions to the complex structure of decision- making process for beekeeping activities. In this study, site suitability analysis via Analytical Hierarchy Process (AHP) was carried out for Konya city in Turkey. Slope, elevation, aspect, distance to water resources, roads and settlements, precipitation and flora criteria are included to determine suitability. The requirements, expectations and limitations of beekeeping activities are specified with the participation of experts and stakeholders. The final suitability map were validated with existing 117 beekeeping locations and Turkish Statistical Institute 2016 beekeeping statistics for Konya province.

Lightning protection for the process canyons at the Savannah River site

International Nuclear Information System (INIS)

McAfee, D.E.

1995-01-01

Westinghouse Savannah River Company (WSRC) has performed Lightning Studies for the existing Process Canyons at the Savannah River Site (SRS). These studies were initiated to verify the lightning protection systems for the facilities and to compare the installations to the National Fire Protection (NFPA) Standard 780, Lighting Protection Code, 1992. The original study of the F-Canyon was initiated to develop answers to concerns raised by the Defense Nuclear Facility Safety Board (DNFSB). Once this study was completed it was determined that a similar study for H-Canyon would be prudent; followed by an evaluation of the Defense Waste Processing Facility (DWPF) Vitrification Building (S-Canyon). This paper will provide an overview of the nature of lightning and the principals of lightning protection. This will provide the reader with a basic understanding of the phenomena of lighting and its potential for damaging structures, components, and injuring personnel in or near the structure

Site Transition Process Upon Cleanup Completion. Fact Sheet

International Nuclear Information System (INIS)

2009-01-01

After environmental remediation is completed at a site and there is no continuing mission, responsibility for the site and the associated records are transferred to the U.S. Department of Energy (DOE) Office of Legacy Management for post-closure management. Where residual hazards (e.g., disposal cells, ground water contamination) remain, active long-term surveillance and maintenance will be required to ensure protection of human health and the environment

Establishment of a Cost-Effective and Robust Planning Basis for the Processing of M-91 Waste at the Hanford Site

Energy Technology Data Exchange (ETDEWEB)

Johnson, Wayne L.; Parker, Brian M.

2004-07-30

This report identifies and evaluates viable alternatives for the accelerated processing of Hanford Site transuranic (TRU) and mixed low-level wastes (MLLW) that cannot be processed using existing site capabilities. Accelerated processing of these waste streams will lead to earlier reduction of risk and considerable life-cycle cost savings. The processing need is to handle both oversized MLLW and TRU containers as well as containers with surface contact dose rates greater than 200 mrem/hr. This capability is known as the ''M-91'' processing capability required by the Tri-Party Agreement milestone M-91--01. The new, phased approach proposed in this evaluation would use a combination of existing and planned processing capabilities to treat and more easily manage contact-handled waste streams first and would provide for earlier processing of these wastes.

The decision-making process and EIA in connection with the siting of nuclear waste facilities - a municipal perspective

Energy Technology Data Exchange (ETDEWEB)

Carlsson, Torsten [Oskarshamn Municipality (Sweden)

1995-12-01

Past experiences from siting of nuclear facilities at Oskarshamn, Sweden are reviewed. This siting were carried out in a traditional manner for that time, i e it was decided to locate the facility at a particular site, then this decision was made public, and finally the decision was defended. New plans now exists for locating nuclear waste facilities to Oskarshamn, and this contribution discusses what the local communities demand from the EIA and EIS processes for producing a meaningful basis for decision-making. 9 refs.

Remedial action standards for inactive uranium processing sites (40 cfr 192). Draft environmental impact statement

International Nuclear Information System (INIS)

1980-12-01

The Environmental Protection Agency is proposing standards for disposing of uranium mill tailings from inactive processing sites and for cleaning up contaminated open land and buildings. These standards were developed pursuant to the Uranium Mill Tailings Radiation Control Act of 1978 (Public Law 95-604). This Act requires EPA to promulgate standards to protect the environment and public health and safety from radioactive and nonradioactive hazards posed by uranium mill tailings at designated inactive processing sites. The Draft Environmental Impact Statement examines health, technical, cost, and other factors relevant to determining standards. The proposed standards for disposal of the tailings piles cover radon emissions from the tailings to the air, protection of surface and ground water from radioactive and nonradioactive contaminants, and the length of time the disposal system should provide a reasonable expectation of meeting these standards. The proposed cleanup standards limit indoor radon decay product concentrations and gamma radiation levels and the residual radium concentration of contaminated land after cleanup

Global Production Planning Process considering the Supply Risk of Overseas Manufacturing Sites

Directory of Open Access Journals (Sweden)

Hosang Jung

2015-01-01

Full Text Available Although global manufacturers can produce most of their final products in local plants, they need to source components or parts from desirable overseas manufacturing partners at low cost in order to fulfill customer orders. In this global manufacturing environment, capacity information for planning is usually imprecise owing to the various risks of overseas plants (e.g., foreign governments’ policies and labor stability. It is therefore not easy for decision-makers to generate a global production plan showing the production amounts at local plants and overseas manufacturing facilities operated by manufacturing partners. In this paper, we present a new global production planning process considering the supply risk of overseas manufacturing sites. First, local experts estimate the supply capacity of an overseas plant using their judgment to determine when the risk could occur and how large the risk impact would be. Next, we run a global production planning model with the estimated supply capacities. The proposed process systematically adopts the qualitative judgments of local experts in the global production planning process and thus can provide companies with a realistic global production plan. We demonstrate the applicability of the proposed process with a real world case.

Interrelation of technologies for RW preparation and sites for final isolation of the wastes from pyrochemical processing of SNF

Energy Technology Data Exchange (ETDEWEB)

Gupalo, V.S.; Chistyakov, V.N. [JSC - Design-Prospecting and Scientific-Research Institute of Industrial Technology -, Kashirskoye Highway, 33, Moscow 115409 (Russian Federation); Kormilitsyn, M.V.; Kormilitsyna, L.A. [JSC - State Scientific Center - Research Institute of Atomic Reactors -, Ulyanovsk region, Dimitrovgrad - 10, 433510 (Russian Federation)

2013-07-01

For the justification of engineering solutions and practical testing of the radiochemical component of the perspective nuclear power complex with on-site variant of nuclear fuel cycle (NFC), it is planned to establish a multi-functional research-development complex (MFCRC) for radiochemical processing of spent nuclear fuels (SNF) from fast reactors. MFCRC is being established at the NIIAR site, it comprises technological process lines, where innovation pyro-electrochemical and hydrometallurgical technologies are realized, with an option for closing the inter-chain material flows for testing the combined radiochemically converted materials. The technological flowchart for processing at the MFCRC is subdivided into 3 segments: -) complex of the lead operations for dismantling the fuel elements (FE) and fuel assemblies (FA), -) pyrochemical extraction flowchart for processing SNF, and -) hydrometallurgical flowchart for processing SNF. The engineered solutions for the management and disposition of the radioactive wastes from MFCRC are reviewed.

Data Validation Package, December 2015, Groundwater and Surface Water Sampling at the Monument Valley, Arizona, Processing Site March 2016

Energy Technology Data Exchange (ETDEWEB)

Tyrrell, Evan [Navarro Research and Engineering, Inc., Oak Ridge, NV (United States); Denny, Angelita [USDOE Office of Legacy Management, Washington, DC (United States)

2016-03-23

Fifty-two groundwater samples and one surface water sample were collected at the Monument Valley, Arizona, Processing Site to monitor groundwater contaminants for evaluating the effectiveness of the proposed compliance strategy as specified in the 1999 Final Site Observational Work Plan for the UMTRA Project Site at Monument Valley, Arizona. Sampling and analyses were conducted as specified in the Sampling and Analysis Plan for U.S. Department of Energy Office of Legacy Management Sites (LMS/PRO/S04351, continually updated, http://energy.gov/lm/downloads/sampling-and-analysis-plan-us-department- energy-office-legacy-management-sites). Samples were collected for metals, anions, nitrate + nitrite as N, and ammonia as N analyses at all locations.

Fate and transport processes controlling the migration of hazardous and radioactive materials from the Area 5 Radioactive Waste Management Site (RWMS)

International Nuclear Information System (INIS)

Estrella, R.

1994-10-01

Desert vadose zones have been considered as suitable environments for the safe and long-term isolation of hazardous wastes. Low precipitation, high evapotranspiration and thick unsaturated alluvial deposits commonly found in deserts make them attractive as waste disposal sites. The fate and transport of any contaminant in the subsurface is ultimately determined by the operating retention and transformation processes in the system and the end result of the interactions among them. Retention (sorption) and transformation are the two major processes that affect the amount of a contaminant present and available for transport. Retention processes do not affect the total amount of a contaminant in the soil system, but rather decrease or eliminate the amount available for transport at a given point in time. Sorption reactions retard the contaminant migration. Permanent binding of solute by the sorbent is also possible. These processes and their interactions are controlled by the nature of the hazardous waste, the properties of the porous media and the geochemical and environmental conditions (temperature, moisture and vegetation). The present study summarizes the available data and investigates the fate and transport processes that govern the migration of contaminants from the Radioactive Waste Management Site (RWMS) in Area 5 of the Nevada Test Site (NTS). While the site is currently used only for low-level radioactive waste disposal, past practices have included burial of material now considered hazardous. Fundamentals of chemical and biological transformation processes are discussed subsequently, followed by a discussion of relevant results

Fate and transport processes controlling the migration of hazardous and radioactive materials from the Area 5 Radioactive Waste Management Site (RWMS)

Energy Technology Data Exchange (ETDEWEB)

Estrella, R.

1994-10-01

Desert vadose zones have been considered as suitable environments for the safe and long-term isolation of hazardous wastes. Low precipitation, high evapotranspiration and thick unsaturated alluvial deposits commonly found in deserts make them attractive as waste disposal sites. The fate and transport of any contaminant in the subsurface is ultimately determined by the operating retention and transformation processes in the system and the end result of the interactions among them. Retention (sorption) and transformation are the two major processes that affect the amount of a contaminant present and available for transport. Retention processes do not affect the total amount of a contaminant in the soil system, but rather decrease or eliminate the amount available for transport at a given point in time. Sorption reactions retard the contaminant migration. Permanent binding of solute by the sorbent is also possible. These processes and their interactions are controlled by the nature of the hazardous waste, the properties of the porous media and the geochemical and environmental conditions (temperature, moisture and vegetation). The present study summarizes the available data and investigates the fate and transport processes that govern the migration of contaminants from the Radioactive Waste Management Site (RWMS) in Area 5 of the Nevada Test Site (NTS). While the site is currently used only for low-level radioactive waste disposal, past practices have included burial of material now considered hazardous. Fundamentals of chemical and biological transformation processes are discussed subsequently, followed by a discussion of relevant results.

Geochemical and radiological characterization of soils from former radium processing sites.

Science.gov (United States)

Landa, E R

1984-02-01

Soil samples were collected from former radium processing sites in Denver, CO, and East Orange, NJ. Particle-size separations and radiochemical analyses of selected samples showed that while the greatest contents of both 226Ra and U were generally found in the finest (less than 45 micron) fraction, the pattern was not always of progressive increase in radionuclide content with decreasing particle size. Leaching tests on these samples showed a large portion of the 226Ra and U to be soluble in dilute hydrochloric acid. Radon-emanation coefficients measured for bulk samples of contaminated soil were about 20%. Recovery of residual uranium and vanadium, as an adjunct to any remedial action program, appears unlikely due to economic considerations.

Ecological studies related to construction of the Defense Waste Processing Facility on the Savannah River Site

Energy Technology Data Exchange (ETDEWEB)

Pechmann, J.H.K.; Scott, D.E.; McGregor, J.H.; Estes, R.A.; Chazal, A.C.

1993-02-01

The Defense Waste Processing Facility (DWPF) was built on the Savannah River Site (SRS) during the mid-1980's. The Savannah River Ecology Laboratory (SREL) has completed 12 years of ecological studies related to the construction of the DWPF complex. Prior to construction, the 600-acre site (S-Area) contained a Carolina bay and the headwaters of a stream. Research conducted by the SREL has focused primarily on four questions related to these wetlands: (1) Prior to construction, what fauna and flora were present at the DWPF site and at similar, yet undisturbed, alternative sites (2) By comparing the Carolina bay at the DWPF site (Sun Bay) with an undisturbed control Carolina bay (Rainbow Bay), what effect is construction having on the organisms that inhabited the DWPF site (3) By comparing control streams with streams on the periphery of the DWPF site, what effect is construction having on the peripheral streams (4) How effective have efforts been to lessen the impacts of construction, both with respect to erosion control measures and the construction of refuge ponds'' as alternative breeding sites for amphibians that formerly bred at Sun Bay Through the long-term census-taking of biota at the DWPF site and Rainbow Bay, SREL has begun to evaluate the impact of construction on the biota and the effectiveness of mitigation efforts. Similarly, the effects of erosion from the DWPF site on the water quality of S-Area peripheral streams are being assessed. This research provides supporting data relevant to the National Environmental Policy Act (NEPA) of 1969, the Endangered Species Act of 1973, Executive Orders 11988 (Floodplain Management) and 11990 (Protection of Wetlands), and United States Department of Energy (DOE) Guidelines for Compliance with Floodplain/Wetland Environmental Review Requirements (10CFR1022).

SITE SUITABILITY ANALYSIS FOR BEEKEEPING VIA ANALYTHICAL HYREARCHY PROCESS, KONYA EXAMPLE

Directory of Open Access Journals (Sweden)

F. Sarı

2017-11-01

Full Text Available Over the past decade, the importance of the beekeeping activities has been emphasized in the field of biodiversity, ecosystems, agriculture and human health. Thus, efficient management and deciding correct beekeeping activities seems essential to maintain and improve productivity and efficiency. Due to this importance, considering the economic contributions to the rural area, the need for suitability analysis concept has been revealed. At this point, Multi Criteria Decision Analysis (MCDA and Geographical Information Systems (GIS integration provides efficient solutions to the complex structure of decision- making process for beekeeping activities. In this study, site suitability analysis via Analytical Hierarchy Process (AHP was carried out for Konya city in Turkey. Slope, elevation, aspect, distance to water resources, roads and settlements, precipitation and flora criteria are included to determine suitability. The requirements, expectations and limitations of beekeeping activities are specified with the participation of experts and stakeholders. The final suitability map were validated with existing 117 beekeeping locations and Turkish Statistical Institute 2016 beekeeping statistics for Konya province.

Strategies for the decision process of siting radioactive waste repositories concerning communication and interaction with the society

International Nuclear Information System (INIS)

Almeida, Ivan Pedro Salati de

2009-01-01

The objective of this paper is to discuss the strategies to be followed in the siting and construction process of radioactive waste repositories considering the communication and relationship with the society. The paper analyzes the prospective advantages and disadvantages of each type of strategy. The strategies can be classified under three different types: 'define, announce and defend' strategy (also called DAD), participative strategy and spontaneous candidacy of host community. Up to the 90s the most common way of construct repositories was the DAD strategy. This type of strategy, despite of some cases of success, is gradually facing opposition in democratic regimes. Examples of failure are the first attempt to construct the Hungarian repository from 1982 to 1990; the French attempt of the construction of high and intermediate waste repository from 1987 to 1989 (both cancelled and substituted by the participative approach) and even the recent discussion to freeze the implantation of the Yucca Mountain repository in United States. The participative strategy has been preferred currently by most of the new repositories projects. Examples are the second attempt in Hungary, the construction of a repository in Slovenia and in the United Kingdom. The participative strategy has the disadvantage of greater expenses at the beginning of the process until the site of the repository is defined. This occurs because the body responsible for the construction has to deal with several potential candidates and spend time and money in the communication and participation process until the definition of the site by technical, economical and social criteria. On the other hand, this process decreases the risk of rejection by the local population. The spontaneous candidacy strategy was also analyzed and it is shown it has some similarities with the participative strategy but hides new risks in the process. (author)

World Nuclear Association (WNA) internationally standardized reporting (checklist) on the sustainable development performance of uranium mining and processing sites

International Nuclear Information System (INIS)

Harris, F.

2014-01-01

The World Nuclear Association (WNA) has developed internationally standardized reporting (‘Checklist’) for uranium mining and processing sites. This reporting is to achieve widespread utilities/miners agreement on a list of topics/indicators for common use in demonstrating miners’ adherence to strong sustainable development performance. Nuclear utilities are often required to evaluate the sustainable development performance of their suppliers as part of a utility operational management system. In the present case, nuclear utilities are buyers of uranium supplies from uranium miners and such purchases are often achieved through the utility uranium or fuel supply management function. This Checklist is an evaluation tool which has been created to collect information from uranium miners’ available annual reports, data series, and measurable indicators on a wide range of sustainable development topics to verify that best practices in this field are implemented throughout uranium mining and processing sites. The Checklist has been developed to align with the WNA’s policy document Sustaining Global Best Practices in Uranium Mining and Processing: Principles for Managing Radiation, Health and Safety, and Waste and the Environment which encompasses all applicable aspects of sustainable development to uranium mining and processing. The eleven sections of the Checklist are: 1. Adherence to Sustainable Development; 2. Health, Safety and Environmental Protection; 3. Compliance; 4. Social Responsibility and Stakeholder Engagement; 5. Management of Hazardous Materials; 6. Quality Management Systems; 7. Accidents and Emergencies; 8. Transport of Hazardous Materials; 9. Systematic Approach to Training; 10. Security of Sealed Radioactive Sources and Nuclear Substances; 11. Decommissioning and Site Closure. The Checklist benefits from many years of nuclear utility experience in verifying the sustainable development performance of uranium mining and processing sites. This

Siting of a low-level radioactive waste management facility - environmental assessment experiences of the Canadian siting task force

International Nuclear Information System (INIS)

Gorber, D.M.; Story, V.A.

1995-01-01

After public opposition to the plans for a low-level radioactive waste facility at one of two candidate areas at Port Hope, Canada the Environmental Assessment process was postponed, and an independent Siting Process Task Force was set-up to assess the most suitable technologies for LLRW disposal, the areas with the best potential in the province to use these technologies, and the most promising approaches to site selection. The Task Force recommended a five-phased siting process known as the 'Co-operative Siting Process', which was based on the voluntary participation of local communities and a collaborative, joint-planning style of decision making. An independent Siting Task Force was to be established to ensure that the principles of the recommended process was upheld. This siting process is still underway, and problems and successes that have been encountered are summarized in this contribution

The influence on the environment of uranium ore transport from mining sites to processing site in Romania

International Nuclear Information System (INIS)

Peic, T.; Banciu, O.; Bardan, N.; Radulescu, C.

1997-01-01

In Romania, the transport of uranium ores from mining sites to the processing plant is carried out by road and rail. The length of the road transport routes is between 5 and 45 km and rail routes between 300 and 500 km. This laboratory began to monitor these transport routes in 1984. Gamma dose rate measurements were made on and around the special wagons and trucks along the road and rail transport routes and in railway stations. Soil and vegetation samples have also been collected along the road and rail transport routes and in railway stations. From the collected samples the specific activity of natural uranium and 226 Ra were measured. The level of natural radioactivity in the train assembling stations in the period 1984-1996, increased 1-4 times in comparison with the natural background. (Author)

New treatment facility for low level process effluents at the Savannah River site

International Nuclear Information System (INIS)

Ebra, M.A.; Bibler, J.P.; Johnston, B.S.; Kilpatrick, L.L.; Poy, F.L.; Wallace, R.M.

1987-01-01

A new facility, the F/H Effluent Treatment Facility (F/H ETF) is under construction at the Savannah River site. It will decontaminate process effluents containing low levels of radionuclides and hazardous chemicals prior to discharge to a surface stream. These effluents, which are currently discharged to seepage basins, originate in the chemical separations and high-level radioactive waste processing areas, known as F-Area and H-Area. The new facility will allow closure of the basins in order to meet the provisions of the Resource Conservation and Recovery Act by November 1988. A high degree of reliability is expected from this design as a result of extensive process development work that has been conducted at the Savannah River Laboratory. This work has included both bench scale testing of individual unit operations and pilot scale testing of an integrated facility, 150 to 285 L/min (40 to 75 gpm), that contains the major operations

Critical Protection Item classification for a waste processing facility at Savannah River Site

International Nuclear Information System (INIS)

Ades, M.J.; Garrett, R.J.

1993-01-01

This paper describes the methodology for Critical Protection Item (CPI) classification and its application to the Structures, Systems and Components (SSC) of a waste processing facility at the Savannah River Site (SRS). The WSRC methodology for CPI classification includes the evaluation of the radiological and non-radiological consequences resulting from postulated accidents at the waste processing facility and comparison of these consequences with allowable limits. The types of accidents considered include explosions and fire in the facility and postulated accidents due to natural phenomena, including earthquakes, tornadoes, and high velocity straight winds. The radiological analysis results indicate that CPIs are not required at the waste processing facility to mitigate the consequences of radiological release. The non-radiological analysis, however, shows that the Waste Storage Tank (WST) and the dike spill containment structures around the formic acid tanks in the cold chemical feed area and waste treatment area of the facility should be identified as CPIs. Accident mitigation options are provided and discussed

Heavy metal contamination in soils and vegetables near an e-waste processing site, South China.

Science.gov (United States)

Luo, Chunling; Liu, Chuanping; Wang, Yan; Liu, Xiang; Li, Fangbai; Zhang, Gan; Li, Xiangdong

2011-02-15

Environmental pollution due to uncontrolled e-waste recycling activities has been reported in a number of locations of China. In the present study, metal pollution to the surrounding environment from a primitive e-waste processing facility was investigated. Soils at sites where e-waste is burned in the open air, those of surrounding paddy fields and vegetable gardens, as well as common vegetable samples were collected and analyzed for heavy metals. The results showed that the soils of former incineration sites had the highest concentrations of Cd, Cu, Pb, and Zn with mean values of 17.1, 11,140, 4500, and 3690 mg kg(-1), respectively. The soils of nearby paddy fields and vegetable gardens also had relatively high concentrations of Cd and Cu. In the edible tissues of vegetables, the concentrations of Cd and Pb in most samples exceeded the maximum level permitted for food in China. Sequential leaching tests revealed that the Cu, Pb, and Zn were predominantly associated with the residual fraction, followed by the carbonate/specifically adsorbed phases with the exception of Cd, which was mainly in the extractable form in paddy fields and vegetable soils. The data showed that uncontrolled e-waste processing operations caused serious pollution to local soils and vegetables. The cleaning up of former incineration sites should be a priority in any future remediation program. Copyright © 2010 Elsevier B.V. All rights reserved.

OPERATIONS REVIEW OF THE SAVANNAH RIVER SITE INTEGRATED SALT DISPOSITION PROCESS - 11327

Energy Technology Data Exchange (ETDEWEB)

Peters, T.; Poirier, M.; Fondeur, F.; Fink, S.; Brown, S.; Geeting, M.

2011-02-07

The Savannah River Site (SRS) is removing liquid radioactive waste from its Tank Farm. To treat waste streams that are low in Cs-137, Sr-90, and actinides, SRS developed the Actinide Removal Process and implemented the Modular Caustic Side Solvent Extraction (CSSX) Unit (MCU). The Actinide Removal Process contacts salt solution with monosodium titanate to sorb strontium and select actinides. After monosodium titanate contact, the resulting slurry is filtered to remove the monosodium titanate (and sorbed strontium and actinides) and entrained sludge. The filtrate is transferred to the MCU for further treatment to remove cesium. The solid particulates removed by the filter are concentrated to {approx} 5 wt %, washed to reduce the sodium concentration, and transferred to the Defense Waste Processing Facility for vitrification. The CSSX process extracts the cesium from the radioactive waste using a customized solvent to produce a Decontaminated Salt Solution (DSS), and strips and concentrates the cesium from the solvent with dilute nitric acid. The DSS is incorporated in grout while the strip acid solution is transferred to the Defense Waste Processing Facility for vitrification. The facilities began radiological processing in April 2008 and started processing of the third campaign ('MarcoBatch 3') of waste in June 2010. Campaigns to date have processed {approx}1.2 million gallons of dissolved saltcake. Savannah River National Laboratory (SRNL) personnel performed tests using actual radioactive samples for each waste batch prior to processing. Testing included monosodium titanate sorption of strontium and actinides followed by CSSX batch contact tests to verify expected cesium mass transfer. This paper describes the tests conducted and compares results from facility operations. The results include strontium, plutonium, and cesium removal, cesium concentration, and organic entrainment and recovery data. Additionally, the poster describes lessons learned during

Inclusive assessment in a site-selection process. Approach, experience, reflections and some lessons beyond boundaries

Energy Technology Data Exchange (ETDEWEB)

Flueeler, Thomas [Directorate of Public Works, Nuclear Technology Unit, Zurich (Switzerland). Energy Dept.; ETH Zurich (Switzerland). Inst. for Environmental Decisions

2015-07-01

Nuclear waste disposal indisputably is a controversial socio-technical issue in most societies widely using nuclear technology. All the more it is pivotal to proceed in a comprehensive, transparent and participative manner. The contribution suggests fundamental rules to follow and confronts them with the currently ongoing site-selection process in Switzerland. Finally it draws some lessons for the audience.

Remediation of 20,000 m3 of hydrocarbon-impacted soil at a former well site using the biopile process

Energy Technology Data Exchange (ETDEWEB)

Bedard, G. [Biogenie Inc., Calgary, AB (Canada)

2006-07-01

The remediation of 20,000 m{sup 3} of hydrocarbon-impacted soil at a former well site using the biopile process was discussed. The site involved was an abandoned site located southwest from Red Deer, Alberta in an agricultural area. The presentation provided background on the site history and discussed an additional site assessment. The objectives of this assessment were to complete the delineation of the hydrocarbon plume; confirm the depth of impact identified in a previous environmental assessment; and, select the most efficient remediation strategy. The presentation also discussed findings of the Environmental Services Association (ESA). Site specific challenges that were addressed included proximity of land owners; lease slopes to a nearby river; large volume of impacted material; depth of impact; limited space available on-site; high concentrations of petroleum hydrocarbons (PHCs); segregation of impacted soil; and winter installation and start-up. The proposed strategy and its advantages as well as the methodology for the remediation strategy were all discussed. 5 tabs., 5 figs.

General aspects of siting and safety considerations

International Nuclear Information System (INIS)

Rutgers, E.

1980-01-01

The siting process from site selection to the different stages of review by the regulatory body is described. Special attention is payed to the role and responsibilities of the licensing authority. Next, the basic considerations involved in the siting process are reviewed. They include system planning, engineering, safety, environmental impact (including land use) and economics. Case studies illustrating different aspects of the siting process (e.g. site selection) are presented. (orig.)

Surface and subsurface cleanup protocol for radionuclides, Gunnison, Colorado, UMTRA project processing site: Final

International Nuclear Information System (INIS)

1994-01-01

Thorium 230 (Th-230) at the Gunnison, Colorado processing site will require remediation, however, a seasonally fluctuating groundwater table at the site significantly complicates conventional remedial action with respect to cleanup. Therefore, to effectively remediate the site with respect to Radium 226 (Ra-226) and Th-230, the following supplemental standard is proposed: In situ Ra-26 will be remediated to the EPA soil cleanup standards independent of groundwater considerations. In situ Th-230 concentrations will be remediated in the region above the encountered water table so the 1000-year projected Ra-226 concentration complies with the EPA soil cleanup concentration limits. If elevated Th-230 persists to the water table, an additional foot of excavation will be performed and the grid will be backfilled. Excavated grids will be backfilled to the final remedial action grade with clean cobbly soil. Final grid verification that is required below the water table will be performed by extracting and analyzing a single bulk soil sample with the bucket of a backhoe. Modeled surface radon flux values will be estimated and documented. A recommendation will be made that land records should be annotated to identify the presence of residual Th-230

Temelin 3,4 Siting

International Nuclear Information System (INIS)

Kubanova, Iva; Fuzer, Jiri

2011-01-01

In the future the Czech Republic will need new energetic resources in spite of current decrease of electricity consumption due to economical crisis. Nuclear power generation is considered as important part of energetic mix of the Czech Republic and this opinion is newly reflected in new government official statement issued in August 2010. CEZ, a. s. prepares new nuclear power plants projects accordingly governmental expectations. Currently 3 projects are in preparation. Temelin 3, 4 project is in the most advanced status, tender is in progress. Potential construction of Dukovany unit 5 and new Jaslovske Bohunice units are analyzed in feasibility studies. Temelin 3, 4 project activities were started 4 years ago. Preparatory analyses, market investigation, feasibility study including many particular studies were elaborated in years 2006-2008. Later on decision to work on bid invitation specification was done and followed. EIA process was started in July 2008 by Intention Announcement and continues. Public tender for EPC contract was announced in August 2009 and it is in progress accordingly schedule. Siting process is in the initial stage. EIA process started in July 2008 through Intention Announcement in spite of anti - nuclear political climate in the Czech Republic. EIA process is interstate process, Austria and Germany participate. Investigation Process Protocol was issued by Ministry of Environment in February 2009 with 34 main conditions and 165 additional comments, requirements, statements. CEZ, a. s. adopted the positive approach with philosophy to deal with all conditions and requirements properly. Elaboration of EIA documentation took 18 months. In May 2010 CEZ, a. s. handed over the EIA documentation to the Ministry of Environment and consequently all legal steps followed including hand-over of EIA documentation to Austria and Germany. In next weeks and months all comments will be gathered by Ministry of Environment and relevant decisions and legal steps

Site locality identification study: Hanford Site. Volume I. Methodology, guidelines, and screening

International Nuclear Information System (INIS)

1980-07-01

Presented in this report are the results of the site locality identification study for the Hanford Site using a screening process. To enable evaluation of the entire Hanford Site, the screening process was applied to a somewhat larger area; i.e., the Pasco Basin. The study consisted of a series of screening steps that progressively focused on smaller areas which are within the Hanford Site and which had a higher potential for containing suitable repository sites for nuclear waste than the areas not included for further study. Five site localities, designated H-1, H-2, H-3, H-4, H-5 (Figure A), varying in size from approximately 10 to 50 square miles, were identified on the Hanford Site. It is anticipated that each site locality may contain one or more candidate sites suitable for a nuclear waste repository. The site locality identification study began with definition of objectives and the development of guidelines for screening. Three objectives were defined: (1) maximize public health and safety; (2) minimize adverse environmental and socioeconomic impacts; and (3) minimize system costs. The screening guidelines have numerical values that provided the basis for the successive reduction of the area under study and to focus on smaller areas that had a higher likelihood of containing suitable sites

Remedial action and site design for stabilization of the inactive uranium mill tailings sites at Slick Rock, Colorado

International Nuclear Information System (INIS)

1993-07-01

The US Environmental Protection Agency (EPA) has established health and environmental protection regulations to correct and prevent groundwater contamination resulting from processing activities at inactive uranium milling sites (EPA, 1987). According to the Uranium Mill Tailings Radiation Control Act (UMTRCA) of 1978 Public Law (PL) 95-604 (PL 95-604), the US Department of Energy (DOE) is responsible for assessing the inactive uranium processing sites. The DOE has determined that for Slick Rock, this assessment shall include hydrogeologic site characterization for two separate uranium processing sites, the Union Carbide (UC) site and the North Continent (NC) site, and for the proposed Burro Canyon disposal site

Surface and subsurface cleanup protocol for radionuclides Gunnison, Colorado, UMTRA Project Processing Site

International Nuclear Information System (INIS)

1994-05-01

The supplemental standards provisions of Title 40, Code of Federal Regulations, Part 192 (40 CFR Part 192) require the cleanup of radionuclides other than radium-226 (Ra-226) to levels ''as low as reasonably achievable'' (ALARA), taking into account site-specific conditions, if sufficient quantities and concentrations are present to constitute a significant radiation hazard. In this context, thorium-230 (Th-230) at the Gunnison, Colorado, processing site will require remediation. However, a seasonally fluctuating groundwater table at the site significantly complicates conventional remedial action with respect to cleanup. Characterization data indicate that in the offpile areas, the removal of residual in situ bulk Ra-226 and Th-230 such that the 1000-year projected Ra-226 concentration (Ra-226 concentration in 1000 years due to the decay of in situ Ra-226 and the in-growth of Ra-226 from in situ Th-230) complies with the US Environmental Protection Agency (EPA) cleanup standard for in situ Ra-226 and the cleanup protocol for in situ Th-230 can be readily achieved using conventional excavation techniques for bulk contamination without encountering significant impacts due to groundwater. The EPA cleanup standard and criterion for Ra-226 and the 1000-year projected Ra-226 are 5 and 15 picocuries per gram (pCi/g) above background, respectively, averaged over 15-centimeter (cm) deep surface and subsurface intervals and 100-square-meter (m 2 ) grid areas. Significant differential migration of Th-230 relative to Ra-226 has occurred over 40 percent of the subpile area. To effectively remediate the site with respect to Ra-226 and Th-230, supplemental standard is proposed and discussed in this report

75 FR 71677 - Reimbursement for Costs of Remedial Action at Active Uranium and Thorium Processing Sites

Science.gov (United States)

2010-11-24

... DEPARTMENT OF ENERGY Reimbursement for Costs of Remedial Action at Active Uranium and Thorium... in FY 2011 from eligible active uranium and thorium processing site licensees for reimbursement under... approximately $24.3 million of Recovery Act funds available for reimbursement in FY 2011, as well as the $10...

Global site-specific analysis of glycoprotein N-glycan processing.

Science.gov (United States)

Cao, Liwei; Diedrich, Jolene K; Ma, Yuanhui; Wang, Nianshuang; Pauthner, Matthias; Park, Sung-Kyu Robin; Delahunty, Claire M; McLellan, Jason S; Burton, Dennis R; Yates, John R; Paulson, James C

2018-06-01

N-glycans contribute to the folding, stability and functions of the proteins they decorate. They are produced by transfer of the glycan precursor to the sequon Asn-X-Thr/Ser, followed by enzymatic trimming to a high-mannose-type core and sequential addition of monosaccharides to generate complex-type and hybrid glycans. This process, mediated by the concerted action of multiple enzymes, produces a mixture of related glycoforms at each glycosite, making analysis of glycosylation difficult. To address this analytical challenge, we developed a robust semiquantitative mass spectrometry (MS)-based method that determines the degree of glycan occupancy at each glycosite and the proportion of N-glycans processed from high-mannose type to complex type. It is applicable to virtually any glycoprotein, and a complete analysis can be conducted with 30 μg of protein. Here, we provide a detailed description of the method that includes procedures for (i) proteolytic digestion of glycoprotein(s) with specific and nonspecific proteases; (ii) denaturation of proteases by heating; (iii) sequential treatment of the glycopeptide mixture with two endoglycosidases, Endo H and PNGase F, to create unique mass signatures for the three glycosylation states; (iv) LC-MS/MS analysis; and (v) data analysis for identification and quantitation of peptides for the three glycosylation states. Full coverage of site-specific glycosylation of glycoproteins is achieved, with up to thousands of high-confidence spectra hits for each glycosite. The protocol can be performed by an experienced technician or student/postdoc with basic skills for proteomics experiments and takes ∼7 d to complete.

Site locality identification study: Hanford Site. Volume II. Data cataloging

International Nuclear Information System (INIS)

1980-07-01

Data compilation and cataloging for the candidate site locality identification study were conducted in order to provide a retrievable data cataloging system for the present siting study and future site evaluation and licensng processes. This task occurred concurrently with and also independently of other tasks of the candidate site locality identification study. Work in this task provided the data utilized primarily in the development and application of screening and ranking processes to identify candidate site localities on the Hanford Site. The overall approach included two steps: (1) data acquisition and screening; and (2) data compilation and cataloging. Data acquisition and screening formed the basis for preliminary review of data sources with respect to their probable utilization in the candidate site locality identification study and review with respect to the level of completeness and detail of the data. The important working assumption was that the data to be used in the study be based on existing and available published and unpublished literature. The data compilation and cataloging provided the basic product of the Task; a retrievable data cataloging system in the form of an annotated reference list and key word index and an index of compiled data. The annotated reference list and key word index are cross referenced and can be used to trace and retrieve the data sources utilized in the candidate site locality identification study

Selection of site specific vibration equation by using analytic hierarchy process in a quarry

Energy Technology Data Exchange (ETDEWEB)

Kalayci, Ulku, E-mail: ukalayci@istanbul.edu.tr; Ozer, Umit, E-mail: uozer@istanbul.edu.tr

2016-01-15

This paper presents a new approach for the selection of the most accurate SSVA (Site Specific Vibration Attenuation) equation for blasting processes in a quarry located near settlements in Istanbul, Turkey. In this context, the SSVA equations obtained from the same study area in the literature were considered in terms of distance between the shot points and buildings and the amount of explosive charge. In this purpose, 11 different SSVA equations obtained from the study area in the past 12 years, forecasting capabilities according to designated new conditions, using 102 vibration records as test data obtained from the study area was investigated. In this study, AHP (Analytic Hierarchy Process) was selected as an analysis method in order to determine the most accurate equation among 11 SSAV equations, and the parameters such as year, distance, charge, and r{sup 2} of the equations were used as criteria for AHP. Finally, the most appropriate equation was selected among the existing ones, and the process of selecting according to different target criteria was presented. Furthermore, it was noted that the forecasting results of the selected equation is more accurate than that formed using the test results. - Highlights: • The optimum Site Specific Vibration Attenuation equation for blasting in a quarry located near settlements was determined. • It is indicated that SSVA equations changing over the years don’t give always accurate estimates at changing conditions. • Selection of the blast induced SSVA equation was made using AHP. • Equation selection method was highlighted based on parameters such as charge, distance, and quarry geometry changes (year).

Selection of site specific vibration equation by using analytic hierarchy process in a quarry

International Nuclear Information System (INIS)

Kalayci, Ulku; Ozer, Umit

2016-01-01

This paper presents a new approach for the selection of the most accurate SSVA (Site Specific Vibration Attenuation) equation for blasting processes in a quarry located near settlements in Istanbul, Turkey. In this context, the SSVA equations obtained from the same study area in the literature were considered in terms of distance between the shot points and buildings and the amount of explosive charge. In this purpose, 11 different SSVA equations obtained from the study area in the past 12 years, forecasting capabilities according to designated new conditions, using 102 vibration records as test data obtained from the study area was investigated. In this study, AHP (Analytic Hierarchy Process) was selected as an analysis method in order to determine the most accurate equation among 11 SSAV equations, and the parameters such as year, distance, charge, and r"2 of the equations were used as criteria for AHP. Finally, the most appropriate equation was selected among the existing ones, and the process of selecting according to different target criteria was presented. Furthermore, it was noted that the forecasting results of the selected equation is more accurate than that formed using the test results. - Highlights: • The optimum Site Specific Vibration Attenuation equation for blasting in a quarry located near settlements was determined. • It is indicated that SSVA equations changing over the years don’t give always accurate estimates at changing conditions. • Selection of the blast induced SSVA equation was made using AHP. • Equation selection method was highlighted based on parameters such as charge, distance, and quarry geometry changes (year).

Simulation of the job processing performance at an ALICE Tier-2 site with MONARC

International Nuclear Information System (INIS)

Zach, C; Adamová, D; Betev, L

2011-01-01

The MONARC (MOdels of Networked Analysis at Regional Centers) framework has been developed and designed with the aim to provide a tool for realistic simulations of large scale distributed computing systems, with a special focus on the Grid systems of the experiments at the CERN LHC. In this paper, we describe a usage of the MONARC framework and tools for a simulation of the job processing performance at an ALICE Tier-2 site.

Sequence motif upstream of the Hendra virus fusion protein cleavage site is not sufficient to promote efficient proteolytic processing

International Nuclear Information System (INIS)

Craft, Willie Warren; Dutch, Rebecca Ellis

2005-01-01

The Hendra virus fusion (HeV F) protein is synthesized as a precursor, F 0 , and proteolytically cleaved into the mature F 1 and F 2 heterodimer, following an HDLVDGVK 109 motif. This cleavage event is required for fusogenic activity. To determine the amino acid requirements for processing of the HeV F protein, we constructed multiple mutants. Individual and simultaneous alanine substitutions of the eight residues immediately upstream of the cleavage site did not eliminate processing. A chimeric SV5 F protein in which the furin site was substituted for the VDGVK 109 motif of the HeV F protein was not processed but was expressed on the cell surface. Another chimeric SV5 F protein containing the HDLVDGVK 109 motif of the HeV F protein underwent partial cleavage. These data indicate that the upstream region can play a role in protease recognition, but is neither absolutely required nor sufficient for efficient processing of the HeV F protein

Old radioactive waste storage sites

International Nuclear Information System (INIS)

2008-01-01

After a recall of the regulatory context for the management of old sites used for the storage of radioactive wastes with respect with their activity, the concerned products, the disposal or storage type, this document describes AREVA's involvement in the radioactive waste management process in France. Then, for the different kinds of sites (currently operated sites having radioactive waste storage, storage sites for uranium mineral processing residues), it indicates their location and name, their regulatory status and their control authority, the reference documents. It briefly presents the investigation on the long term impact of uranium mineral processing residues on health and environment, evokes some aspects of public information transparency, and presents the activities of an expertise group on old uranium mines. The examples of the sites of Bellezane (uranium mineral processing residues) and COMURHEX Malvesi (assessment of underground and surface water quality at the vicinity of this installation) are given in appendix

Selection of radioactive waste disposal site considering natural processes

International Nuclear Information System (INIS)

Nakamura, H.

1991-01-01

To dispose the radioactive waste, it is necessary to consider the transfer of material in natural environment. The points of consideration are 1) Long residence time of water 2) Independence of biosphere from the compartment containing the disposal site in the natural hydrologic cycle 3) Dilution with the natural inactive isotope or the same group of elements. Isotope dilution for 129 I and 14 C can be expected by proper selection of the site. 241 Am and 239 Pu will be homogenized into soil or sediment with insoluble elements such as iron and aluminium. For 237 Np and 99 Tc anionic condition is important for the selection. From the point of view of hydrologic cycle, anoxic dead water zone avoiding beneath mountain area is preferable for the disposal site. (author)

Data Validation Package May 2016 Groundwater Sampling at the Lakeview, Oregon, Processing Site August 2016

Energy Technology Data Exchange (ETDEWEB)

Linard, Joshua [USDOE Office of Legacy Management, Washington, DC (United States); Hall, Steve [Navarro Research and Engineering, Inc., Oak Ridge, TN (United States)

2016-08-01

This biennial event includes sampling five groundwater locations (four monitoring wells and one domestic well) at the Lakeview, Oregon, Processing Site. For this event, the domestic well (location 0543) could not be sampled because no one was in residence during the sampling event (Note: notification was provided to the resident prior to the event). Per Appendix A of the Groundwater Compliance Action Plan, sampling is conducted to monitor groundwater quality on a voluntary basis. Sampling and analyses were conducted as specified in the Sampling and Analysis Plan for U.S. Department of Energy Office of Legacy Management Sites (LMS/PRO/S04351, continually updated). One duplicate sample was collected from location 0505. Water levels were measured at each sampled monitoring well. The constituents monitored at the Lakeview site are manganese and sulfate. Monitoring locations that exceeded the U.S. Environmental Protection Agency (EPA) Secondary Maximum Contaminant Levels for these constituents are listed in Table 1. Review of time-concentration graphs included in this report indicate that manganese and sulfate concentrations are consistent with historical measurements.

Quadruple-layered perovskite (CuCl)Ca2NaNb4O13

International Nuclear Information System (INIS)

Kitada, A.; Tsujimoto, Y.; Yamamoto, T.; Kobayashi, Y.; Narumi, Y.; Kindo, K.; Aczel, A.A.; Luke, G.M.; Uemura, Y.J.; Kiuchi, Y.; Ueda, Y.; Yoshimura, K.; Ajiro, Y.; Kageyama, H.

2012-01-01

We will present the synthesis, structure and magnetic properties of a new quadruple-layered perovskite (CuCl)Ca 2 NaNb 4 O 13 . Through a topotactic ion-exchange reaction with CuCl 2 , the precursor RbCa 2 NaNb 4 O 13 presumably having an incoherent octahederal tliting changes into (CuCl)Ca 2 NaNb 4 O 13 with a 2a p ×2a p ×2c p superstructure (tetragonal; a=7.73232(5) Å, c=39.2156(4) Å). The well-defined superstructure for the ion-exchanged product should be stabilized by the inserted CuCl 4 O 2 octahedral layers that firmly connect with neighboring perovskite layers. Magnetic studies show the absence of long-range magnetic ordering down to 2 K despite strong in-plane interactions. Aleksandrov′s group theory and Rietveld refinement of synchrotron X-ray diffraction data suggest the structure to be of I4/mmm space group with in-phase tilting along the a and b axes, a two-tilt system (++0). - Graphical Abstract: We present a quadruple-layered copper oxyhalide (CuCl)Ca 2 NaNb 4 O 13 synthesized through a topotactic ion-exchange reaction of RbCa 2 NaNb 4 O 13 with CuCl 2 . The compound has a well-defined superstructure. Magnetic studies suggest the absence of magnetic order even at 2 K. Highlights: ► (CuCl)Ca 2 NaNb 4 O 13 was prepared by ion-exchange reaction of RbCa 2 NaNb 4 O 13 with CuCl 2 . ► Compound has a 2a p ×2a p ×2c p superstructure (tetragonal; a=7.73 Å, c=39.21 Å). ► Such a well-defined superstructure was not observed in the precursor compound. ► Aleksandrov′s theory and Rietveld study suggest a (++0) octahedral tilting (I4/mmm). ► Magnetic studies revealed the absence of magnetic order down to 2 K.

Site survey for nuclear power plants

International Nuclear Information System (INIS)

1984-01-01

This Safety Guide describes the first stage of the siting process for nuclear power plants - the site survey to select one or more preferred candidate sites. Its purpose is to recommend procedures and provide information for use in implementing a part of the Code of Practice on Safety in Nuclear Power Plant Siting (IAEA Safety Series No.50-C-S). The organization, procedures, methodologies, guidance for documenting the site survey process and examples of detailed procedures on some safety-related site characteristics are given in the Guide

SITE PROGRAM DEMONSTRATION ECO LOGIC INTERNATIONAL GAS-PHASE CHEMICAL REDUCTION PROCESS, BAY CITY, MICHIGAN TECHNOLOGY EVALUATION REPORT

Science.gov (United States)

The SITE Program funded a field demonstration to evaluate the Eco Logic Gas-Phase Chemical Reduction Process developed by ELI Eco Logic International Inc. (ELI), Ontario, Canada. The Demonstration took place at the Middleground Landfill in Bay City, Michigan using landfill wa...

Radionuclide transfer in marine coastal ecosystems, a modelling study using metabolic processes and site data.

Science.gov (United States)

Konovalenko, L; Bradshaw, C; Kumblad, L; Kautsky, U

2014-07-01

This study implements new site-specific data and improved process-based transport model for 26 elements (Ac, Ag, Am, Ca, Cl, Cm, Cs, Ho, I, Nb, Ni, Np, Pa, Pb, Pd, Po, Pu, Ra, Se, Sm, Sn, Sr, Tc, Th, U, Zr), and validates model predictions with site measurements and literature data. The model was applied in the safety assessment of a planned nuclear waste repository in Forsmark, Öregrundsgrepen (Baltic Sea). Radionuclide transport models are central in radiological risk assessments to predict radionuclide concentrations in biota and doses to humans. Usually concentration ratios (CRs), the ratio of the measured radionuclide concentration in an organism to the concentration in water, drive such models. However, CRs vary with space and time and CR estimates for many organisms are lacking. In the model used in this study, radionuclides were assumed to follow the circulation of organic matter in the ecosystem and regulated by radionuclide-specific mechanisms and metabolic rates of the organisms. Most input parameters were represented by log-normally distributed probability density functions (PDFs) to account for parameter uncertainty. Generally, modelled CRs for grazers, benthos, zooplankton and fish for the 26 elements were in good agreement with site-specific measurements. The uncertainty was reduced when the model was parameterized with site data, and modelled CRs were most similar to measured values for particle reactive elements and for primary consumers. This study clearly demonstrated that it is necessary to validate models with more than just a few elements (e.g. Cs, Sr) in order to make them robust. The use of PDFs as input parameters, rather than averages or best estimates, enabled the estimation of the probable range of modelled CR values for the organism groups, an improvement over models that only estimate means. Using a mechanistic model that is constrained by ecological processes enables (i) the evaluation of the relative importance of food and water

Radionuclide transfer in marine coastal ecosystems, a modelling study using metabolic processes and site data

International Nuclear Information System (INIS)

Konovalenko, L.; Bradshaw, C.; Kumblad, L.; Kautsky, U.

2014-01-01

This study implements new site-specific data and improved process-based transport model for 26 elements (Ac, Ag, Am, Ca, Cl, Cm, Cs, Ho, I, Nb, Ni, Np, Pa, Pb, Pd, Po, Pu, Ra, Se, Sm, Sn, Sr, Tc, Th, U, Zr), and validates model predictions with site measurements and literature data. The model was applied in the safety assessment of a planned nuclear waste repository in Forsmark, Öregrundsgrepen (Baltic Sea). Radionuclide transport models are central in radiological risk assessments to predict radionuclide concentrations in biota and doses to humans. Usually concentration ratios (CRs), the ratio of the measured radionuclide concentration in an organism to the concentration in water, drive such models. However, CRs vary with space and time and CR estimates for many organisms are lacking. In the model used in this study, radionuclides were assumed to follow the circulation of organic matter in the ecosystem and regulated by radionuclide-specific mechanisms and metabolic rates of the organisms. Most input parameters were represented by log-normally distributed probability density functions (PDFs) to account for parameter uncertainty. Generally, modelled CRs for grazers, benthos, zooplankton and fish for the 26 elements were in good agreement with site-specific measurements. The uncertainty was reduced when the model was parameterized with site data, and modelled CRs were most similar to measured values for particle reactive elements and for primary consumers. This study clearly demonstrated that it is necessary to validate models with more than just a few elements (e.g. Cs, Sr) in order to make them robust. The use of PDFs as input parameters, rather than averages or best estimates, enabled the estimation of the probable range of modelled CR values for the organism groups, an improvement over models that only estimate means. Using a mechanistic model that is constrained by ecological processes enables (i) the evaluation of the relative importance of food and water

Environmental assessment of remedial action at the Naturita Uranium processing site near Naturita, Colorado

International Nuclear Information System (INIS)

1993-08-01

The proposed remedial action for the Naturita processing site is relocation of the contaminated materials and debris to the Dry Flats disposal site, 6 road miles (mi) [ 1 0 kilometers (km)] to the southeast. At the disposal site, the contaminated materials would be stabilized and covered with layers of earth and rock. The proposed disposal site is on land administered by the Bureau of Land Management (BLM) and used primarily for livestock grazing. The final disposal site would cover approximately 57 ac (23 ha), which would be permanently transferred from the BLM to the DOE and restricted from future uses. The remedial action activities would be conducted by the DOE's Uranium Mill Tailings Remedial Action (UMTRA) Project. The remedial action would result in the loss of approximately 164 ac (66 ha) of soils, but 132 ac (53 ha) of these soils are contaminated and cannot be used for other purposes. Another 154 ac (62 ha) of soils would be temporarily disturbed. Approximately 57 ac (23 ha) of open range land would be permanently removed from livestock grazing and wildlife use. The removal of the contaminated materials would affect the 1 00-year floodplain of the San Miguel River and would result in the loss of riparian habitat along the river. The southwestern willow flycatcher, a Federal candidate species, may be affected by the remedial action, and the use of water from the San Miguel River ''may affect'' the Colorado squawfish, humpback chub, bonytail chub, and razorback sucker. Traffic levels on State Highways 90 and 141 would be increased during the remedial action, as would the noise levels along these transportation routes. Measures for mitigating the adverse environmental impacts of the proposed remedial action are discussed in Section 6.0 of this environmental assessment (EA)

SU-E-T-760: Tolerance Design for Site-Specific Range in Proton Patient QA Process Using the Six Sigma Model

International Nuclear Information System (INIS)

Lah, J; Shin, D; Kim, G

2015-01-01

Purpose: To show how tolerance design and tolerancing approaches can be used to predict and improve the site-specific range in patient QA process in implementing the Six Sigma. Methods: In this study, patient QA plans were selected according to 6 site-treatment groups: head &neck (94 cases), spine (76 cases), lung (89 cases), liver (53 cases), pancreas (55 cases), and prostate (121 cases), treated between 2007 and 2013. We evaluated a model of the Six Sigma that determines allowable deviations in design parameters and process variables in patient-specific QA, where possible, tolerance may be loosened, then customized if it necessary to meet the functional requirements. A Six Sigma problem-solving methodology is known as DMAIC phases, which are used stand for: Define a problem or improvement opportunity, Measure process performance, Analyze the process to determine the root causes of poor performance, Improve the process by fixing root causes, Control the improved process to hold the gains. Results: The process capability for patient-specific range QA is 0.65 with only ±1 mm of tolerance criteria. Our results suggested the tolerance level of ±2–3 mm for prostate and liver cases and ±5 mm for lung cases. We found that customized tolerance between calculated and measured range reduce that patient QA plan failure and almost all sites had failure rates less than 1%. The average QA time also improved from 2 hr to less than 1 hr for all including planning and converting process, depth-dose measurement and evaluation. Conclusion: The objective of tolerance design is to achieve optimization beyond that obtained through QA process improvement and statistical analysis function detailing to implement a Six Sigma capable design

SU-E-T-760: Tolerance Design for Site-Specific Range in Proton Patient QA Process Using the Six Sigma Model

Energy Technology Data Exchange (ETDEWEB)

Lah, J [Myongji Hospital, Goyang, Gyeonggi-do (Korea, Republic of); Shin, D [National Cancer Center, Goyang-si, Gyeonggi-do (Korea, Republic of); Kim, G [University of California, San Diego, La Jolla, CA (United States)

2015-06-15

Purpose: To show how tolerance design and tolerancing approaches can be used to predict and improve the site-specific range in patient QA process in implementing the Six Sigma. Methods: In this study, patient QA plans were selected according to 6 site-treatment groups: head &neck (94 cases), spine (76 cases), lung (89 cases), liver (53 cases), pancreas (55 cases), and prostate (121 cases), treated between 2007 and 2013. We evaluated a model of the Six Sigma that determines allowable deviations in design parameters and process variables in patient-specific QA, where possible, tolerance may be loosened, then customized if it necessary to meet the functional requirements. A Six Sigma problem-solving methodology is known as DMAIC phases, which are used stand for: Define a problem or improvement opportunity, Measure process performance, Analyze the process to determine the root causes of poor performance, Improve the process by fixing root causes, Control the improved process to hold the gains. Results: The process capability for patient-specific range QA is 0.65 with only ±1 mm of tolerance criteria. Our results suggested the tolerance level of ±2–3 mm for prostate and liver cases and ±5 mm for lung cases. We found that customized tolerance between calculated and measured range reduce that patient QA plan failure and almost all sites had failure rates less than 1%. The average QA time also improved from 2 hr to less than 1 hr for all including planning and converting process, depth-dose measurement and evaluation. Conclusion: The objective of tolerance design is to achieve optimization beyond that obtained through QA process improvement and statistical analysis function detailing to implement a Six Sigma capable design.

Audit Report on 'Waste Processing and Recovery Act Acceleration Efforts for Contact-Handled Transuranic Waste at the Hanford Site'

International Nuclear Information System (INIS)

2010-01-01

The Department of Energy's Office of Environmental Management's (EM), Richland Operations Office (Richland), is responsible for disposing of the Hanford Site's (Hanford) transuranic (TRU) waste, including nearly 12,000 cubic meters of radioactive contact-handled TRU wastes. Prior to disposing of this waste at the Department's Waste Isolation Pilot Plant (WIPP), Richland must certify that it meets WIPP's waste acceptance criteria. To be certified, the waste must be characterized, screened for prohibited items, treated (if necessary) and placed into a satisfactory disposal container. In a February 2008 amendment to an existing Record of Decision (Decision), the Department announced its plan to ship up to 8,764 cubic meters of contact-handled TRU waste from Hanford and other waste generator sites to the Advanced Mixed Waste Treatment Project (AMWTP) at Idaho's National Laboratory (INL) for processing and certification prior to disposal at WIPP. The Department decided to maximize the use of the AMWTP's automated waste processing capabilities to compact and, thereby, reduce the volume of contact-handled TRU waste. Compaction reduces the number of shipments and permits WIPP to more efficiently use its limited TRU waste disposal capacity. The Decision noted that the use of AMWTP would avoid the time and expense of establishing a processing capability at other sites. In May 2009, EM allocated $229 million of American Recovery and Reinvestment Act of 2009 (Recovery Act) funds to support Hanford's Solid Waste Program, including Hanford's contact-handled TRU waste. Besides providing jobs, these funds were intended to accelerate cleanup in the short term. We initiated this audit to determine whether the Department was effectively using Recovery Act funds to accelerate processing of Hanford's contact-handled TRU waste. Relying on the availability of Recovery Act funds, the Department changed course and approved an alternative plan that could increase costs by about $25 million

Remedial Action Plan for stabilization of the inactive uraniferous lignite processing sites at Belfield and Bowman, North Dakota

International Nuclear Information System (INIS)

1990-12-01

This remedial action plan (RAP) has been developed to serve a threefold purpose. It presents the series of activities that are proposed by the US Department of Energy (DOE) to accomplish long-term stabilization and control of radioactive materials at the inactive uraniferous lignite processing sites at Belfield and near Bowman (at the former Griffin town site), North Dakota. It provides a characterization of the present conditions of the sites. It also serves to document the concurrence of the state of North Dakota and the US Nuclear Regulatory Commission (NRC) in the remedial action. This agreement, upon execution by the DOE and the state of North Dakota and concurrence by the NRC, becomes Appendix B of the Cooperative Agreement

Ecological studies related to the construction of the Defense Waste Processing Facility on the Savannah River Site

International Nuclear Information System (INIS)

Scott, D.E.; Chazel, A.C.; Pechmann, J.H.K.; Estes, R.A.

1993-06-01

The Defense Waste Processing Facility (DWPF) was built on the Savannah River Site (SRS) during the mid-1980's. The Savannah River Ecology Laboratory (SREL) has completed 14 years of ecological studies related to the construction of the DWPF complex. Prior to construction, the 600-acre site (S-Area) contained a Carolina bay and the headwaters of a stream. Research conducted by the SREL has focused primarily on four questions related to these wetlands: (1) Prior to construction, what fauna and flora were present at the DWPF site and at similar, yet undisturbed, alternative sites? (2) By comparing the Carolina bay at the DWPF site (Sun Bay) with an undisturbed control Carolina bay (Rainbow Bay), what effect is construction having on the organisms that inhabited the DWPF site? (3) By comparing control streams with streams on the periphery of the DWPF site, what effect is construction having on the peripheral streams? (4) How effective have efforts been to lessen the impacts of construction, both with respect to erosion control measures and the construction of ''refuge ponds'' as alternative breeding sites for amphibians that formerly bred at Sun Bay? Through the long-term census-taking of biota at the DWPF site and Rainbow Bay, SREL has begun to evaluate the impact of construction on the biota and the effectiveness of mitigation efforts. Similarly, the effects of erosion from the DWPF site on the water quality of S-Area peripheral streams are being assessed. This research provides supporting data relevant to the National Environmental Policy Act (NEPA) of 1969, the Endangered Species Act of 1973, Executive Orders 11988 (Floodplain Management) and 11990 (Protection of Wetlands), and United States Department of Energy (DOE) Guidelines for Compliance with Floodplain/Wetland Environmental Review Requirements (10 CFR 1022)

Long term developments in irradiated natural uranium processing costs. Optimal size and siting of plants

International Nuclear Information System (INIS)

Thiriet, L.

1964-01-01

The aim of this paper is to help solve the problem of the selection of optimal sizes and sites for spent nuclear fuel processing plants associated with power capacity programmes already installed. Firstly, the structure of capital and running costs of irradiated natural uranium processing plants is studied, as well as the influence of plant sizes on these costs and structures. Shipping costs from the production site to the plant must also be added to processing costs. An attempt to reach a minimum cost for the production of a country or a group of countries must therefore take into account both the size and the location of the plants. The foreseeable shipping costs and their structure (freight, insurance, container cost and depreciation), for spent natural uranium are indicated. Secondly, for various annual spent fuel reprocessing programmes, the optimal sizes and locations of the plants are determined. The sensitivity of the results to the basic assumptions relative to processing costs, shipping costs, the starting up year of the plant programme and the length of period considered, is also tested. - this rather complex problem, of a combinative nature, is solved through dynamic programming methods. - It is shown that these methods can also be applied to the problem of selecting the optimal sizes and locations of processing plants for MTR type fuel elements, related to research reactor programmes, as well as to future plutonium element processing plants related to breeder reactors. Thirdly, the case where yearly extraction of the plutonium contained in the irradiated natural uranium is not compulsory is examined; some stockpiling of the fuel is then allowed some years, entailing delayed processing. The load factor of such plants is thus greatly improved with respect to that of plants where the annual plutonium demand is strictly satisfied. By including spent natural uranium stockpiling costs an optimal rhythm of introduction and optimal sizes for spent fuel

Structure, Process, and Outcome Quality of Surgical Site Infection Surveillance in Switzerland.

Science.gov (United States)

Kuster, Stefan P; Eisenring, Marie-Christine; Sax, Hugo; Troillet, Nicolas

2017-10-01

OBJECTIVE To assess the structure and quality of surveillance activities and to validate outcome detection in the Swiss national surgical site infection (SSI) surveillance program. DESIGN Countrywide survey of SSI surveillance quality. SETTING 147 hospitals or hospital units with surgical activities in Switzerland. METHODS Site visits were conducted with on-site structured interviews and review of a random sample of 15 patient records per hospital: 10 from the entire data set and 5 from a subset of patients with originally reported infection. Process and structure were rated in 9 domains with a weighted overall validation score, and sensitivity, specificity, positive predictive value, and negative predictive value were calculated for the identification of SSI. RESULTS Of 50 possible points, the median validation score was 35.5 (range, 16.25-48.5). Public hospitals (PSwitzerland (P=.021), and hospitals with longer participation in the surveillance (P=.018) had higher scores than others. Domains that contributed most to lower scores were quality of chart review and quality of data extraction. Of 49 infections, 15 (30.6%) had been overlooked in a random sample of 1,110 patient records, accounting for a sensitivity of 69.4% (95% confidence interval [CI], 54.6%-81.7%), a specificity of 99.9% (95% CI, 99.5%-100%), a positive predictive value of 97.1% (95% CI, 85.1%-99.9%), and a negative predictive value of 98.6% (95% CI, 97.7%-99.2%). CONCLUSIONS Irrespective of a well-defined surveillance methodology, there is a wide variation of SSI surveillance quality. The quality of chart review and the accuracy of data collection are the main areas for improvement. Infect Control Hosp Epidemiol 2017;38:1172-1181.

Assessment of public acceptability in site selection process. The methodology and the results

International Nuclear Information System (INIS)

Zeleznik, N.; Kralj, M.; Polic, M.; Kos, D.; Pek Drapal, D.

2005-01-01

The site selection process for the low and intermediate radioactive waste (LILW) repository in Slovenia follows the mixed mode approach according to the model proposed by IAEA. After finishing the conceptual and planning stage in 1999, and after identification of the potentially suitable areas in the area survey stage in 2001, ARAO (Agency for radwaste management) invited all municipalities to volunteer in the procedure of placing the LILW repository in the physical environment. A positive response was received from eight municipalities, though three municipalities later resigned from it. A selection between twelve locations in these five municipalities had to be done because Slovenian procedure provides for only three locations to be further evaluated in the stage of identification of potentially suitable sites. A pre-feasibility study of the public acceptability, together with the technical aspects (safety, technical functionality, economic, environmental and spatial aspects) was performed. The aspect of public acceptability included objective and subjective evaluation criteria. The former included information obtained from studies of demography, data on local economy, infrastructure and eventual environmental problems, media analysis, and earlier public opinion polls. The latter included data obtained from topical workshops, free phone line, telephone interviews with the general public and personal interviews with representatives of decision makers and public opinion leaders, as well as a public opinion poll in all included communities. Evaluated municipalities were ranked regarding their social suitability for the radioactive waste site. (author)

Processing capabilties for the elimination of contaminated metal scrapyards at DOE/ORO-managed sites

International Nuclear Information System (INIS)

Mack, J.E.; Williams, L.C.

1982-01-01

Capabilities exist for reducing all the contaminated nickel, aluminum, and copper scrap to ingot form by smelting. Processing these metals at existing facilities could be completed in about 5 or 6 years. However, these metals represent only about 20% of the total metal inventories currently on hand at the DOE/ORO-managed sites. No provisions have been made for the ferrous scrap. Most of the ferrous scrap is unclassified and does not require secured storage. Also, the potential resale value of the ferrous scrap at about $100 per ton is very low in comparison. Consequently, this scrap has been allowed to accumulate. With several modifications and equipment additions, the induction melter at PGDP could begin processing ferrous scrap after its commitment to nickel and aluminum. The PGDP smelter is a retrofit installation, and annual throughput capabilities are limited. Processing of the existing ferrous scrap inventories would not be completed until the FY 1995-2000 time frame. An alternative proposal has been the installation of induction melters at the other two enrichment facilities. Conceptual design of a generic metal smelting facility is under way. The design study includes capital and operating costs for scrap preparation through ingot storage at an annual throughput of 10,000 tons per year. Facility design includes an induction melter with the capability of melting both ferrous and nonferrous metals. After three years of operation with scrapyard feed, the smelter would have excess capacity to support on-site decontamination and decomissioning projects or upgrading programs. The metal smelting facility has been proposed for FY 1984 line item funding with start-up operations in FY 1986

Internationally Standardized Reporting (Checklist) on the Sustainable Development Performance of Uranium Mining and Processing Sites

International Nuclear Information System (INIS)

Harris, Frank

2014-01-01

The Internationally Standardized Reporting Checklist on the Sustainable Development Performance of Uranium Mining and Processing Sites: • A mutual and beneficial work between a core group of uranium miners and nuclear utilities; • An approach based on an long term experience, international policies and sustainable development principles; • A process to optimize the reporting mechanism, tools and efforts; • 11 sections focused on the main sustainable development subject matters known at an operational and headquarter level. The WNA will make available the sustainable development checklist for member utilities and uranium suppliers. Utilities and suppliers are encouraged to use the checklist for sustainable development verification.

A process to estimate net infiltration using a site-scale water-budget approach, Rainier Mesa, Nevada National Security Site, Nevada, 2002–05

Science.gov (United States)

Smith, David W.; Moreo, Michael T.; Garcia, C. Amanda; Halford, Keith J.; Fenelon, Joseph M.

2017-08-29

This report documents a process used to estimate net infiltration from precipitation, evapotranspiration (ET), and soil data acquired at two sites on Rainier Mesa. Rainier Mesa is a groundwater recharge area within the Nevada National Security Site where recharged water flows through bedrock fractures to a deep (450 meters) water table. The U.S. Geological Survey operated two ET stations on Rainier Mesa from 2002 to 2005 at sites characterized by pinyon-juniper and scrub-brush vegetative cover. Precipitation and ET data were corrected to remove measurement biases and gap-filled to develop continuous datasets. Net infiltration (percolation below the root zone) and changes in root-zone water storage were estimated using a monthly water-balance model.Site-scale water-budget results indicate that the heavily-fractured welded-tuff bedrock underlying thin (water source for vegetation during dry periods. Annual precipitation during the study period ranged from fourth lowest (182 millimeters [mm]) to second highest (708 mm) on record (record = 55 years). Annual ET exceeded precipitation during dry years, indicating that the fractured-bedrock reservoir capacity is sufficient to meet atmospheric-evaporative demands and to sustain vegetation through extended dry periods. Net infiltration (82 mm) was simulated during the wet year after the reservoir was rapidly filled to capacity. These results support previous conclusions that preferential fracture flow was induced, resulting in an episodic recharge pulse that was detected in nearby monitoring wells. The occurrence of net infiltration only during the wet year is consistent with detections of water-level rises in nearby monitoring wells that occur only following wet years.

Remedial action plan and site design for stabilization of the inactive uranium processing site at Naturita, Colorado. Appendix B of Attachment 3: Groundwater hydrology report, Attachment 4: Water resources protection strategy, Final

Energy Technology Data Exchange (ETDEWEB)

1994-03-01

Attachment 3 Groundwater Hydrology Report describes the hydrogeology, water quality, and water resources at the processing site and Dry Flats disposal site. The Hydrological Services calculations contained in Appendix A of Attachment 3, are presented in a separate report. Attachment 4 Water Resources Protection Strategy describes how the remedial action will be in compliance with the proposed EPA groundwater standards.

A New Tool for Automated Data Collection and Complete On-site Flux Data Processing for Eddy Covariance Measurements

Science.gov (United States)

Begashaw, I. G.; Kathilankal, J. C.; Li, J.; Beaty, K.; Ediger, K.; Forgione, A.; Fratini, G.; Johnson, D.; Velgersdyk, M.; Hupp, J. R.; Xu, L.; Burba, G. G.

2014-12-01

The eddy covariance method is widely used for direct measurements of turbulent exchange of gases and energy between the surface and atmosphere. In the past, raw data were collected first in the field and then processed back in the laboratory to achieve fully corrected publication-ready flux results. This post-processing consumed significant amount of time and resources, and precluded researchers from accessing near real-time final flux results. A new automated measurement system with novel hardware and software designs was developed, tested, and deployed starting late 2013. The major advancements with this automated flux system include: 1) Enabling logging high-frequency, three-dimensional wind speeds and multiple gas densities (CO2, H2O and CH4), low-frequency meteorological data, and site metadata simultaneously through a specially designed file format 2) Conducting fully corrected, real-time on-site flux computations using conventional as well as user-specified methods, by implementing EddyPro Software on a small low-power microprocessor 3) Providing precision clock control and coordinate information for data synchronization and inter-site data comparison by incorporating a GPS and Precision Time Protocol. Along with these innovations, a data management server application was also developed to chart fully corrected real-time fluxes to assist remote system monitoring, to send e-mail alerts, and to automate data QA/QC, transfer and archiving at individual stations or on a network level. Combination of all of these functions was designed to help save substantial amount of time and costs associated with managing a research site by eliminating the post-field data processing, reducing user errors and facilitating real-time access to fully corrected flux results. The design, functionality, and test results from this new eddy covariance measurement tool will be presented.

Implementation of a fully automated process purge-and-trap gas chromatograph at an environmental remediation site

International Nuclear Information System (INIS)

Blair, D.S.; Morrison, D.J.

1997-01-01

The AQUASCAN, a commercially available, fully automated purge-and-trap gas chromatograph from Sentex Systems Inc., was implemented and evaluated as an in-field, automated monitoring system of contaminated groundwater at an active DOE remediation site in Pinellas, FL. Though the AQUASCAN is designed as a stand alone process analytical unit, implementation at this site required additional hardware. The hardware included a sample dilution system and a method for delivering standard solution to the gas chromatograph for automated calibration. As a result of the evaluation the system was determined to be a reliable and accurate instrument. The AQUASCAN reported concentration values for methylene chloride, trichloroethylene, and toluene in the Pinellas ground water were within 20% of reference laboratory values

Data Validation Package June 2016 Groundwater and Surface Water Sampling at the Old and New Rifle, Colorado, Processing Sites September 2016

Energy Technology Data Exchange (ETDEWEB)

Bush, Richard [USDOE Office of Legacy Management (LM), Washington, DC (United States); Lemke, Peter [Navarro Research and Engineering, Inc., Oak Ridge, TN (United States)

2016-10-17

Sampling Period: June 14–17 and July 7, 2016. Water samples were collected from 36 locations at New Rifle and Old Rifle, Colorado, Disposal/Processing Sites. Planned monitoring locations are shown in Attachment 1, Sampling and Analysis Work Order. Duplicate samples were collected from New Rifle locations 0216 and 0855, and Old Rifle location 0655. One equipment blank was collected after decontamination of non-dedicated equipment used to collect one surface water sample. See Attachment 2, Trip Report for additional details. Sampling and analyses were conducted as specified in the Sampling and Analysis Plan for U.S. Department of Energy Office of Legacy Management Sites (LMS/PRO/S04351, continually updated, http://energy.gov/lm/downloads/sampling-and- analysis-plan-us-department-energy-office-legacy-management-sites). New Rifle Site Samples were collected at the New Rifle site from 16 monitoring wells and 7 surface locations in compliance with the December 2008 Groundwater Compliance Action Plan [GCAP] for the New Rifle, Colorado, Processing Site (LMS/RFN/S01920). Monitoring well 0216 could not be sampled in June because it was surrounded by standing water due to the high river stage from spring runoff, it was later sampled in July. Monitoring well 0635 and surface location 0322 could not be sampled because access through the elk fence along Interstate 70 has not been completed at this time. Old Rifle Site Samples were collected at the Old Rifle site from eight monitoring wells and five surface locations in compliance with the December 2001 Ground Water Compliance Action Plan for the Old Rifle, Colorado, UMTRA Project Site (GJ0-2000-177-TAR).

The question of chemical processing of drilling muds when drilling wells at the Bulla Sea site

Energy Technology Data Exchange (ETDEWEB)

Ismaylov, A P; Avanesova, A M; Noven' kov, Yu P

1979-01-01

Based on the experience in the sinking of a number of deep wells in the Bulla Sea site, an integral chemical processing of drilling muds is recommended. The experience is shown of using inhibited gypsum systems in drilling in the deposits of the Akchagyl'sk stage and the PT to the roof of the V level instead of the previously used KSSB with viscosity reducers. From the roof of the V level because of the increased content of sandstone material the type of chemical processing is changed - instead of gypsum solutions, solutions are recommended, which are processed by KSSB in combination with oxyl with additives of bentonite clay because of their low content in the section.

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.

2015 Advanced Site Investigation and Monitoring Report Riverton, Wyoming, Processing Site September 2016

Energy Technology Data Exchange (ETDEWEB)

Frazier, William [U.S. Dept. of Energy, Washington, DC (United States). Office of Legacy Management (LM); Campbell, Sam [Navarro Research and Engineering, Inc., Oak Ridge, TN (United States)

2016-09-01

The U.S. Department of Energy conducted initial groundwater characterization of the Riverton, Wyoming, Processing Site in the 1990s. The characterization culminated in a Site Observational Work Plan in 1998 that recommended a natural flushing compliance strategy. Results of verification monitoring indicated that natural flushing was generally progressing as expected until June 2010, when significant increases in contaminant concentrations were measured in several monitoring wells downgradient of the site after the area flooded. In response to the unexpected results following the flood, an enhanced characterization of the surficial aquifer was conducted in 2012, which included installation of 103 boreholes along nine transects with a Geoprobe, collection of 103 water samples and 65 soil samples, laboratory tests on the soil samples, and additional groundwater modeling. This advanced site investigation report summarizes additional investigation in 2015 through the use of backhoe trenching, sonic drilling, multilevel monitoring wells, direct-push drilling, and temporary well points to collect soil and groundwater samples. Additional surface water measurements were made included the installation of a stilling well and the measurement of stream elevation along the Wind River to approximate upgradient groundwater heads. Groundwater sampling included the addition of geochemical constituents and isotopes that have not been sampled in the past to better understand post-flood conditions and the possibility of additional or ongoing contaminant sources. This sampling was performed to (1) better define the contaminant plumes, (2) verify the occurrence of persistent secondary contaminant sources, (3) better understand the reason for the contaminant spikes after a 2010 flood, and (4) assess contaminant plume stagnation near the Little Wind River. This report provides data analyses and interpretations for the 2015 site investigation that addresses these issues and provides

The Influence of Social Network Sites on the Job Application Process

DEFF Research Database (Denmark)

Ben Allouch, Somaya; Kotamraju, Nalini Panchita

2011-01-01

The popularity of social network sites has given rise to concerns about the amount and nature of information that people disclose on them. While the media has publicized several high-profile instances of people losing their jobs because they had disclosed inappropriate job-related, empirical......, but when tested experimentally, the results show that recruiters do rely more on information derived from others than on self-reported information. This research confirms the popular suspicion that social network sites influence job applicants’ career opportunities, but also goes further to demonstrate...... research about the use of social network sites by job recruiters is almost non-existing. Social network sites are nowadays tools for recruiters to screen job applicants during the job application procedure. This study examined what specific information on social network sites recruiters use to form...

Regrowth of arsenate–sulfate efflorescences on processing plant walls at the Ottery arsenic–tin mine, New South Wales, Australia: Implications for arsenic mobility and remediation of mineral processing sites

International Nuclear Information System (INIS)

Hebbard, Emily R.; Wilson, Siobhan A.; Jowitt, Simon M.; Tait, Alastair W.; Turvey, Connor C.; Wilson, Harriet L.

2017-01-01

Processing equipment and buildings at derelict mine sites are commonly coated in metal- and metalloid-rich residues that can significantly contribute to acid and metalliferous drainage, potentially polluting soils and watercourses. Here, we describe arsenic-rich residues and efflorescences on processing buildings at the derelict Ottery As–Sn mine in New South Wales, Australia and use the resulting data to determine the mineral hosts for arsenic and their distribution at the site. X-ray diffraction (XRD), portable X-ray fluorescence (XRF) and scanning electron microscopy (SEM) data are used to conduct mineralogical, geochemical and microstructural analysis of the efflorescences. Brickwork columns within As condenser buildings are coated primarily with gypsum (CaSO_4·2H_2O) and contain approximately 1–5 wt% As, but more sheltered columns are associated with efflorescences rich in arsenolite and claudetite (polymorphs of As_2O_3) and contain up to ∼70–80 wt% As. The efflorescences within the Ottery condensers commonly contain minor quartz (SiO_2), feldspars, and two uncharacterised phases, including a K-Al-As phase and a Ca-Na-K-Al-F-As phase that are likely similar to previously reported phases from an As processing site in Cornwall, UK. SEM imaging indicates that the weathering of mortar and bricks provides a source of cations for efflorescence formation, with grains of more resistant minerals (e.g., quartz) incorporated into the efflorescences. Arsenic does not appear to substitute significantly for S in gypsum but instead is generally hosted in (1) Al, Na, Ca and Fe-bearing arsenate minerals in weathered efflorescences and (2) in small grains of arsenolite in pore spaces within the brickwork, indicating that the bricks are a potentially long-lived source of As. The efflorescences on exposed columns at Ottery also regrow within 12 months after removal, releasing stored arsenic from the brickwork and causing a cyclical degradation of the buildings. Our

Mercury behaviour and C, N, and P biogeochemical cycles during ecological restoration processes of old mining sites in French Guiana.

Science.gov (United States)

Couic, Ewan; Grimaldi, Michel; Alphonse, Vanessa; Balland-Bolou-Bi, Clarisse; Livet, Alexandre; Giusti-Miller, Stéphanie; Sarrazin, Max; Bousserrhine, Noureddine

2018-04-25

Several decades of gold mining extraction activities in the Amazonian rainforest have caused deforestation and pollution. While ecological rehabilitation is essential for restoring biodiversity and decreasing erosion on deforested lands, few studies note the behaviour or toxicity of trace elements during the rehabilitation process. Our original study focused on the potential use of microbial activity and Hg speciation and compared them with As, Cu, Zn and Cr speciation in assessing the chemical and biological quality of ecological restoration efforts. We sampled two sites in French Guyana 17 years after rehabilitation efforts began. The former site was actively regenerated (R) with the leguminous species Clitoria racemosa and Acacia mangium, and the second site was passively regenerated with spontaneous vegetation (Sv). We also sampled soil from a control site without a history of gold mining (F). We performed microcosm soil experiments for 30 days, where trace element speciation and enzyme activities (i.e., FDA, dehydrogenase, β-glucosidase, urease, alkaline and acid phosphatase) were estimated to characterise the behaviour of trace elements and the soil microbial activity. As bioindicators, the use of soil microbial carbon biomass and soil enzyme activities related to the carbon and phosphorus cycles seems to be relevant for assessing soil quality in rehabilitated and regenerated old mining sites. Our results showed that restoration with leguminous species had a positive effect on soil chemical quality and on soil microbial bioindicators, with activities that tended toward natural non-degraded soil (F). Active restoration processes also had a positive effect on Hg speciation by reducing its mobility. While in Sv we found more exchangeable and soluble mercury, in regenerated sites, Hg was mostly bound to organic matter. These results also suggested that enzyme activities and mercury cycles are sensitive to land restoration and must be considered when evaluating

Position paper on the applicability of supplemental standards to the uppermost aquifer at the Uranium Mill Tailings Vitro Processing Site, Salt Lake City, Utah

International Nuclear Information System (INIS)

1996-03-01

This report documents the results of the evaluation of the potential applicability of supplemental standards to the uppermost aquifer underlying the Uranium Mill Tailings Remedial Action (UMTRA) Project, Vitro Processing Site, Salt Lake City, Utah. There are two goals for this evaluation: provide the landowner with information to make an early qualitative decision on the possible use of the Vitro property, and evaluate the proposed application of supplemental standards as the ground water compliance strategy at the site. Justification of supplemental standards is based on the contention that the uppermost aquifer is of limited use due to wide-spread ambient contamination not related to the previous site processing activities. In support of the above, this report discusses the site conceptual model for the uppermost aquifer and related hydrogeological systems and establishes regional and local background water quality. This information is used to determine the extent of site-related and ambient contamination. A risk-based evaluation of the contaminants' effects on current and projected land uses is also provided. Reports of regional and local studies and U.S. Department of Energy (DOE) site investigations provided the basis for the conceptual model and established background ground water quality. In addition, a limited field effort (4 through 28 March 1996) was conducted to supplement existing data, particularly addressing the extent of contamination in the northwestern portion of the Vitro site and site background ground water quality. Results of the field investigation were particularly useful in refining the conceptual site model. This was important in light of the varied ground water quality within the uppermost aquifer. Finally, this report provides a critical evaluation, along with the related uncertainties, of the applicability of supplemental standards to the uppermost aquifer at the Salt Lake City Vitro processing site

Site identification presentation: Basalt Waste Isolation Project

International Nuclear Information System (INIS)

1979-11-01

The final step in the site identification process for the Basalt Waste Isolation Project is described. The candidate sites are identified. The site identification methodology is presented. The general objectives which must be met in selecting the final site are listed. Considerations used in the screening process are also listed. Summary tables of the guidelines used are included

Using Dirichlet Processes for Modeling Heterogeneous Treatment Effects across Sites

Science.gov (United States)

Miratrix, Luke; Feller, Avi; Pillai, Natesh; Pati, Debdeep

2016-01-01

Modeling the distribution of site level effects is an important problem, but it is also an incredibly difficult one. Current methods rely on distributional assumptions in multilevel models for estimation. There it is hoped that the partial pooling of site level estimates with overall estimates, designed to take into account individual variation as…

Social acceptance process model for ensuring the high-level radioactive waste disposal site

International Nuclear Information System (INIS)

Wada, Ryutaro; Tanaka, Satoru; Nagasaki, Shinya

2009-01-01

Generally speaking, a vast, advanced and unfamiliar science and technology are unacceptable to the public for fear of their unknown nature. Here, the social acceptance process model was examined on the basis of the analysis of the cause phenomenon and numerical grounds, by referring to the problems on the application of literature documentation for location examination of a high-level radioactive waste disposal site in Toyo town in Kochi Pref. in April 2007. In analyzing the Toyo town case, we have found a possibility that the majority of local residents knew very little about the object opposed by the fringe route processing. To ensure a healthy decision making by the public, it is vital to convey fundamental information using sufficient wide-area PR media before the issue becomes actual. After the issue becomes actual, dialog with residents through a careful technology assessment is indispensable. The authors focus attention on the decision-making process of human beings from the social and psychological viewpoints, and point out that it is desirable for promoting social acceptance by adopting two approaches: a direct approach aiming at better intelligibility for the different resident layers and a deductive approach in technological essence. (author)

Plan for implementing EPA standards for UMTRA sites

International Nuclear Information System (INIS)

1984-01-01

The Uranium Mill Tailings Radiation Control Act of 1978 (UMTRCA), authorizes the Department of Energy (DOE) to undertake remedial actions at 24 DOE designated processing sites. The term ''processing site,'' by statutory definition, means the inactive uranium mill or processing site and any other real property or improvement which is in the vicinity of the mill or processing site and is determined to be contaminated with residual radioactive materials derived from the mill or processing site. For purposes of this document, the inactive mill or processing site is referred to as the ''processing site'' and the other real property or improvement in the vicinity of such site is referred to as a 'vicinity property.'' The purpose of the remedial actions is to stabilize and control the uranium mill tailings and other residual radioactive materials in a safe and environmentally sound manner. Remedial actions undertaken by DOE are to be accomplished: With the full participation of the affected states and Indian tribes, in accordance with standards issued by the Environmental Protection Agency (EPA), and with the concurrence of the Nuclear Regulatory Commission (NRC). This plan is designed to be a generic presentation on methodology that will be followed in implementing the EPA standards. 5 refs., 1 tab

The Specification of Cement Powders for Waste Encapsulation Processes at Sellafield site

International Nuclear Information System (INIS)

Angus, M.; Borwick, J.; Cann, G.; Hayes, M.; McLuckie, B.; Jowsey, J.

2012-01-01

Requirements are described for Portland Cement (CEM I), Ground Granulated Blast-furnace Slag (GGBS) and Fly Ash (FA) powders used for the encapsulation of Intermediate Level Radioactive Waste (ILW) in UK, with particular reference to Sellafield site encapsulation processes. Differences between the powders used by the UK nuclear industry and the equivalent British and European cement standards are explained. Research over the last 20 years to respond to changes in the performance of these powders is summarised and options for dealing with potential future changes are discussed. These include the use of special blends of GGBS to achieve the desired flow properties or alternatively poly-carboxylate super-plasticizers to produce grouts with consistent performance using cement powders with a wide range of composition. (authors)

The procedure of alternative site selection within the report of the study group on the radioactive waste final repository selection process (AKEnd)

International Nuclear Information System (INIS)

Brenner, M.

2005-01-01

The paper discusses the results of the report of the study group on the radioactive waste final repository selection process with respect to the alternative site selection procedure. Key points of the report are the long-term safety, the alternativity of sites and the concept of one repository. The critique on this report is focussed on the topics site selection and licensing procedures, civil participation, the factor time and the question of cost

Use of the Geographic Information System and Analytic Hierarchy Process for Municipal Solid Waste Landfill Site Selection: A Case Study of Najafabad, Iran

Directory of Open Access Journals (Sweden)

A. Afzali

2014-03-01

Full Text Available Following technological advancements and integrated municipal solid waste management in recent decades, various methods such as recycling, biotreatment, thermal treatment, and sanitary landfills have been developed and employed. Creating sanitary landfills is a major strategy in the integrated solid waste management hierarchy. It is cheaper and thus more common than other disposal methods. Selecting a suitable solid waste landfill site can prevent adverse ecological and socioeconomic effects. Landfill site selection requires the analysis of spatial data, regulations, and accepted criteria. The present study aimed to use the geographic information system and the analytic hierarchy process to identify an appropriate landfill site for municipal solid wastes in Najafabad (Isfahan, Iran. Environmental and socioeconomic criteria were evaluated through different information layers in the Boolean and fuzzy logics. The analytical hierarchy process was applied for weighing the fuzzy information layers. Subsequently, two suitable sites were identified by superimposing the maps from the Boolean and fuzzy logics and considering the minimum required landfill area for 20 years. However, proximity of these two sites to Tiran (a nearby city made them undesirable landfill sites for Najafabad. Therefore, due to the existing restrictions in Najafabad, the possibility of creating landfill sites in common with adjacent cities should be further investigated.

Technical know-how of site descriptive modeling for site characterization - 59089

International Nuclear Information System (INIS)

Saegusa, Hiromitsu; Onoe, Hironori; Doke, Ryosuke; Niizato, Tadafumi; Yasue, Ken-ichi

2012-01-01

The site descriptive model covering the current status of characteristics of geological environment and the site evolution model for estimation of the long-term evolution of site conditions are used to integrate multi-disciplinary investigation results. It is important to evaluate uncertainties in the models, to specify issues regarding the uncertainties and to prioritize the resolution of specified issues, for the planning of site characterization. There is a large quantity of technical know-how in the modeling process. It is important to record the technical know-how with transparency and traceability, since site characterization projects generally need long duration. The transfer of the technical know-how accumulated in the research and development (R and D) phase to the implementation phase is equally important. The aim of this study is to support the planning of initial surface-based site characterizations based on the technical know-how accumulated from the underground research laboratory projects. These projects are broad scientific studies of the deep geological environment and provide a technical basis for the geological disposal of high-level radioactive wastes. In this study, a comprehensive task flow from acquisition of existing data to planning of field investigations through the modeling has been specified. Specific task flow and decision-making process to perform the tasks have been specified. (authors)

Site Selection for the Salt Disposition Facility at the Savannah River Site

International Nuclear Information System (INIS)

Gladden, J.B.; Rueter, K.J.; Morin, J.P.

2000-01-01

A site selection study was conducted to identify a suitable location for the construction and operation of a new Salt Disposition Facility (SDF) at the Savannah River Site (SRS). The facility to be sited is a single processing facility and support buildings that could house either of three technology alternatives being developed by the High Level Waste Systems Engineering Team: Small Tank Tetraphenylborate Precipitation, Crystalline Silicotitanate Non-Elutable Ion Exchange or Caustic Side Solvent Extraction. A fourth alternative, Direct Disposal in grout, is not part of the site selection study because a location has been identified that is unique to this technology (i.e., Z-Area). Facility site selection at SRS is a formal, documented process that seeks to optimize siting of new facilities with respect to facility-specific engineering requirements, sensitive environmental resources, and applicable regulatory requirements. In this manner, the prime objectives of cost minimization, environmental protection, and regulatory compliance are achieved. The results from this geotechnical characterization indicated that continued consideration be given to Site B for the proposed SDF. Suitable topography, the lack of surface hydrology and floodplain issues, no significant groundwater contamination, the presence of minor soft zones along the northeast portion of footprint, and no apparent geological structure in the Gordon Aquitard support this recommendation

Remedial design process for Montclair/West Orange and Glen Ridge radium sites

International Nuclear Information System (INIS)

MacIndoe, M.; Johnson, R.; Paez-Restrepo, A.; Wilkinson, S.; Hyman, M.

1994-01-01

The Montclair/West Orange and Glen Ridge Superfund Sites, located in Essex County, New Jersey, are contaminated to varying degrees with radioactive materials. The waste materials originated from radium processing facilities prevalent in the area during the early 1900's. The two sites consist of 769 residential and commercial properties having a combined land area of approximately 210 acres. Historically, radioactive waste materials were disposed as landfill material in what were once rural areas. As development flourished, homes and streets were constructed over the landfilled waste. In 1981 the EPA conducted an aerial gamma radiation survey of the area to determine the presence of radioactive materials. It was from this survey that subsequent ground studies where initiated, and elevated gamma radiation and radon levels were discovered. The paper will discuss the methods used to obtain data through field investigations; the relationship between the interpretation of data to define the vertical and lateral limits of contamination and the selection of remedial design methods used to develop excavation plans; the evolution of remediation methods and technologies relative to the remediation of structures by underpinning basements, on-grade structures, and chimneys; removal of contaminated material beneath footings without cribbing; and demolition of basement foundation walls (where contaminated) without use of traditional support methods. Finally, the paper will discuss remedial action execution of the work

Ground water elevation monitoring at the Uranium Mill Tailings Remedial Action Salt Lake City, Utah, Vitro processing site

International Nuclear Information System (INIS)

1995-04-01

In February 1994, a ground water level monitoring program was begun at the Vitro processing site. The purpose of the program was to evaluate how irrigating the new golf driving range affected ground water elevations in the unconfined aquifer. The program also evaluated potential impacts of a 9-hole golf course planned as an expansion of the driving range. The planned golf course expansion would increase the area to be irrigated and, thus, the water that could infiltrate the processing site soil to recharge the unconfined aquifer. Increased water levels in the aquifer could alter the ground water flow regime; contaminants in ground water could migrate off the site or could discharge to bodies of surface water in the area. The potential effects of expanding the golf course have been evaluated, and a report is being prepared. Water level data obtained during this monitoring program indicate that minor seasonal mounding may be occurring in response to irrigation of the driving range. However, the effects of irrigation appear small in comparison to the effects of precipitation. There are no monitor wells in the area that irrigation would affect most; that data limitation makes interpretations of water levels and the possibility of ground water mounding uncertain. Limitations of available data are discussed in the conclusion

Hanford Site Development Plan

International Nuclear Information System (INIS)

Hathaway, H.B.; Daly, K.S.; Rinne, C.A.; Seiler, S.W.

1993-05-01

The Hanford Site Development Plan (HSDP) provides an overview of land use, infrastructure, and facility requirements to support US Department of Energy (DOE) programs at the Hanford Site. The HSDP's primary purpose is to inform senior managers and interested parties of development activities and issues that require a commitment of resources to support the Hanford Site. The HSDP provides an existing and future land use plan for the Hanford Site. The HSDP is updated annually in accordance with DOE Order 4320.1B, Site Development Planning, to reflect the mission and overall site development process. Further details about Hanford Site development are defined in individual area development plans

Use of advanced chemical fingerprinting in PAH source identification and allocation at a coal tar processing site

International Nuclear Information System (INIS)

Brown, J.S.; Boehm, P.D.; Douglas, G.S.

1995-01-01

Advanced chemical fingerprinting analyses were used to determine source allocation at a former coal tar processing facility which had been converted to a petroleum recycling site. Soil samples from the site had high petroleum hydrocarbon concentrations and elevated levels of polynuclear aromatic hydrocarbons (PAH). Comparisons of PAH distributions were used to differentiate the coal tar hydrocarbons from the petroleum hydrocarbons in soil samples. A more specific technique was needed to accurately allocate the contribution of the two sources to the observed PAH contamination in the soil. Petroleum biomarkers (steranes and triterpanes) which are present in crude oils and many refined petroleum products but are absent in coal tar were used to quantitatively allocate the source of the PAH contamination based on the relative ratio of the PAH to the biomarkers in soil samples. Using the resulting coal tar/petroleum source ratio the contribution of petroleum to the overall PAH contamination at the site was calculated. A multivariate statistical technique (principal component analysis or PCA) was used to provide an independent validation of the source allocation. The results of the source allocation provided a foundation for the site clean-up and remediation costs

Nuclear waste repository siting

International Nuclear Information System (INIS)

Soloman, B.D.; Cameron, D.M.

1987-01-01

This paper discusses the geopolitics of nuclear waste disposal in the USA. Constitutional choice and social equity perspectives are used to argue for a more open and just repository siting program. The authors assert that every potential repository site inevitably contains geologic, environmental or other imperfections and that the political process is the correct one for determining sites selected

Radiological surveillance of Remedial Action activities at the processing site, Falls City, Texas. Final report

International Nuclear Information System (INIS)

1993-04-01

The Uranium Mill Tailings Remedial Action (UMTRA) Project's Technical Assistance Contractor (TAC) performed a radiological surveillance of the Remedial Action Contractor (RAC), MK-Ferguson and CWM Federal Environmental Services, Inc., at the processing site in Falls City, Texas. This surveillance was conducted March 22--26, 1993. No findings were identified during the surveillance. Three site-specific observations and three programmatic observations are presented in this report. The overall conclusion from the surveillance is that the radiological aspects of the Falls City, Texas, remedial action program are performed adequately. However, some of the observations identify that there is potential for improving certain aspects of the occupational radiological air sampling, ensuring analytical data quality, and in communicating with the DOE and TAC on the ore sampling methods. The TAC has also received and is currently reviewing the RAC's responses regarding the observations identified during the radiological surveillance performed October 29--30, 1992

Process evaluation of child health services at outreach sites during health and nutrition day (Mamta Day) in urban slums of Western India.

Science.gov (United States)

Mehta, Kedar; Pandya, Chandresh; Chavda, Paragkumar; Solanki, Dipak

2017-01-01

Health indicators of rural and urban India show a wide variation. Rural areas have received large focus in child health services, but on the flip side, urban areas have been the last to receive such attention. A cross-sectional study was conducted to include one randomly selected outreach session from all the 19 urban primary health centers of Vadodara city from April 2013 to May 2014. Nineteen session sites were observed for the process evaluation of three components of child health care, namely, "planning of Health and Nutrition Day," "availability of vaccines/logistics," and "direct observation of actual immunization process" at the site using a structured checklist. Most of the vaccines and logistics were present at all 19 sites visited, but adverse events following immunization kit were observed at ten sites (52%) only. Open vial policy, no-touch technique, and immediate cutting of syringe with hub cutter were implemented at all sites; however, completely filled Mamta Card was observed at 9 (47%) sites only. All four key messages were given at 5 (26%) sites only. Immunization services such as proper vaccine administration with no-touch technique and open vial policy were mainly focused; however, other services such as biomedical waste management, record keeping, and delivery of all four key messages need to be strengthened during Mamta Divas. Strengthening of other child health care services such as growth monitoring, Integrated Management of Neonatal and Childhood Illnesses, and referral services is required in urban areas.

Conditions and processes affecting sand resources at archeological sites in the Colorado River corridor below Glen Canyon Dam, Arizona

Science.gov (United States)

East, Amy E.; Collins, Brian D.; Sankey, Joel B.; Corbett, Skye C.; Fairley, Helen C.; Caster, Joshua J.

2016-05-17

This study examined links among fluvial, aeolian, and hillslope geomorphic processes that affect archeological sites and surrounding landscapes in the Colorado River corridor downstream from Glen Canyon Dam, Arizona. We assessed the potential for Colorado River sediment to enhance the preservation of river-corridor archeological resources through aeolian sand deposition or mitigation of gully erosion. By identifying locally prevailing wind directions, locations of modern sandbars, and likely aeolian-transport barriers, we determined that relatively few archeological sites are now ideally situated to receive aeolian sand supply from sandbars deposited by recent controlled floods. Whereas three-fourths of the 358 river-corridor archeological sites we examined include Colorado River sediment as an integral component of their geomorphic context, only 32 sites currently appear to have a high degree of connectivity (coupled interactions) between modern fluvial sandbars and sand-dominated landscapes downwind. This represents a substantial decrease from past decades, as determined by aerial-photograph analysis. Thus, we infer that recent controlled floods have had a limited, and declining, influence on archeological-site preservation.

Qualified public involvement in the decision making process of siting a waste repository

International Nuclear Information System (INIS)

Rodrigues, Danielle Monegalha; Almeida, Ivan Pedro Salati de

2009-01-01

The main objective of this paper is to identify the most important characteristics required for the qualification of local communities for participating in the process of defining a specific site for a radioactive waste repository. It also compares the strategies used by Hungary, United Kingdom and Belgium to stimulate the public participation in the decision-making process of building and operating a radioactive waste repository, considering both the stepwise process and the spontaneous candidacy. Two main aspects are discussed as prerequisites to constitute a qualified public. The first aspect is how well the person or entity can be considered an effective representative of the community affected by the repository. This means the conditions the representative has to speak on behalf of the community and participate in the decision making process as its voice. The second characteristic is the level and quality of the information that the community and its representatives must have to participate actively in the decision-making process and what can be done to improve this status. Referring to the strategy to public involvement, this paper discusses the importance of transparency in the process, aiming the credibility of the entrepreneur as the first pace to gaining the confidence of the public affected by the project. Implementing an open dialog and listening to the needs and claims of the population are the first steps to being accepted as a true partner of the community. Preliminary discussions and explanations are important to introduce the subject and to reduce beliefs of false threats in the affected community. The constitution of a local committee is suggested, to act as a legal and formal channel to facilitate the partnership between local community, neighbors and the entrepreneur in order to achieve a positive result in the whole process. (author)

Public participation in the process of decision making related to site selection of low and intermediate radioactive waste repository

International Nuclear Information System (INIS)

Cerskov Klika, M.

1994-01-01

This paper presents the work with public related to the acceptance of low and intermediate radioactive waste disposal facility in the Republic of Croatia. Activities performing in the field of public relations in the Hazardous Waste Management Agency - APO have been described. The fact that all the important decisions on site selections and constructions of different facilities, frequently controversial, were made in the former system without involvement of the public, makes them more significant. Therefore, the public is afraid of being cheated and manipulated again. In order to represent APO not only as the expert ecologically interested actor in the decision-making process on site selection, the study on forming the ecological image of the agency, has been done. In accordance with the results of the study, the activities related to the permanent informing and educating of the public, are being performed. In the end, it has been concluded that it is not enough to inform the public properly, accurately and timely, but it is necessary to educate the public too, because only in the way the public can be thoroughly involved in the decision-making process on site selection of radioactive waste disposal

Olkiluoto site description 2011

International Nuclear Information System (INIS)

2012-12-01

This fourth version of the Olkiluoto Site Report, produced by the OMTF (Olkiluoto Modelling Task Force), updates the Olkiluoto Site Report 2008 with the data and knowledge obtained up to December 2010. A descriptive model of the site (the Site Descriptive Model, SDM), i.e. a model describing the geological and hydrogeological structure of the site, properties of the bedrock and the groundwater and its flow, and the associated interacting processes and mechanisms. The SDM is divided into six parts: surface system, geology, rock mechanics, hydrogeology, hydrogeochemistry and transport properties

Olkiluoto site description 2011

Energy Technology Data Exchange (ETDEWEB)

NONE

2012-12-15

This fourth version of the Olkiluoto Site Report, produced by the OMTF (Olkiluoto Modelling Task Force), updates the Olkiluoto Site Report 2008 with the data and knowledge obtained up to December 2010. A descriptive model of the site (the Site Descriptive Model, SDM), i.e. a model describing the geological and hydrogeological structure of the site, properties of the bedrock and the groundwater and its flow, and the associated interacting processes and mechanisms. The SDM is divided into six parts: surface system, geology, rock mechanics, hydrogeology, hydrogeochemistry and transport properties.

MUNICIPAL LANDFILL SITE SELECTION FOR ISFAHAN CITY BY USE OF FUZZY LOGIC AND ANALYTIC HIERARCHY PROCESS

Directory of Open Access Journals (Sweden)

A. Afzali

2011-09-01

Full Text Available Selecting the most suitable site for landfill can avoid any ecological and socio-economical effects. The increase in industrial and economical development along with the increase of population growth in Isfahan city generates tremendous amount of solid waste within the region. Factors such as the scarcity of land, life span of landfill, and environmental considerations warrant that the scientific and fundamental studies are carried in selecting the suitability of a landfill site. The analysis of spatial data and consideration of regulations, and accepted criteria are part of the important elements in the site selection. The present study presents a multi criteria evaluation method using GIS technique for landfill suitability site evaluation. The Analytic Hierarchy Process (AHP was used for weighing the information layers. By using the fuzzy logic method (classification of suitable areas in the range of 0 to 255 byte scale the superposing of the information layers related to topography, soil, water table, sensitive ecosystems, land use and geology maps was performed in the study. Only after omission of inappropriate areas, the suitability examination of the residue areas was accomplished. The application of the present method in Isfahan city shows approximately 5% of the south east and north east parts of the study area with the value of more than 220 byte scale, which are suitable for landfill establishment.

Chemistry of proposed calcination/dissolution processing of Hanford Site tank wastes

International Nuclear Information System (INIS)

Delegard, C.H.

1995-01-01

Plans exist to separate radioactive waste stored in underground tanks at the US Department of Energy's Hanford Site in south central Washington State into low-level and high-level fractions, and to immobilize the separate fractions in high-integrity vitrified forms for long-term disposal. Calcination with water dissolution has been proposed as a possible treatment for achieving low/high-level separation. Chemistry development activities conducted since 1992 with simulated and genuine tank waste show that calcination/dissolution destroys organic carbon and converts nitrate and nitrite to hydroxide and benign offgases. The process also dissolves significant quantities of bulk chemicals (aluminum, chromium, and phosphate), allowing their redistribution from the high-level to the low-level fraction. Present studies of the chemistry of calcination/dissolution processing of genuine wastes, conducted in the period October 1993 to September 1994, show the importance of sodium fluoride phosphate double salt in controlling phosphate dissolution. Peptization of waste solids is of concern if extensive washing occurs. Strongly oxidizing conditions imposed by calcination reactions were found to convert transition metals to soluble anions in the order chromate > manganate > > ferrate. In analogy with manganese behavior, plutonium dissolution, presumably by oxidation to more soluble anionic species, also occurs by calcination/dissolution. Methods to remove plutonium from the product low-level solution stream must be developed

Small Wind Site Assessment Guidelines

Energy Technology Data Exchange (ETDEWEB)

Olsen, Tim [Advanced Energy Systems LLC, Eugene, OR (United States); Preus, Robert [National Renewable Energy Lab. (NREL), Golden, CO (United States)

2015-09-01

Site assessment for small wind energy systems is one of the key factors in the successful installation, operation, and performance of a small wind turbine. A proper site assessment is a difficult process that includes wind resource assessment and the evaluation of site characteristics. These guidelines address many of the relevant parts of a site assessment with an emphasis on wind resource assessment, using methods other than on-site data collection and creating a small wind site assessment report.

Data Validation Package October 2016 Groundwater and Surface Water Sampling at the Monticello, Utah, Disposal and Processing Sites January 2017

Energy Technology Data Exchange (ETDEWEB)

Nguyen, Jason [USDOE Office of Legacy Management (LM), Washington, DC (United States); Smith, Fred [Navarro Research and Engineering, Inc., Grand Junction, CO (United States)

2017-02-01

Sampling Period: October 10–12, 2016. This semiannual event includes sampling groundwater and surface water at the Monticello Disposal and Processing Sites. Sampling and analyses were conducted as specified in the Sampling and Analysis Plan for U.S. Department of Energy Office of Legacy Management Sites (LMS/PRO/S04351, continually updated) and Program Directive MNT-2016-01. Samples were collected from 54 of 64 planned locations (16 of 17 former mill site wells, 15 of 18 downgradient wells, 7 of 9 downgradient permeable reactive barrier wells, 3 of 3 bedrock wells, 4 of 7 seeps and wetlands, and 9 of 10 surface water locations).

Site Management Guide (Blue Book)

International Nuclear Information System (INIS)

2014-01-01

The U.S. Department of Energy (Department) Office of Legacy Management (LM), established in 2003, manages the Department's postclosure responsibilities and ensures the future protection of human health and the environment. During World War II and the Cold War, the Federal government developed and operated a vast network of industrial facilities for the research, production, and testing of nuclear weapons, as well as other scientific and engineering research. These processes left a legacy of radioactive and chemical waste, environmental contamination, and hazardous facilities and materials at well over 100 sites. Since 1989, the Department has taken an aggressive accelerated cleanup approach to reduce risks and cut costs. At most Departmental sites undergoing cleanup, some residual hazards will remain at the time cleanup is completed due to financial and technical impracticality. However, the Department still has an obligation to protect human health and the environment after cleanup is completed. LM fulfills DOE's postclosure obligation by providing long-term management of postcleanup sites which do not have continuing missions. LM is also responsible for sites under the Formerly Utilized Sites Remedial Action Program (FUSRAP). Currently, the U.S. Army Corps of Engineers (USACE) is responsible for site surveys and remediation at FUSRAP sites. Once remediation is completed, LM becomes responsible for long-term management. LM also has responsibility for uranium processing sites addressed by Title II of the Uranium Mill Tailings Radiation Control Act (UMTRCA). UMTRCA Title II sites are sites that were commercially owned and are regulated under a U.S. Nuclear Regulatory Commission (NRC) license. For license termination, the owner must conduct an NRC-approved cleanup of any on-site radioactive waste remaining from former uranium ore-processing operations. The site owner must also provide full funding for inspections and, if necessary, ongoing maintenance. Once site

Applicability of the Linear Sorption Isotherm Model to Represent Contaminant Transport Processes in Site Wide Performance Assessments

International Nuclear Information System (INIS)

FOGWELL, T.W.; LAST, G.V.

2003-01-01

The estimation of flux of contaminants through the vadose zone to the groundwater under varying geologic, hydrologic, and chemical conditions is key to making technically credible and sound decisions regarding soil site characterization and remediation, single-shell tank retrieval, and waste site closures (DOE 2000). One of the principal needs identified in the science and technology roadmap (DOE 2000) is the need to improve the conceptual and numerical models that describe the location of contaminants today, and to provide the basis for forecasting future movement of contaminants on both site-specific and site-wide scales. The State of Knowledge (DOE 1999) and Preliminary Concepts documents describe the importance of geochemical processes on the transport of contaminants through the Vadose Zone. These processes have been identified in the international list of Features, Events, and Processes (FEPs) (NEA 2000) and included in the list of FEPS currently being developed for Hanford Site assessments (Soler et al. 2001). The current vision for Hanford site-wide cumulative risk assessments as performed using the System Assessment Capability (SAC) is to represent contaminant adsorption using the linear isotherm (empirical distribution coefficient, K d ) sorption model. Integration Project Expert Panel (PEP) comments indicate that work is required to adequately justify the applicability of the linear sorption model, and to identify and defend the range of K d values that are adopted for assessments. The work plans developed for the Science and Technology (S and T) efforts, SAC, and the Core Projects must answer directly the question of ''Is there a scientific basis for the application of the linear sorption isotherm model to the complex wastes of the Hanford Site?'' This paper is intended to address these issues. The reason that well documented justification is required for using the linear sorption (K d ) model is that this approach is strictly empirical and is often

Process design and economics of on-site cellulase production on various carbon sources in a softwood-based ethanol plant.

Science.gov (United States)

Barta, Zsolt; Kovacs, Krisztina; Reczey, Kati; Zacchi, Guido

2010-06-28

On-site cellulase enzyme fermentation in a softwood-to-ethanol process, based on SO(2)-catalysed steam pretreatment followed by simultaneous saccharification and fermentation, was investigated from a techno-economic aspect using Aspen Plus© and Aspen Icarus Process Evaluator© softwares. The effect of varying the carbon source of enzyme fermentation, at constant protein and mycelium yields, was monitored through the whole process. Enzyme production step decreased the overall ethanol yield (270 L/dry tonne of raw material in the case of purchased enzymes) by 5-16 L/tonne. Capital cost was found to be the main cost contributor to enzyme fermentation, constituting to 60-78% of the enzyme production cost, which was in the range of 0.42-0.53 SEK/L ethanol. The lowest minimum ethanol selling prices (4.71 and 4.82 SEK/L) were obtained in those scenarios, where pretreated liquid fraction supplemented with molasses was used as carbon source. In some scenarios, on-site enzyme fermentation was found to be a feasible alternative.

HOW DO STUDENTS SELECT SOCIAL NETWORKING SITES? AN ANALYTIC HIERARCHY PROCESS (AHP) MODEL

OpenAIRE

Chun Meng Tang; Miang Hong Ngerng

2015-01-01

Social networking sites are popular among university students, and students today are indeed spoiled for choice. New emerging social networking sites sprout up amid popular sites, while some existing ones die out. Given the choice of so many social networking sites, how do students decide which one they will sign up for and stay on as an active user? The answer to this question is of interest to social networking site designers and marketers. The market of social networking sites is highly co...

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

The Hanford Site solid waste treatment project; Waste Receiving and Processing (WRAP) Facility

International Nuclear Information System (INIS)

Roberts, R.J.

1991-01-01

The Waste Receiving and Processing (WRAP) Facility will provide treatment and temporary storage (consisting of in-process storage) for radioactive and radioactive/hazardous mixed waste. This facility must be constructed and operated in compliance with all appropriate US Department of Energy (DOE) orders and Resource Conservation and Recovery Act (RCRA) regulations. The WRAP Facility will examine and certify, segregate/sort, and treat for disposal suspect transuranic (TRU) wastes in drums and boxes placed in 20-yr retrievable storage since 1970; low-level radioactive mixed waste (RMW) generated and placed into storage at the Hanford Site since 1987; designated remote-handled wastes; and newly generated TRU and RMW wastes from high-level waste (HLW) recovery and processing operations. In order to accelerated the WRAP Project, a partitioning of the facility functions was done in two phases as a means to expedite those parts of the WRAP duties that were well understood and used established technology, while allowing more time to better define the processing functions needed for the remainder of WRAP. The WRAP Module 1 phase one, is to provide the necessary nondestructive examination and nondestructive assay services, as well as all transuranic package transporter (TRUPACT-2) shipping for both WRAP Project phases, with heating, ventilation, and air conditioning; change rooms; and administrative services. Phase two of the project, WRAP Module 2, will provide all necessary waste treatment facilities for disposal of solid wastes. 1 tab

March 2016 Memo: Planning for Removal and Remedial Activities at Hardrock Mining and Mineral Processing Sites with Fluid Hazards

Science.gov (United States)

Memo from EPA Assistant Administrator Mathy Stanislaus, regarding planning for removal and remedial activities at hardrock mining and mineral processing sites with fluid hazards, and to share the Agency’s expectations for the work that is done at these sit

Molecular Characterization of the Processing of Arenavirus Envelope Glycoprotein Precursors by Subtilisin Kexin Isozyme-1/Site-1 Protease

Science.gov (United States)

Burri, Dominique J.; Pasqual, Giulia; Rochat, Cylia; Seidah, Nabil G.

2012-01-01

A crucial step in the life cycle of arenaviruses is the biosynthesis of the mature fusion-active viral envelope glycoprotein (GP) that is essential for virus-host cell attachment and entry. The maturation of the arenavirus GP precursor (GPC) critically depends on proteolytic processing by the cellular proprotein convertase (PC) subtilisin kexin isozyme-1 (SKI-1)/site-1 protease (S1P). Here we undertook a molecular characterization of the SKI-1/S1P processing of the GPCs of the prototypic arenavirus lymphocytic choriomeningitis virus (LCMV) and the pathogenic Lassa virus (LASV). Previous studies showed that the GPC of LASV undergoes processing in the endoplasmic reticulum (ER)/cis-Golgi compartment, whereas the LCMV GPC is cleaved in a late Golgi compartment. Herein we confirm these findings and provide evidence that the SKI-1/S1P recognition site RRLL, present in the SKI-1/S1P prodomain and LASV GPC, but not in the LCMV GPC, is crucial for the processing of the LASV GPC in the ER/cis-Golgi compartment. Our structure-function analysis revealed that the cleavage of arenavirus GPCs, but not cellular substrates, critically depends on the autoprocessing of SKI-1/S1P, suggesting differences in the processing of cellular and viral substrates. Deletion mutagenesis showed that the transmembrane and intracellular domains of SKI-1/S1P are dispensable for arenavirus GPC processing. The expression of a soluble form of the protease in SKI-I/S1P-deficient cells resulted in the efficient processing of arenavirus GPCs and rescued productive virus infection. However, exogenous soluble SKI-1/S1P was unable to process LCMV and LASV GPCs displayed at the surface of SKI-I/S1P-deficient cells, indicating that GPC processing occurs in an intracellular compartment. In sum, our study reveals important differences in the SKI-1/S1P processing of viral and cellular substrates. PMID:22357276

SiteChar – Methodology for a Fit-for-Purpose Assessment of CO2 Storage Sites in Europe

Directory of Open Access Journals (Sweden)

Delprat-Jannaud F.

2015-04-01

Full Text Available The FP7-funded SiteChar project examined the entire CO2 geological storage site characterisation process, from the initial feasibility studies through to the final stage of application for a CO2 storage permit based on criteria defined by the relevant European legislation. The SiteChar workflow for CO2 geological storage site characterisation provides a description of all elements of a site characterisation study, as well as guidance to streamline the site characterisation process and make sure that the output covers the aspects mentioned in the European Community (EC Storage Directive. Five potential European storage sites, representative of prospective geological contexts, were considered as test sites for the research work: a North Sea multi-store site (hydrocarbon field and aquifer offshore Scotland; an onshore aquifer in Denmark; an onshore gas field in Poland; an aquifer offshore in Norway; and an aquifer in the Southern Adriatic Sea. This portfolio combines complementary sites that allowed to encompass the different steps of the characterisation workflow. A key innovation was the development of internal ‘dry-run’ permit applications at the Danish and Scottish sites and their review by relevant regulatory authorities. This process helped to refine the site characterisation workflow, and aimed to identify remaining gaps in site-specific characterisation, needed to secure storage permits under the EC Storage Directive as implemented in ‘host’ Member States. SiteChar considered the important aspect of the public awareness and public opinions of these new technologies, in parallel to technical issues, on the onshore Polish and offshore Scottish sites. A new format to assist public opinion-forming processes was tested involving a small sample of local communities. Generic as well as site-specific information was made available to the general and local public via the internet and at information meetings. These exercises provide insight

Comparative Analysis of Site-Selection Process for Power Plants in Korea: Cases of Thermal, Nuclear, and Renewable Energies

International Nuclear Information System (INIS)

Kang, M.; Lee, M.; Yoon, J. W.; Choi, H. C.; Chu, C.; Lee, H.; Park, J.

2017-01-01

There are various conflicts related to power generation facilities; however, the conflicts that arise during the process of luring facilities or site selection, as in the previous cases, can eventually influence greatly the implementation of the national energy policy or strategy. This study analyzed the conflict phenomenon that occurred in the site selection policy of the power generation facilities through the case studies. We selected the most recent conflict cases by each energy source, identified the qualitative context characteristics of the cases and tried to suggest the policy leverages. In this study, it is concluded that the cause of conflicts in decision making system for site selection of power plants is insufficient yet due to the variable circumstances such as environmental events, stakeholder range, etc. However, the conclusions obtained from the case study are difficult generalization without specific prescription books, so further studies for those areas are required.

Site observational work plan for the UMTRA Project Site at Tuba City, Arizona

International Nuclear Information System (INIS)

1994-09-01

The requirements for ground water compliance for Uranium Mill Tailings Remedial Action (UMTRA) Project sites, including the Tuba City, Arizona, site, are found in the Uranium Mill Tailings Radiation Control Act; Subparts B and C of the U.S. Environmental Protection Agency's Health and Environmental Protection Standards for Uranium and Thorium Mill Tailings (40 CFR 192 (1994)), and the associated proposed 1987 standards (52 FR 36000). During the surface remedial action, an estimated 1,400,000 cubic yards (yd 3 ) (1,100,000 cubic meters [m 3 ]) of uranium mill tailings and other contaminated materials were consolidated and stabilized in place in an unlined disposal cell covering 50 acres (20 hectares). The surface remedial action was completed in April 1990. Ground water beneath the Tuba City site was contaminated by subsurface migration of water from uranium ore processing activities. The main source of contaminants was water from the tailings piles that began in 1956 when the mill opened and ended in 1966 when the mill closed. A total of 800,000 tons (725,000 tonnes) of uranium ore were processed onsite over a 10-year period. Two processes were used to refine the ore: an acid leach process and a sodium carbonate alkaline process. Water from these tailings then seeped into the ground and migrated downward to the ground water. The Tuba City site is currently in a post-stabilization, prelicensing status. The preliminary ground water compliance strategy at the Tuba City site is active remediation. The specific technology to be evaluated is in situ bioremediation. This selection was made because of the potential ability of bioremediation to reduce concentrations to lower levels than a conventional extraction system and to minimize disturbance of the water resource

Hanford Site Development Plan

International Nuclear Information System (INIS)

Hathaway, H.B.; Daly, K.S.; Rinne, C.A.; Seiler, S.W.

1992-05-01

The Hanford Site Development Plan (HSDP) provides an overview of land use, infrastructure, and facility requirements to support US Department of Energy (DOE) programs at the Hanford Site. The HSDP's primary purpose is to inform senior managers and interested parties of development activities and issues that require a commitment of resources to support the Hanford Site. The HSDP provides a land use plan for the Hanford Site and presents a picture of what is currently known and anticipated in accordance with DOE Order 4320.1B. Site Development Planning. The HSDP wig be updated annually as future decisions further shape the mission and overall site development process. Further details about Hanford Site development are defined in individual area development plans

Effects of radiation on the chemical environment surrounding waste canisters in proposed repository sites and possible effects on the corrosion process

International Nuclear Information System (INIS)

Glass, R.S.

1981-12-01

This report explores the interaction of ionizing radiation with various environments. In particular, worst case (aqueous) environments for the proposed nuclear waste repository sites are considered. Emphasis is on the fundamental chemical and physical processes involved. The identities of possible radiolysis products (both transient and stable) have been sought through a literature search. The effect of radiation on corrosion processes is discussed. The radiation-induced chemical environment in the worst case repository sites is not well defined. Attention should therefore be given to fundamental studies exploring the interaction of such environments with components of the nuclear waste package, including the canister materials and backfills. Identification and quantification of radiolysis products would be helpful in this regard

Remedial investigation of the High-Explosives (HE) Process Area, Lawrence Livermore National Laboratory Site 300

Energy Technology Data Exchange (ETDEWEB)

Crow, N.B.; Lamarre, A.L.

1990-08-01

This report presents the results of a Remedial Investigation (RI) to define the extent of high explosives (HE) compounds and volatile organic compounds (VOCs) found in the soil, rocks, and ground water of the HE Process Area of Lawrence Livermore National Laboratory's (LLNL) Site 300 Facility. The report evaluates potential public health environmental risks associated with these compounds. Hydrogeologic information available before February 15, 1990, is included; however, chemical analyses and water-level data are reported through March 1990. This report is intended to assist the California Regional Water Quality Control Board (RWQCB)--Central Valley Region and the US Environmental Protection Agency (EPA) in evaluating the extent of environmental contamination of the LLNL HE Process Area and ultimately in designing remedial actions. 90 refs., 20 figs., 7 tabs.

Finding of no significant impact proposed remedial action at two uranium processing sites near Slick Rock, Colorado

International Nuclear Information System (INIS)

1994-01-01

The U.S. Department of Energy (DOE) has prepared an environmental assessment (EA) (DOE/EA-0339) of the proposed remedial action at two uranium processing sites near Slick Rock in San Miguel County, Colorado. These sites contain radioactively contaminated materials that would be removed and stabilized at a remote location. Based on the information and analyses in the EA, the DOE has determined that the proposed action does not constitute a major Federal action significantly affecting the quality of the human environment within the meaning of the National Environmental Policy Act (NEPA) of 1969 (42 U.S.C. 4321 et seq.), as amended. Therefore, preparation of an environmental impact statement is not required, and the DOE is issuing this Finding of No Significant Impact (ONSI)

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.

Societal and Political Issues of Site Selection Process Development for the LILW Repository in Slovenia

Energy Technology Data Exchange (ETDEWEB)

Polic, Marko; KoS, Drago [Univ. of Ljubljana (Slovenia); Zeleznik, Nadja [ARAO, Ljubljana (Slovenia)

2006-09-15

The siting of the radioactive waste repository, even the low and intermediate level radioactivity waste (LILW), presents a great problem in almost every country that produces these materials. Attempts to locate a disposal facility in Slovenia have until now proven unsuccessful. After the failure of the first 'technocratic' approach it became evident that the main problem was not a technical one, but socio-psychological, namely the public acceptability of any radioactive waste disposal facility (RWD). In general people strongly oppose to any kind of such a facility in their vicinity and exhibit a 'Not in my Backyard' (NIMBY) attitude even if they are aware of its necessity. However there are slight signs of changes especially in argumentation supporting the public denial of LIL RWD. The main LILW producer in Slovenia is nuclear power plant in Krsko (NEK). The project for the construction of this plant did not include consideration of the LIL RWD while at that time plans for new NPP's in Yugoslavia with a centralized LILW repository were present. The search for possible locations of LILW repository started only after the beginning of its commercial operation in 1983. The general development of radioactive waste management (RWM) issue in Slovenia was similar to the development in other developed countries, while its details and context differ in smaller or greater degree due to different cultural, political, social and economic backgrounds. The RWM process was following the same general course: technological approach neglecting public issues - public reactance - move toward public involvement. All this was accompanied by the relevant public attitudes: neutrality - rejection - eventual conditional public acceptance. The procedure to find a LILW repository is proposed and established, but the processes leading to final solution are going on without being completely foreseen yet. The general underlying view is connected to the fear of

Societal and Political Issues of Site Selection Process Development for the LILW Repository in Slovenia

International Nuclear Information System (INIS)

Polic, Marko; KoS, Drago; Zeleznik, Nadja

2006-01-01

The siting of the radioactive waste repository, even the low and intermediate level radioactivity waste (LILW), presents a great problem in almost every country that produces these materials. Attempts to locate a disposal facility in Slovenia have until now proven unsuccessful. After the failure of the first 'technocratic' approach it became evident that the main problem was not a technical one, but socio-psychological, namely the public acceptability of any radioactive waste disposal facility (RWD). In general people strongly oppose to any kind of such a facility in their vicinity and exhibit a 'Not in my Backyard' (NIMBY) attitude even if they are aware of its necessity. However there are slight signs of changes especially in argumentation supporting the public denial of LIL RWD. The main LILW producer in Slovenia is nuclear power plant in Krsko (NEK). The project for the construction of this plant did not include consideration of the LIL RWD while at that time plans for new NPP's in Yugoslavia with a centralized LILW repository were present. The search for possible locations of LILW repository started only after the beginning of its commercial operation in 1983. The general development of radioactive waste management (RWM) issue in Slovenia was similar to the development in other developed countries, while its details and context differ in smaller or greater degree due to different cultural, political, social and economic backgrounds. The RWM process was following the same general course: technological approach neglecting public issues - public reactance - move toward public involvement. All this was accompanied by the relevant public attitudes: neutrality - rejection - eventual conditional public acceptance. The procedure to find a LILW repository is proposed and established, but the processes leading to final solution are going on without being completely foreseen yet. The general underlying view is connected to the fear of radioactivity and general negative

Radiological surveillance of Remedial Action activities at the processing site, Ambrosia Lake, New Mexico, April 12--16, 1993. Final report

International Nuclear Information System (INIS)

1993-04-01

The Uranium Mill Tailings Remedial Action (UMTRA) Project's Technical Assistance Contractor (TAC) performed a radiological surveillance of the Remedial Action Contractor (RAC), MK-Ferguson and CWM Federal Environmental Services, Inc., at the processing site in Ambrosia Lake, New Mexico. The requirements and attributes examined during the audit were developed from reviewing working-level procedures developed by the RAC. Objective evidence, comments, and observations were verified based on investigating procedures, documentation, records located at the site, personal interviews, and tours of the site. No findings were identified during this audit. Ten site-specific observations, three good practice observations, and five programmatic observations are presented in this report. The overall conclusion from the surveillance is that the radiological aspects of the Ambrosia Lake, New Mexico, remedial action program are performed adequately. The results of the good practice observations indicate that the site health physics (HP) staff is taking the initiative to address and resolve potential issues, and implement suggestions useful to the UMTRA Project. However, potential exists for improving designated storage areas for general items, and the RAC Project Office should consider resolving site-specific and procedural inconsistencies

Site observational work plan for the UMTRA Project site at Tuba City, Arizona

International Nuclear Information System (INIS)

1994-09-01

The requirements for ground water compliance for Uranium Mill Tailings Remedial Action (UMTRA) Project sites, including the Tuba City, Arizona, site, are found in the Uranium Mill Tailings Radiation Control Act; Subparts B and C of the U.S. Environmental Protection Agency's Health and Environmental Protection Standards for Uranium and Thorium Mill Tailings (40 CFR 192 (1994)), and the associated proposed 1987 standards (52 FR 36000). During the surface remedial action, an estimated 1,400,000 cubic yards (yd 3 ) (1,100,000 cubic meters [m 3 ]) of uranium mill tailings and other contaminated materials were consolidated and stabilized in place in an unlined disposal cell covering 50 acres (20 hectares). The surface remedial action was completed in April 1990. Ground water beneath the Tuba City site was contaminated by subsurface migration of water from uranium ore processing activities. The main source of contaminants was water from the tailings piles that began in 1956 when the mill opened and ended in 1966 when the mill closed. 800,000 tons (725,000 tonnes) of uranium ore were processed onsite over a 10-year period. The wet tailings remaining after processing were placed as a slurry in three piles at the site. Water from these tailings then seeped into the ground and migrated downward to the ground water. The Tuba City site is currently in a post-stabilization, prelicensing status. The site is expected to remain in this status until licensed by the U.S. Nuclear Regulatory Commission (NRC) for long-term surveillance and maintenance. The preliminary ground water compliance strategy at the Tuba City site is active remediation-specific technology to be evaluated is in situ bioremediation. This selection was made because of the potential ability of bioremediation to reduce concentrations to lower levels than a conventional extraction system and to minimize disturbance of the water resource

Evaluation of natural attenuation processes in the groundwater of a tar oil contaminated site: development of a monitoring network

International Nuclear Information System (INIS)

Borke, P.; Husers, N.; Werner, P.; Leibenath, C.

2005-01-01

Tar oil is a complex mixture of mainly aromatic hydrocarbons. It is found in the subsurface of manufactured gas plants (MGP), coking plants or wood preserving facilities. The transportation into the soil and groundwater stands for a severe contamination. This is due to the physico-chemical properties of the DNAPL (dense non aqueous phase liquid) and its mobility in the soil and aquifer system. Additionally most of the contaminants show a low biological degradability and solubility under in situ conditions. Therefore it is known as a long term source of contamination. Nevertheless, natural attenuation (NA) processes are detectable at tar oil contaminated sites. In the thematic network two of the German funding priority KORA (http://www.natural-attenuation.de) these processes are matter of investigation. Four typical contaminated sites were chosen to evaluate under which circumstances monitored natural attenuation (MNA) is applicable. Furthermore enhanced natural attenuation questions are examined. The design of monitoring networks at tar oil contaminated sites plays a significant role in gaining field evidence for natural attenuation as well as documenting the efficiency of the attenuation processes and evaluating the matching of performance goals. Well designed monitoring networks include the placement of monitoring wells in 3D so that 3D flow path, mass balances and an estimation of mass flux can be monitored. As an example the history of the monitoring network of a wood preserving facility is shown. Starting from a risk assessment network to a network for MNA is presented. In this case for example especially the determination of the groundwater flow direction in time and space is connected to the number of observation wells and their location. Moreover in the beginning the observation wells were located according to the assumed centerline of the plume. Because of the variability of the groundwater flow direction and the need to determine mass flux a control plane

Environmental assessment of remedial action at the Naturita Uranium processing site near Naturita, Colorado. Revision 1

Energy Technology Data Exchange (ETDEWEB)

1993-08-01

The proposed remedial action for the Naturita processing site is relocation of the contaminated materials and debris to the Dry Flats disposal site, 6 road miles (mi) [ 1 0 kilometers (km)] to the southeast. At the disposal site, the contaminated materials would be stabilized and covered with layers of earth and rock. The proposed disposal site is on land administered by the Bureau of Land Management (BLM) and used primarily for livestock grazing. The final disposal site would cover approximately 57 ac (23 ha), which would be permanently transferred from the BLM to the DOE and restricted from future uses. The remedial action activities would be conducted by the DOE`s Uranium Mill Tailings Remedial Action (UMTRA) Project. The remedial action would result in the loss of approximately 164 ac (66 ha) of soils, but 132 ac (53 ha) of these soils are contaminated and cannot be used for other purposes. Another 154 ac (62 ha) of soils would be temporarily disturbed. Approximately 57 ac (23 ha) of open range land would be permanently removed from livestock grazing and wildlife use. The removal of the contaminated materials would affect the 1 00-year floodplain of the San Miguel River and would result in the loss of riparian habitat along the river. The southwestern willow flycatcher, a Federal candidate species, may be affected by the remedial action, and the use of water from the San Miguel River ``may affect`` the Colorado squawfish, humpback chub, bonytail chub, and razorback sucker. Traffic levels on State Highways 90 and 141 would be increased during the remedial action, as would the noise levels along these transportation routes. Measures for mitigating the adverse environmental impacts of the proposed remedial action are discussed in Section 6.0 of this environmental assessment (EA).

Independent assessment to continue improvement: Implementing statistical process control at the Hanford Site

International Nuclear Information System (INIS)

Hu, T.A.; Lo, J.C.

1994-11-01

A Quality Assurance independent assessment has brought about continued improvement in the PUREX Plant surveillance program at the Department of Energy's Hanford Site. After the independent assessment, Quality Assurance personnel were closely involved in improving the surveillance program, specifically regarding storage tank monitoring. The independent assessment activities included reviewing procedures, analyzing surveillance data, conducting personnel interviews, and communicating with management. Process improvement efforts included: (1) designing data collection methods; (2) gaining concurrence between engineering and management, (3) revising procedures; and (4) interfacing with shift surveillance crews. Through this process, Statistical Process Control (SPC) was successfully implemented and surveillance management was improved. The independent assessment identified several deficiencies within the surveillance system. These deficiencies can be grouped into two areas: (1) data recording and analysis and (2) handling off-normal conditions. By using several independent assessment techniques, Quality Assurance was able to point out program weakness to senior management and present suggestions for improvements. SPC charting, as implemented by Quality Assurance, is an excellent tool for diagnosing the process, improving communication between the team members, and providing a scientific database for management decisions. In addition, the surveillance procedure was substantially revised. The goals of this revision were to (1) strengthen the role of surveillance management, engineering and operators and (2) emphasize the importance of teamwork for each individual who performs a task. In this instance we believe that the value independent assessment adds to the system is the continuous improvement activities that follow the independent assessment. Excellence in teamwork between the independent assessment organization and the auditee is the key to continuing improvement

Canada's deep geological repository for used nuclear fuel - site selection process update

International Nuclear Information System (INIS)

Facella, J.

2014-01-01

In 2007, the Government of Canada selected Adaptive Phased Management as Canada's plan for the long-term management of Canada's used nuclear fuel in a deep geological repository, located in an informed and willing host. The process of site selection is an important milestone in this program. The NWMO describes its approach to working collaboratively with communities which expressed interest in exploring the project, as well as Aboriginal communities in the area and other surrounding communities. The project is designed to be implemented through a long-term partnership involving the interested community, Aboriginal communities and surrounding communities working with the NWMO. (author)

Global positioning site environment evaluator

International Nuclear Information System (INIS)

Leffler, S.; Reeser, H.G.; Zaker, E.; Hansen, W.; Sikorski, R.W.

1990-01-01

Development of an innovative, integrated, automated system (Global Positioning Site Environment Evaluator - GPSEETM) for surveying contaminated waste sites is described. This system makes novel use of the Global Positioning System (GPS) satellite constellation for establishing specific locations and current times for surveying radioactive, hazardous, or mixed-waste sites. GPSEE may also be used for waste site contamination surveys after remediation activities to ensure environmental remediation is complete. A base station is established for collecting and recording data and directing field operations for field stations which may be located many miles from the base station. The field operators collect site surveying and contamination data utilizing a variety of chemical and radiological sensors. A major goal for the data collection process is to collect all data utilizing in situ sensors, thereby minimizing the need for collecting soil and water samples. Site contamination data is transmitted electronically to the base station for recording and processing. The GPSEE system is being developed for use at DOE/DOD and a variety of industrial facilities. 3 figs

Site characterization plan:

International Nuclear Information System (INIS)

1988-01-01

The Yucca Mountain site in Nevada is one of three candidate sites for the first geologic repository for radioactive waste. On May 28, 1986, it was recommended for detailed study in a program of site characterization. This site characterization plan (SCP) has been prepared in accordance with the requirements of the Nuclear Waste Policy Act to summarize the information collected to date about the geologic conditions at the site;to describe the conceptual designs for the repository and the waste package;and to present the plans for obtaining the geologic information necessary to demonstrate the suitability of the site for repository, to design the repository and the waste package, to prepare an environmental impact statement, and to obtain from the US Nuclear Regulatory Commission (NRC) an authorization to construct the repository. This introduction begins with a brief section on the process for siting and developing a repository, followed by a discussion of the pertinent legislation and regulations. A description of site characterization is presented next;it describes the facilities to be constructed for the site characterization program and explains the principal activities to be conducted during the program. Finally, the purpose, content, organizing principles, and organization of this site characterization plan are outlined, and compliance with applicable regulations is discussed

The french low-level waste disposal site 'Centre de l'Aube'. A ten years process, from geological concept to waste deliveries

International Nuclear Information System (INIS)

Fernique, J.C.

1993-01-01

The 'Centre de la Manche', first French low-level waste disposal site opened in 1969 and will enter the institutional control period around 1994. A creation process for a new disposal was initiated in 1981 when ANDRA prepared a general radioactive waste management Program and presented it to the High Council for Nuclear Safety and Information. After acceptance of the Program, a national site screening was made, based on a conceptual geological model designed from the experience. In 1984, the Minister of Industry announced the pre-selection of 3 counties out of the inventory for preliminary studies that allowed to select l' Aube as a potential site for the new French disposal 'Centre de l'Aube'. The different steps of the process and procedure that brought to the acceptance of the first packages in January 1992 is presented in the paper, as well as the experience recently gained since that date. This additional know-how and expertise is made available by Andra through agreements already existing with various Countries like, among others, Spain, the United States, and Mexico

Processing and geologic analysis of conventional cores from well ER-20-6 No. 1, Nevada Test Site

International Nuclear Information System (INIS)

Prothro, L.B.; Townsend, M.J.; Drellack, S.L. Jr

1997-09-01

In 1996, Well Cluster ER-20-6 was drilled on Pahute Mesa in Area 20, in the northwestern corner of the Nevada Test Site (NTS). The three wells of the cluster are located from 166 to 296 meters (m) (544 to 971 feet [ft]) southwest of the site of the underground nuclear test code-named BULLION, conducted in 1990 in Emplacement Hole U-20bd. The well cluster was planned to be the site of a forced-gradient experiment designed to investigate radionuclide transport in groundwater. To obtain additional information on the occurrence of radionuclides, nature of fractures, and lithology, a portion of Well ER-20-6 No. 1, the hole closest to the explosion cavity, was cored for later analysis. Bechtel Nevada (BN) geologists originally prepared the geologic interpretation of the Well Cluster ER-20-6 site and documented the geology of each well in the cluster. However, the cores from Well ER-20-6 No. 1 were not accessible at the time of that work. As the forced-gradient experiment and other radio nuclide migration studies associated with the well cluster progressed, it was deemed appropriate to open the cores, describe the geology, and re-package the core for long-term air-tight storage. This report documents and describes the processing, geologic analysis, and preservation of the conventional cores from Well ER20-6 No. 1

Processing and geologic analysis of conventional cores from well ER-20-6 No. 1, Nevada Test Site

Energy Technology Data Exchange (ETDEWEB)

Prothro, L.B., Townsend, M.J.; Drellack, S.L. Jr. [and others

1997-09-01

In 1996, Well Cluster ER-20-6 was drilled on Pahute Mesa in Area 20, in the northwestern corner of the Nevada Test Site (NTS). The three wells of the cluster are located from 166 to 296 meters (m) (544 to 971 feet [ft]) southwest of the site of the underground nuclear test code-named BULLION, conducted in 1990 in Emplacement Hole U-20bd. The well cluster was planned to be the site of a forced-gradient experiment designed to investigate radionuclide transport in groundwater. To obtain additional information on the occurrence of radionuclides, nature of fractures, and lithology, a portion of Well ER-20-6 No. 1, the hole closest to the explosion cavity, was cored for later analysis. Bechtel Nevada (BN) geologists originally prepared the geologic interpretation of the Well Cluster ER-20-6 site and documented the geology of each well in the cluster. However, the cores from Well ER-20-6 No. 1 were not accessible at the time of that work. As the forced-gradient experiment and other radio nuclide migration studies associated with the well cluster progressed, it was deemed appropriate to open the cores, describe the geology, and re-package the core for long-term air-tight storage. This report documents and describes the processing, geologic analysis, and preservation of the conventional cores from Well ER20-6 No. 1.

US Department of Energy response to standards for remedial actions at inactive uranium processing sites: Proposed rule

International Nuclear Information System (INIS)

1988-01-01

The Title I groundwater standards for inactive uranium mill tailings sites, which were promulgated on January 5, 1983, by the US Environmental Protection Agency (EPA) for the Uranium Mill Tailings Remedial Action (UMTRA) Project, were remanded to the EPA on September 3, 1985, by the US Tenth Circuit Court of Appeals. The Court instructed the EPA to compile general groundwater standards for all Title I sites. On September 24, 1987, the EPA published proposed standards (52FR36000-36008) in response to the remand. This report includes an evaluation of the potential effects of the proposed EPA groundwater standards on the UMTRA Project, as well as a discussion of the DOE's position on the proposed standards. The report also contains and appendix which provides supporting information and cost analyses. In order to assess the impacts of the proposed EPA standards, this report summarizes the proposed EPA standards in Section 2.0. The next three sections assess the impacts of the three parts of the EPA standards: Subpart A considers disposal sites; Subpart B is concerned with restoration at processing sites; and Subpart C addresses supplemental standards. Section 6.0 integrates previous sections into a recommendations section. Section 7.0 contains the DOE response to questions posed by the EPA in the preamble to the proposed standards. 6 refs., 5 figs., 3 tabs

IOs as Social Sites

DEFF Research Database (Denmark)

Park, Susan M.; Vetterlein, Antje

Norms research has made significant inroads into examining their emergence and influence in international relations, while recognizing international organizations (IOs) as key social sites for norms to be created and/or disseminated. This paper interrogates how IOs as “organizational platforms......” (Finnemore 1996) influence the norm building process. Going beyond state-centric approaches to norm construction, it argues that the process of taking up a norm by an IO does affect the norm’s power. A norm’s strength is determined by the extent to which it is uncontested and taken for granted as appropriate...... the norm building process in this way provides insight into the effect of IOs as social sites in strengthening a norm....

Remedial action plan and site design for stabilization of the inactive uranium mill tailings site at Lowman, Idaho

International Nuclear Information System (INIS)

1991-09-01

The US Environmental Protection Agency (EPA) has established health and environmental regulations to correct and prevent groundwater contamination resulting from former uranium processing activities at inactive uranium processing sites (40 CFR 192). According to the Uranium Mill Tailings Radiation Control Act of 1978 (UMTRCA), the US Department of Energy (DOE) is responsible for assessing the inactive uranium processing sites. The DOE has decided that each assessment shall include information on hydrogeologic site characterization. The water resources protection strategy that describes how the proposed action will comply with the EPA groundwater protection standards is presented in Attachment 4. Site characterization activities discussed in this section include: Definition of the hydrogeologic characteristics of the environment, including hydrostratigraphy, aquifer parameters, areas of aquifer recharge and discharge, potentiometric surfaces, and groundwater velocities. Definition of background groundwater quality and comparison with the proposed EPA groundwater protection standards. Evaluation of the physical and chemical characteristics of the contaminant source and/or residual radioactive materials. Definition of existing groundwater contamination by comparison with the EPA groundwater protection standards. Description of the geochemical processes that affect the downward migration of the source contaminants at the processing site. Description of water resource utilization, including availability, current and future use and value, and alternate water supplies

Multi-Site Project Management A Program for Reducing the Cost of Technology Deployment at Department of Energy Sites

International Nuclear Information System (INIS)

Davis, N.R.; Selden, E.R.; Little, D.B.; Coleman, M.C.; Bennett, J.T.

2009-01-01

Retrieval and processing of High Level Waste (HLW) stored in Department of Energy (DOE) waste tanks is performed to support closure of the tanks as required by site specific regulatory agreements. Currently, there are four sites in the DOE Complex that have HLW tanks and must process and disposition HLW. As such, there is an opportunity to achieve an economy of scale and reduce duplication of efforts. Two or more sites typically have similar technology development and deployment needs. Technology development is already executed at the national level. As the technology is matured, the next step is to commission a design/build project. Typically each site performs this separately due to differences in waste type, tank design, site specific considerations such as proximity to the water table or to the site boundary. The focus of the individual sites tends to be on the differences between sites versus on the similarities thus there is an opportunity to minimize the cost for similar deployments. A team of engineers and project management professionals from the Savannah River Site has evaluated technology needs at the four HLW sites and determined that there is an economy of scale that can be achieved by specific technology deployments in the area of waste retrieval, waste pretreatment and waste disposition. As an example, the Waste on Wheels tank retrieval system (presented in the 2006 Waste Management Symposium) was designed and fabricated in portable modules that could be installed in HLW tanks at Hanford, Savannah River or Idaho. This same concept could be used for modular in-tank cesium removal process and equipment, tank cleaning mechanical equipment, and chemical tank cleaning process and equipment. The purpose of this paper is to present a multi-site project management approach that will reduce deployment costs and be consistent with DOE Order 413.3 project management principles. The approach will describe how projects can be managed by a lead site with

Remedial Action Plan and site design for stabilization of the inactive uranium mill tailings site at Gunnison, Colorado

International Nuclear Information System (INIS)

1992-10-01

The US Environmental Protection Agency (EPA) has established health and environmental protection regulations to correct and prevent groundwater contamination resulting from processing activities at inactive uranium milling sites (40 CFR 192). The US Department of Energy (DOE) is responsible for assessing the inactive uranium processing sites. The DOE has determined this assessment shall include information on hydrogeologic site characterization. This document contains appendices to Attachment 3, Groundwater Hydrology Report included are calculations

Life Cycle Inventory (LCI) Data-Treatment Chemicals, Construction Materials, Transportation, On-site Equipment, and Other Processes for Use in Spreadsheets for Environmental Footprint Analysis (SEFA)

Science.gov (United States)

This report estimates environmental emission factors (EmF) for key chemicals, construction and treatment materials, transportation/on-site equipment, and other processes used at remediation sites. The basis for chemical, construction, and treatment material EmFs is life cycle inv...

Electrokinetic demonstration at Sandia National Laboratories: Use of transference numbers for site characterization and process evaluation

International Nuclear Information System (INIS)

Lindgren, E.R.; Mattson, E.D.

1997-01-01

Electrokinetic remediation is generally an in situ method using direct current electric potentials to move ionic contaminants and/or water to collection electrodes. The method has been extensively studied for application in saturated clayey soils. Over the past few years, an electrokinetic extraction method specific for sandy, unsaturated soils has been developed and patented by Sandia National Laboratories. A RCRA RD ampersand D permitted demonstration of this technology for the in situ removal of chromate contamination from unsaturated soils in a former chromic acid disposal pit was operated during the summer and fall of 1996. This large scale field test represents the first use of electrokinetics for the removal of heavy metal contamination from unsaturated soils in the United States and is part of the US EPA Superfund Innovative Technology Evaluation (SITE) Program. Guidelines for characterizing a site for electrokinetic remediation are lacking, especially for applications in unsaturated soil. The transference number of an ion is the fraction of the current carried by that ion in an electric field and represents the best measure of contaminant removal efficiency in most electrokinetic remediation processes. In this paper we compare the transference number of chromate initially present in the contaminated unsaturated soil, with the transference number in the electrokinetic process effluent to demonstrate the utility of evaluating this parameter

Mature clustered, regularly interspaced, short palindromic repeats RNA (crRNA) length is measured by a ruler mechanism anchored at the precursor processing site.

Science.gov (United States)

Hatoum-Aslan, Asma; Maniv, Inbal; Marraffini, Luciano A

2011-12-27

Precise RNA processing is fundamental to all small RNA-mediated interference pathways. In prokaryotes, clustered, regularly interspaced, short palindromic repeats (CRISPR) loci encode small CRISPR RNAs (crRNAs) that protect against invasive genetic elements by antisense targeting. CRISPR loci are transcribed as a long precursor that is cleaved within repeat sequences by CRISPR-associated (Cas) proteins. In many organisms, this primary processing generates crRNA intermediates that are subject to additional nucleolytic trimming to render mature crRNAs of specific lengths. The molecular mechanisms underlying this maturation event remain poorly understood. Here, we defined the genetic requirements for crRNA primary processing and maturation in Staphylococcus epidermidis. We show that changes in the position of the primary processing site result in extended or diminished maturation to generate mature crRNAs of constant length. These results indicate that crRNA maturation occurs by a ruler mechanism anchored at the primary processing site. We also show that maturation is mediated by specific cas genes distinct from those genes involved in primary processing, showing that this event is directed by CRISPR/Cas loci.

Independent technical evaluation and recommendations for contaminated groundwater at the department of energy office of legacy management Riverton processing site

Energy Technology Data Exchange (ETDEWEB)

Looney, Brain B. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Denham, Miles E. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Eddy-Dilek, Carol A. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

2014-04-01

The U.S. Department of Energy Office of Legacy Management (DOE-LM) manages the legacy contamination at the Riverton, WY, Processing Site – a former uranium milling site that operated from 1958 to 1963. The tailings and associated materials were removed in 1988-1989 and contaminants are currently flushing from the groundwater. DOE-LM commissioned an independent technical team to assess the status of the contaminant flushing, identify any issues or opportunities for DOE-LM, and provide key recommendations. The team applied a range of technical frameworks – spatial, temporal, hydrological and geochemical – in performing the evaluation. In each topic area, an in depth evaluation was performed using DOE-LM site data (e.g., chemical measurements in groundwater, surface water and soil, water levels, and historical records) along with information collected during the December 2013 site visit (e.g., plant type survey, geomorphology, and minerals that were observed, collected and evaluated).

SITE: a methodology for assessment of energy facility siting patterns. Regional studies program

International Nuclear Information System (INIS)

Frigerio, N.A.; Habegger, L.J.; King, R.F.; Hoover, L.J.; Clark, N.A.; Cobian, J.M.

1975-08-01

The timely development of the nation's energy production capacity in a manner that minimizes potential adverse local and regional impacts associated with energy facilities requires the use of sophisticated techniques for evaluation of siting alternatives and fuel cycle options. This report is a documentation of the computerized SITE methodology that has been developed for evaluating health, environmental, and socioeconomic impacts related to utilization of alternate sites for energy production within a region of interest. The cost, impact, and attribute vectors, which are generated and displayed on density maps, can be used in a multiparameter overlay process to identify preferable siting areas. The assessment of clustered facilities in energy centers is also possible within the SITE analysis framework. An application of the SITE methodology to Northern Illinois is presented. Also included is a description of the ongoing extension of SITE for the accumulative evaluation of alternative regional energy siting patterns and fuel cycle options. An appendix provides documentation and user information for the SITE computer program

COMPARISON OF CONSEQUENCE ANALYSIS RESULTS FROM TWO METHODS OF PROCESSING SITE METEOROLOGICAL DATA

International Nuclear Information System (INIS)

, D

2007-01-01

Consequence analysis to support documented safety analysis requires the use of one or more years of representative meteorological data for atmospheric transport and dispersion calculations. At minimum, the needed meteorological data for most atmospheric transport and dispersion models consist of hourly samples of wind speed and atmospheric stability class. Atmospheric stability is inferred from measured and/or observed meteorological data. Several methods exist to convert measured and observed meteorological data into atmospheric stability class data. In this paper, one year of meteorological data from a western Department of Energy (DOE) site is processed to determine atmospheric stability class using two methods. The method that is prescribed by the U.S. Nuclear Regulatory Commission (NRC) for supporting licensing of nuclear power plants makes use of measurements of vertical temperature difference to determine atmospheric stability. Another method that is preferred by the U.S. Environmental Protection Agency (EPA) relies upon measurements of incoming solar radiation, vertical temperature gradient, and wind speed. Consequences are calculated and compared using the two sets of processed meteorological data from these two methods as input data into the MELCOR Accident Consequence Code System 2 (MACCS2) code

Implementation of a Self-Consistent Stereo Processing Chain for 3D Stereo Reconstruction of the Lunar Landing Sites

Science.gov (United States)

Tasdelen, E.; Willner, K.; Unbekannt, H.; Glaeser, P.; Oberst, J.

2014-04-01

The department for Planetary Geodesy at Technical University Berlin is developing routines for photogrammetric processing of planetary image data to derive 3D representations of planetary surfaces. The Integrated Software for Imagers and Spectrometers (ISIS) software (Anderson et al., 2004), developed by USGS, Flagstaff, is readily available, open source, and very well documented. Hence, ISIS was chosen as a prime processing platform and tool kit. However, ISIS does not provide a full photogrammetric stereo processing chain. Several components like image matching, bundle block adjustment (until recently) or digital terrain model (DTM) interpolation from 3D object points are missing. Our group aims to complete this photogrammetric stereo processing chain by implementing the missing components, taking advantage of already existing ISIS classes and functionality. We report here on the current status of the development of our stereo processing chain and its first application on the Lunar Apollo landing sites.

1994 Site Development Plan: A plan with vision

Energy Technology Data Exchange (ETDEWEB)

1994-07-01

The 1994 Lawrence Livermore National Laboratory Site Development Plan has been developed during a period of great change and uncertainty. Our goal is to make possible the best use of the Laboratory`s resources to meet shifting national priorities in the post-Cold War world. Site Planning is an important component of the overall Laboratory strategic planning process. This plan focuses on opportunities for the Laboratory as well as on key site development issues including facility construction, redevelopment and reuse, site accessibility, and security. A major challenge is to achieve sufficient stability in the site planning and execution so that the processes of construction can occur efficiently while at the same time providing sufficient flexibility in site facilities so that a range of changing national needs can be accommodated. We are closely coupled to the DOE strategic planning process to meet this challenge.

Deep borehole disposition of surplus fissile materials-The site selection process

International Nuclear Information System (INIS)

Heiken, G.; WoldeGabriel, G.; Morley, R.; Plannerer, H.

1996-01-01

One option for disposing of excess weapons plutonium is to place it near the base of deep boreholes in stable crystalline rocks. The technology exists to immediately begin the design of this means of disposition and there are many attractive sites available within the conterminous US. The borehole system utilizes mainly natural barriers to preven migration of Pu and U to the Earth's surface. Careful site selection ensures favorable geologic conditions that provide natural long-lived migration barriers; they include deep, extremely stable rock formations, strongly reducing brines that exhibit increasing salinity with depth, and most importantly, demonstrated isolation or non-communication of deep fluids with the biosphere for millions of years. This isolation is the most important characteristic, with the other conditions mainly being those that will enhance the potential of locating and maintaining the isolated zones. Candidate sites will probably be located on the craton in very old Precambrian crystalline rocks, most likely the center of a granitic pluton. The sites will be located in tectonically stable areas with no recent volcanic or seismic activity, and situated away from tectonic features that might become active in the near geologic future

MGP site remediation: Working toward presumptive remedies

International Nuclear Information System (INIS)

Larsen, B.R.

1996-01-01

Manufactured Gas Plants (MGPs) were prevalent in the United States during the 19th and first half of the 20th centuries. MGPs produced large quantities of waste by-products, which varied depending on the process used to manufacture the gas, but most commonly were tars and polynuclear aromatic hydrocarbons. There are an estimated 3,000 to 5,000 abandoned MGP sites across the United States. Because these sites are not concentrated in one geographic location and at least three different manufacturing processes were used, the waste characteristics are very heterogeneous. The question of site remediation becomes how to implement a cost-effective remediation with the variety of cleanup technologies available for these sites. Because of the significant expenditure required for characterization and cleanup of MGP sites, owners and regulatory agencies are beginning to look at standardizing cleanup technologies for these sites. This paper discusses applicable cleanup technologies and the attitude of state regulatory agencies towards the use of presumptive remedies, which can reduce the amount of characterization and detailed analysis necessary for any particular site. Additionally, this paper outlines the process of screening and evaluating candidate technologies, and the progress being made to match the technology to the site

Performance evaluation of the technical capabilities of DOE sites for disposal of mixed low-level waste: Volume 3, Site evaluations

Energy Technology Data Exchange (ETDEWEB)

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

1996-03-01

A team of analysts designed and conducted a performance evaluation to estimate the technical capabilities of fifteen Department of Energy sites for disposal of mixed low-level waste (i.e., waste that contains both low-level radioactive materials and hazardous constituents). Volume 1 summarizes the process for selecting the fifteen sites, the methodology used in the evaluation, and the conclusions derived from the evaluation. Volume 2 provides details about the site-selection process, the performance-evaluation methodology, and the overall results of the analysis. Volume 3 contains detailed evaluations of the fifteen sites and discussion of the results for each site.

Performance evaluation of the technical capabilities of DOE sites for disposal of mixed low-level waste: Volume 3, Site evaluations

International Nuclear Information System (INIS)

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

1996-03-01

A team of analysts designed and conducted a performance evaluation to estimate the technical capabilities of fifteen Department of Energy sites for disposal of mixed low-level waste (i.e., waste that contains both low-level radioactive materials and hazardous constituents). Volume 1 summarizes the process for selecting the fifteen sites, the methodology used in the evaluation, and the conclusions derived from the evaluation. Volume 2 provides details about the site-selection process, the performance-evaluation methodology, and the overall results of the analysis. Volume 3 contains detailed evaluations of the fifteen sites and discussion of the results for each site

Site characterization plan:

International Nuclear Information System (INIS)

1988-01-01

The Yucca Mountain site in Nevada is one of three candidate sites for the first geologic repository for radioactive waste. On May 28, 1986, it was recommended for detailed study in a program of site characterization. This site characterization plan (SCP) has been prepared in acordance with the requirements of the Nuclear Waste Policy Act to summarize the information collected to date about the geologic conditions at the site;to describe the conceptual designs for the repository and the waste package and to present the plans for obtaining the geologic information necessary to demonstrate the suitability of the site for a repository, to design the repository and the waste package, to prepare an environmental impact statement, and to obtain from the US Nuclear Regulatory Commission (NRC) an authorization to construct the repository. This introduction begins with a brief section on the process for siting and eveloping a repository, followed by a discussion of the pertinent legislation and regulations. A description of site characterization is presented next;it describes the facilities to be constructed for the site characterization program and explains the principal activities to be conducted during the program. Finally, the purpose, content, organizing prinicples, and organization of this site characterization plan are outlined, and compliance with applicable regulations is discussed. 880 refs., 130 figs., 25 tabs

Canada's deep geological repository for used nuclear fuel - update on the site evaluation process and interweaving of aboriginal traditional knowledge

International Nuclear Information System (INIS)

Watts, B.; Belfadhel, M.B.; Facella, J.

2015-01-01

The Nuclear Waste Management Organization (NWMO) is responsible for implementing Adaptive Phased Management (APM), the approach selected by the Government of Canada for the long-term management of used nuclear fuel generated by Canadian nuclear reactors. The ultimate objective of APM is the centralized containment and isolation of Canada's used nuclear fuel in a Deep Geological Repository (DGR) in a suitable crystalline or sedimentary rock formation. In May 2010, the NWMO initiated a nine-step site selection process to seek an informed and willing community to host Canada's deep geological repository. As of April 2015, twenty-two communities expressed interest in learning more about the project. This paper provides an update on the site evaluation process and describes the approach, methods and criteria used in the assessments, focusing on geological and community well-being studies. Engagement and field activities to interweave Aboriginal Traditional Knowledge with western science are also discussed. (author)

Application of quality assurance/quality control to waste management processes at the Hanford site

International Nuclear Information System (INIS)

Jones, D.H.; Vance, L.W.; Saget, R.P.; Sastry, A.M.

1990-01-01

The Hanford Site contains hazardous, radioactive and mixed wastes. The State of Washington and EPA both have regulatory and oversight responsibility for the ERRA program. A landmark agreement, the first of its kind in the USA, was signed in May 1989 between DOE, EPA and the State of Washington Department of Ecology which binds DOE to specific actions and milestones over a 30 year period. Public participation is provided throughout the process. This document is commonly known as the 'Tri-Party Agreement'. The paper discusses examples of unique waste management and ERRA activities subject to the quality assurance program and the considerations involved in designing an appropriate QA Program for Hanford's new mission. (orig./DG)

CoPc and CoPcF16 on gold: Site-specific charge-transfer processes

Directory of Open Access Journals (Sweden)

Fotini Petraki

2014-04-01

Full Text Available Interface properties of cobalt(II phthalocyanine (CoPc and cobalt(II hexadecafluoro-phthalocyanine (CoPcF16 to gold are investigated by photo-excited electron spectroscopies (X-ray photoemission spectroscopy (XPS, ultraviolet photoemission spectroscopy (UPS and X-ray excited Auger electron spectroscopy (XAES. It is shown that a bidirectional charge transfer determines the interface energetics for CoPc and CoPcF16 on Au. Combined XPS and XAES measurements allow for the separation of chemical shifts based on different local charges at the considered atom caused by polarization effects. This facilitates a detailed discussion of energetic shifts of core level spectra. The data allow the discussion of site-specific charge-transfer processes.

Pennsylvania's partnering process

International Nuclear Information System (INIS)

Latham, J.W.

1996-01-01

Pennsylvania is committed to finding a site for a low-level radioactive waste (LLRW) disposal facility through an innovative voluntary process. The Pennsylvania Department of Environmental Protection (DEP) and Chem-Nuclear Systems, Inc. (CNSI) developed the Community Partnering Plan with extensive public participation. The Community Partnering Plan outlines a voluntary process that empowers municipalities to evaluate the advantages and disadvantages of hosting the facility. DEP and CNSI began developing the Community Partnering Plan in July 1995. Before then, CNSI was using a screening process prescribed by state law and regulations to find a location for the facility. So far, approximately 78 percent of the Commonwealth has been identified as disqualified as a site for the LLRW disposal facility. The siting effort will now focus on identifying volunteer host municipalities in the remaining 22 percent of the state. This combination of technical screening and voluntary consideration makes Pennsylvania's process unique. A volunteered site will have to meet the same tough requirements for protecting people and the environment as a site chosen through the screening process. Protection of public health and safety continues to be the foundation of the state's siting efforts. The Community Partnering Plan offers a window of opportunity. If Pennsylvania does not find volunteer municipalities with suitable sites by the end of 1997, it probably will return to a technical screening process

Site systems engineering: Systems engineering management plan

Energy Technology Data Exchange (ETDEWEB)

Grygiel, M.L. [Westinghouse Hanford Co., Richland, WA (United States)

1996-05-03

The Site Systems Engineering Management Plan (SEMP) is the Westinghouse Hanford Company (WHC) implementation document for the Hanford Site Systems Engineering Policy, (RLPD 430.1) and Systems Engineering Criteria Document and Implementing Directive, (RLID 430.1). These documents define the US Department of Energy (DOE), Richland Operations Office (RL) processes and products to be used at Hanford to implement the systems engineering process at the site level. This SEMP describes the products being provided by the site systems engineering activity in fiscal year (FY) 1996 and the associated schedule. It also includes the procedural approach being taken by the site level systems engineering activity in the development of these products and the intended uses for the products in the integrated planning process in response to the DOE policy and implementing directives. The scope of the systems engineering process is to define a set of activities and products to be used at the site level during FY 1996 or until the successful Project Hanford Management Contractor (PHMC) is onsite as a result of contract award from Request For Proposal DE-RP06-96RL13200. Following installation of the new contractor, a long-term set of systems engineering procedures and products will be defined for management of the Hanford Project. The extent to which each project applies the systems engineering process and the specific tools used are determined by the project`s management.

Process for Transition of Uranium Mill Tailings Radiation Control Act Title II Disposal Sites to the U.S. Department of Energy Office of Legacy Management for Long-Term Surveillance and Maintenance

Energy Technology Data Exchange (ETDEWEB)

None

2012-03-01

This document presents guidance for implementing the process that the U.S. Department of Energy (DOE) Office of Legacy Management (LM) will use for assuming perpetual responsibility for a closed uranium mill tailings site. The transition process specifically addresses sites regulated under Title II of the Uranium Mill Tailings Radiation Control Act (UMTRCA) but is applicable in principle to the transition of sites under other regulatory structures, such as the Formerly Utilized Sites Remedial Action Program.

Remedial technology for contaminated natural gas dehydrator sites

International Nuclear Information System (INIS)

Prosen, B.J.; Korreck, W.M.; Armstrong, J.M.

1991-01-01

Ground water and soil contamination at many of Michigan's oil and gas well sites has been attributed to natural gas dehydration processes. Since water was once thought to be the only by-product from the dehydration process, condensate from the process was discharged directly to the ground for several years. This condensate was later found to contain benzene, toluene, ethyl-benzene, and xylenes (BTEX), and the process of discharging condensate to the ground was stopped. Many oil and gas well sites had become impacted from the process during this time. Although condensate is no longer discharged to the ground, soil and water contamination still remains at many of these sites. In the last few years, the Michigan Department of Natural Resources has targeted over 90 well sites for assessment of contamination associated with gas dehydration. The results of many of these assessments indicate that soil and ground water have been impacted, and the State of Michigan has mandated cleanup of these sites. Remedial technologies which have been used to contain and/or clean up the sites include excavation and product removal, soil venting, purge and treat, and enhanced biodegradation. This paper is a discussion of the technology, implementation, and results from each of these methods

Tanks focus area site needs assessment FY 1997

International Nuclear Information System (INIS)

1997-04-01

The Tanks Focus Area's (TFA's) mission is to manage an integrated technology development program that results in the application of technology to safely and efficiently accomplish tank waste remediation across the U.S. Department of Energy (DOE) complex. The TFA uses a systematic process for developing its annual program that draws from the tanks technology development needs expressed by four DOE tank waste sites - Hanford Site, Idaho National Engineering and Environmental Laboratory (INEEL), Oak Ridge Reservation (ORR), and Savannah River Site (SRS). The process is iterative and involves six steps: (1) Site needs identification and documentation, (2) Site communication of priority needs, (3) Technical response development, (4) Review technical responses, (5) Develop program planning documents, and (6) Review planning documents. This document describes the outcomes of the first two steps: site needs identification and documentation, and site communication of priority needs. It also describes the initial phases of the third and fourth steps: technical response development and review technical responses. Each site's Site Technology Coordination Group (STCG) was responsible for developing and delivering priority tank waste needs. This was accomplished using a standardized needs template developed by the National STCG. The standard template helped improve the needs submission process this year. The TFA received the site needs during December 1996 and January 1997

Status report: Fernald site remediation

International Nuclear Information System (INIS)

Craig, J.R. Jr.; Saric, J.A.; Schneider, T.; Yates, M.K.

1995-01-01

The Fernald site is rapidly transitioning from a Remedial Investigation/ Feasibility Study (RI/FS) site to one where design and construction of the remedies dominates. Fernald is one of the first sites in the Department of Energy (DOE) complex to accomplish this task and real physical progress is being made in moving the five operable units through the CERCLA process. Two of the required Records of Decision (ROD) are in hand and all five operable units will have received their RODs (IROD for OU3) by the end of 1995. Pre-design investigations, design work or construction are now in progress on the operable units. The lessons learned from the work done to date include implementing innovations in the RI and FS process as well as effective use of Removal Actions to begin the actual site remediation. Also, forging close working relationships with the Federal and State Regulators, citizens action groups and the Fernald Citizens Task Force has helped move the program forward. The Fernald successes have been achieved by close coordination and cooperation among all groups working on the projects and by application of innovative technologies within the decision making process

Site observational work plan for the UMTRA Project Site at Riverton, Wyoming. Revision 3/95

International Nuclear Information System (INIS)

1995-03-01

Ground water compliance for the Uranium Mill Tailings Remedial Action (UMTRA) Project sites, including the Riverton, Wyoming, site, is governed by the Uranium Mill Tailings Radiation Control Act and the US Environmental Protection Agency's Health and Environmental Protection Standards for Uranium and Thorium Mill Tailings. The compliance strategy proposed for this site is natural flushing in conjunction with institutional controls. The essential premise of natural flushing is that ground water movement and natural attenuation processes will reduce the detected contamination to background levels or alternate concentration limits that do not pose a risk to human health or the environment within 100 years. This document contains the following sections. Section 2.0 of this SOWP describes the requirements for meeting standards at UMTRA Project sites. Section 3.0 provides site-specific data and the related conceptual model. Section 4.0 provides the justification for the recommended ground water compliance strategy for the Riverton site. Section 5.0 provides the justification and process for collection and assessment of additional required data. Section 6.0 provides a list of the references cited. The appendixes include data on monitor wells and lithography, ground water, surface water, and sediment quality

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

International Nuclear Information System (INIS)

Nevalainen, Janne

2013-01-01

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

Ion Exchange Properties of Georgian Natural Zeolites

Directory of Open Access Journals (Sweden)

Vladimer Tsitsishvili

2017-06-01

Full Text Available Ion-exchange properties of natural zeolites of Georgia with a relatively low Si/Al ratio have been studied: analcimes are characterized by selectivity series: Na+>K+>Ag+>NH4+>Ca+2>Sr+2>Li+; for phillipsites selectivity sequences are different for calcium- and potassium forms; selectivity sequence for scolecite is: Sr+2>Ba+2>Rb+>Ca+2>Cs+>K+>NH4+>Na+>Mg+2>Li+>Cd+2>Cu+2> Mn+2> Zn+2>Co+2>Ni+2.

Report of early site suitability evaluation of the potential repository site at Yucca Mountain, Nevada; Yucca Mountain Site Characterization Project

Energy Technology Data Exchange (ETDEWEB)

Younker, J.L.; Andrews, W.B.; Fasano, G.A.; Herrington, C.C.; Mattson, S.R.; Murray, R.C. [Science Applications International Corp., Las Vegas, NV (United States); Ballou, L.B.; Revelli, M.A. [Lawrence Livermore National Lab., CA (United States); Ducharme, A.R.; Shephard, L.E. [Sandia National Labs., Albuquerque, NM (United States); Dudley, W.W.; Hoxie, D.T. [Geological Survey, Denver, CO (United States); Herbst, R.J.; Patera, E.A. [Los Alamos National Lab., NM (United States); Judd, B.R. [Decision Analysis Co., Portola Valley, CA (United States); Docka, J.A.; Rickertsen, L.D. [Weston Technical Associates, Washington, DC (United States)

1992-01-01

This study evaluated the technical suitability of Yucca Mountain, Nevada, as a potential site for a mined geologic repository for the permanent disposal of radioactive waste. The evaluation was conducted primarily to determine early in the site characterization program if there are any features or conditions at the site that indicate it is unsuitable for repository development. A secondary purpose was to determine the status of knowledge in the major technical areas that affect the suitability of the site. This early site suitability evaluation (ESSE) was conducted by a team of technical personnel at the request of the Associate Director of the US Department of Energy (DOE) Office of Geologic Disposal, a unit within the DOE`s Office of Civilian Radioactive Waste Management. The Yucca Mountain site has been the subject of such evaluations for over a decade. In 1983, the site was evaluated as part of a screening process to identify potentially acceptable sites. The site was evaluated in greater detail and found suitable for site characterization as part of the Environmental Assessment (EA) (DOE, 1986) required by the Nuclear Waste Policy Act of 1982 (NWPA). Additional site data were compiled during the preparation of the Site Characterization Plan (SCP) (DOE, 1988a). This early site suitability evaluation has considered information that was used in preparing both-documents, along with recent information obtained since the EA and SCP were published. This body of information is referred to in this report as ``current information`` or ``available evidence.``

Separation processes for the pretreatment of high-level nuclear wastes at the Savannah River site - 59291

International Nuclear Information System (INIS)

Hobbs, David; Peters, Thomas; Taylor-Pashow, Kathryn; Fondeur, Fernando; Nash, Charles; Fink, Samuel; Herman, David; Marra, Jim

2012-01-01

Document available in abstract form only. Full text of publication follows: Separation methods for the pretreatment of the high-level nuclear wastes (HLW) at the Savannah River Site (SRS) include the Caustic Side Solvent Extraction (CSSX) process for cesium and adsorption/ion exchange for the removal of cesium, strontium and alpha-emitting actinides. The CSSX process uses a calixarene extractant in combination with phase modifiers in a hydrocarbon diluent. Monosodium titanate (MST), a hydrous metal oxide, is the baseline material for the removal of strontium and alpha-emitting radionuclides (principally Pu-238, Pu-239, Pu-240 and Np-237). Two pretreatment facilities, the Modular Caustic Side Solvent Extraction Unit (MCU) and the Actinide Removal Process (ARP) facility began radioactive operations at SRS in 2008. Together these facilities can treat approximately 4 million liters of waste per year. The same separation processes are also planned for the much larger Salt Waste Processing Facility (SWPF). The SWPF, which has a design throughput of about 27 million liters per year, is under construction and scheduled to begin radioactive operations in 2014. Current R and D activities for the CSSX process are focused on implementing a new solvent system and stripping flowsheet that offers enhanced extraction and stripping of cesium. This next generation solvent system features a different calixarene extractant, uses caustic instead of nitric acid

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)

Remediation of acid mine drainage at the friendship hill national historic site with a pulsed limestone bed process

Science.gov (United States)

Sibrell, P.L.; Watten, B.; Boone, T.; ,

2003-01-01

A new process utilizing pulsed fluidized limestone beds was tested for the remediation of acid mine drainage at the Friendship Hill National Historic Site, in southwestern Pennsylvania. A 230 liter-per-minute treatment system was constructed and operated over a fourteen-month period from June 2000 through September 2001. Over this period of time, 50,000 metric tons of limestone were used to treat 50 million liters of water. The influent water pH was 2.5 and acidity was 1000 mg/L as CaCO3. Despite the high potential for armoring at the site, effluent pH during normal plant operation ranged from 5.7 to 7.8 and averaged 6.8. As a result of the high influent acidity, sufficient CO2 was generated and recycled to provide a net alkaline discharge with about 50 mg/L as CaCO3 alkalinity. Additions of commercial CO2 increased effluent alkalinity to as high as 300 mg/L, and could be a useful process management tool for transient high flows or acidities. Metal removal rates were 95% for aluminum (60 mg/L in influent), 50 to 90% for iron (Fe), depending on the ratio of ferrous to ferric iron, which varied seasonally (200 mg/L in influent), and treatment passive settling/oxidation pond. Metal hydroxide sludges were settled in settling tanks, and then hauled from the site for aesthetic purposes. Over 450 metric tons of sludge were removed from the water over the life of the project. The dried sludge was tested by the Toxicity Characteristics Leaching Protocol (TCLP) and was found to be non-hazardous. Treatment costs were $43,000 per year and $1.08 per m 3, but could be decreased to $22,000 and $0.51 per m3 by decreasing labor use and by onsite sludge handling. These results confirm the utility of the new process in treatment of acid impaired waters that were previously not amenable to low cost limestone treatment.

Site selection: Past and present

International Nuclear Information System (INIS)

Tilford, N.R.

1994-01-01

Site selection has been going on since the earliest times. The process has evolved through the Industrial Revolution to the present period of exploding population and environmental awareness. Now the work must be done both with increasing sophistication and greater transparency. Modern techniques for site selection have been developed during the last two decades or so, utilizing a teachable body of knowledge and a growing literature. Many firms and individuals have contributed to this growing field. The driving force has been the need for such a process in siting and licensing of critical facilities such as nuclear power plants. A list of crucial, documented steps for identifying social impacts and acceptability are provided. A recent innovation is the self-selection method developed by government. The Superconducting Supercollider serves as an example of this approach. Geological or geologically dependent factors often dominate the process. The role as engineering and environmental geoscientists is to provide responsible leadership, consultation, and communication to the effort

Site selection - siting of the final repository for spent nuclear fuel

International Nuclear Information System (INIS)

2011-03-01

SKB has selected Forsmark as the site for the final repository for spent nuclear fuel. The site selection is the end result of an extensive siting process that began in the early 1990s. The strategy and plan for the work was based on experience from investigations and development work over a period of more than ten years prior to then. This document describes the siting work and SKB's choice of site for the final repository. It also presents the information on which the choice was based and the reasons for the decisions made along the way. The document comprises Appendix PV to applications under the Nuclear Activities Act and the Environmental Code for licences to build and operate an encapsulation plant adjacent to the central interim storage facility for spent nuclear fuel in Oskarshamn, and to build and operate a final repository for spent nuclear fuel in Forsmark in Oesthammar Municipality

Site selection - siting of the final repository for spent nuclear fuel

Energy Technology Data Exchange (ETDEWEB)

2011-03-15

SKB has selected Forsmark as the site for the final repository for spent nuclear fuel. The site selection is the end result of an extensive siting process that began in the early 1990s. The strategy and plan for the work was based on experience from investigations and development work over a period of more than ten years prior to then. This document describes the siting work and SKB's choice of site for the final repository. It also presents the information on which the choice was based and the reasons for the decisions made along the way. The document comprises Appendix PV to applications under the Nuclear Activities Act and the Environmental Code for licences to build and operate an encapsulation plant adjacent to the central interim storage facility for spent nuclear fuel in Oskarshamn, and to build and operate a final repository for spent nuclear fuel in Forsmark in Oesthammar Municipality

Remedial Action Plan and Site Design for stabilization of the inactive Uranium Mill Tailings sites at Slick Rock, Colorado: Appendix C to Attachment 3, Calculations. Final

International Nuclear Information System (INIS)

1995-09-01

This volume contains calculations for: Slick Rock processing sites background ground water quality; Slick Rock processing sites lysimeter water quality; Slick Rock processing sites on-site and downgradient ground water quality; Slick Rock disposal site background water quality; Burro Canyon disposal site, Slick Rock, Colorado, average hydraulic gradients and average liner ground water velocities in the upper, middle, and lower sandstone units of the Burro Canyon formation; Slick Rock--Burro Canyon disposal site, Burro Canyon pumping and slug tests--analyses; water balance and surface contours--Burro Canyon disposal cell; and analytical calculation of drawdown in a hypothetical well completed in the upper sandstone unit of the Burro Canyon formation

Tracking nitrous oxide emission processes at a suburban site with semicontinuous, in situ measurements of isotopic composition

Science.gov (United States)

Harris, Eliza; Henne, Stephan; Hüglin, Christoph; Zellweger, Christoph; Tuzson, Béla; Ibraim, Erkan; Emmenegger, Lukas; Mohn, Joachim

2017-02-01

The isotopic composition of atmospheric nitrous oxide (N2O) was measured semicontinuously, at ˜35 min frequency in intermittent periods of 1-6 days over one and a half years, using preconcentration coupled to a quantum cascade laser spectrometer at the suburban site of Dübendorf, Switzerland. The achieved measurement repeatability was 0.08‰, 0.11‰, and 0.10‰ for δ18O, site preference, and δ15Nbulk respectively, which is better than or equal to standard flask sampling-based isotope ratio mass spectrometry performance. The observed mean diurnal cycle reflected the buildup of N2O from isotopically light sources on an isotopically heavy tropospheric background. The measurements were used to determine the source isotopic composition, which varied significantly compared to chemical and meteorological parameters monitored at the site. FLEXPART-COSMO transport modeling in combination with modified Emissions Database for Global Atmospheric Research inventory emissions was used to model N2O mole fractions at the site. Additionally, isotopic signatures were estimated for different source categories using literature data and used to simulate N2O isotopic composition over the measurement period. The model was able to capture variability in N2O mole fraction well, but simulations of isotopic composition showed little agreement with observations. In particular, measured source isotopic composition exhibited one magnitude larger variability than simulated, clearly indicating that the range of isotopic source signatures estimated from literature significantly underestimates true variability of source signatures. Source δ18O signature was found to be the most sensitive tracer for urban/industry versus agricultural N2O. δ15Nbulk and site preference may provide more insight into microbial and chemical emission processes than partitioning of anthropogenic source categories.

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

Track 2 sites: Guidance for assessing low probability hazard sites at the INEL

International Nuclear Information System (INIS)

1994-01-01

This document presents guidance for assessment of Track 2 low probability hazard sites (LPHS) at the Idaho National Engineering Laboratory (INEL). The Track 2 classification was developed specifically for the INEL to streamline the implementation of Comprehensive Environmental Response, Compensation, and Liability Act. Track 2 LPHSs are described as sites where insufficient data are available to make a decision concerning the risk level or to select or design a remedy. As such, these types of sites are not described in the National Contingency Plan or existing regulatory guidance. The goal of the Track 2 process is to evaluate LPHSs using existing qualitative and quantitative data to minimize the collection of new environmental data. To this end, this document presents a structured format consisting of a series of questions and tables. A qualitative risk assessment is used. The process is iterative, and addresses an LPHS from multiple perspectives (i.e., historical, empirical, process) in an effort to generate a reproducible and defensible method. This rigorous approach follows the data quality objective process and establishes a well organized, logical approach to consolidate and assess existing data, and set decision criteria. If necessary, the process allows for the design of a sampling and analysis strategy to obtain new environmental data of appropriate quality to support decisions for each LPHS. Finally, the guidance expedites consensus between regulatory parties by emphasizing a team approach to Track 2 investigations

Searching your site`s management information systems

Energy Technology Data Exchange (ETDEWEB)

Marquez, W.; Rollin, C. [S.M. Stoller Corp., Boulder, CO (United States)

1994-12-31

The Department of Energy`s guidelines for the Baseline Environmental Management Report (BEMR) encourage the use of existing data when compiling information. Specific systems mentioned include the Progress Tracking System, the Mixed-Waste Inventory Report, the Waste Management Information System, DOE 4700.1-related systems, Programmatic Environmental Impact Statement (PEIS) data, and existing Work Breakdown Structures. In addition to these DOE-Headquarters tracking and reporting systems, there are a number of site systems that will be relied upon to produce the BEMR, including: (1) site management control and cost tracking systems; (2) commitment/issues tracking systems; (3) program-specific internal tracking systems; (4) Site material/equipment inventory systems. New requirements have often prompted the creation of new, customized tracking systems. This is a very time and money consuming process. As the BEMR Management Plan emphasizes, an effort should be made to use the information in existing tracking systems. Because of the wealth of information currently available from in-place systems, development of a new tracking system should be a last resort.

Total site integration of light hydrocarbons separation process

OpenAIRE

Ulyev, L.; Vasilyev, M.; Maatouk, A.; Duic, Neven; Khusanovc, Alisher

2016-01-01

Ukraine is the largest consumer of hydrocarbons per unit of production in Europe (Ukraine policy review, 2006). The most important point is a reduction of energy consumption in chemical and metallurgical industries as a biggest consumer. This paper deals with energy savings potential of light hydrocarbons separation process. Energy consumption of light hydrocarbons separation process processes typical of Eastern European countries were analysed. Process Integration (PI) was used to perform a ...

Remediation management of complex sites using an adaptive site management approach.

Science.gov (United States)

Price, John; Spreng, Carl; Hawley, Elisabeth L; Deeb, Rula

2017-12-15

Complex sites require a disproportionate amount of resources for environmental remediation and long timeframes to achieve remediation objectives, due to their complex geologic conditions, hydrogeologic conditions, geochemical conditions, contaminant-related conditions, large scale of contamination, and/or non-technical challenges. A recent team of state and federal environmental regulators, federal agency representatives, industry experts, community stakeholders, and academia worked together as an Interstate Technology & Regulatory Council (ITRC) team to compile resources and create new guidance on the remediation management of complex sites. This article summarizes the ITRC team's recommended process for addressing complex sites through an adaptive site management approach. The team provided guidance for site managers and other stakeholders to evaluate site complexities and determine site remediation potential, i.e., whether an adaptive site management approach is warranted. Adaptive site management was described as a comprehensive, flexible approach to iteratively evaluate and adjust the remedial strategy in response to remedy performance. Key aspects of adaptive site management were described, including tools for revising and updating the conceptual site model (CSM), the importance of setting interim objectives to define short-term milestones on the journey to achieving site objectives, establishing a performance model and metrics to evaluate progress towards meeting interim objectives, and comparing actual with predicted progress during scheduled periodic evaluations, and establishing decision criteria for when and how to adapt/modify/revise the remedial strategy in response to remedy performance. Key findings will be published in an ITRC Technical and Regulatory guidance document in 2017 and free training webinars will be conducted. More information is available at www.itrc-web.org. Copyright © 2017 Elsevier Ltd. All rights reserved.

SiteChar. Characterisation of European CO2 storage. Deliverable D8.1. Qualitative and quantitative social site characterisations

Energy Technology Data Exchange (ETDEWEB)

Brunsting, S.; Pol, M.; Paukovic, M. [ECN Policy Studies, Energy research Centre of the Netherlands ECN, Amsterdam (Netherlands); Kaiser, M.; Zimmer, R. [Unabhaengiges Institut fuer Umweltfragen UfU, Berlin (Germany); Shackley, S.; Mabon, L. [Scottish Carbon Capture and Storage SCCS, Edinburg, Scotland (United Kingdom); Hepplewhite, F.; Loveridge, R. [Energy Markets Unit, Scottish Government, Edinburg, Scotland (United Kingdom); Mazurowski, M.; Polak-Osiniak, D. [Polish Oil and Gas Company PGNiG, Warszawa (Poland); Rybicki, C. [AGH University of Science and Technology, Krakow (Poland)

2012-10-15

At local level, public support has proven crucial to the implementation of CO2 capture and storage (CCS) demonstration projects. Whereas no method exists to guarantee public acceptability of any project, a constructive stakeholder engagement process does increase the likelihood thereof. Social site characterisation can be used as an instrument to explore, plan and evaluate a process of active and constructive local stakeholder engagement in a prospective CCS project as a parallel activity to technical site characterisation. It roughly consists of a formative research phase to get acquainted with the area followed by a series of public information and engagement activities. This deliverable presents results from the first phase for the social site characterisations of a prospective CCS site in Poland (onshore) and the UK (offshore), using qualitative as well as quantitative research methods, as a first step to planning of local public engagement activities and evaluation of these activities that will be undertaken by this consortium at both sites in the near future. Although the term social site characterisation actually refers to the entire process of formative research and subsequent public outreach, and hence to the complete package of awareness work undertaken as part of SiteChar, in the present deliverable the term only refers to the formative research activities as undertaken up to now and as described in this deliverable. The qualitative part of the social site characterisation consisted of (1) a description of relevant social site characteristics such as local history; (2) interviews with relevant local stakeholders; (3) a media analysis of local newspapers. The quantitative part of the social site characterisation consisted of surveys using representative samples to characterise the local population in terms of awareness, knowledge and perceptions of CCS, felt involvement in decision making, extent of local activism, level of trust in representatives and

Advanced technologies for maintenance of electrical systems and equipment at the Savannah River Site Defense Waste Processing Facility

International Nuclear Information System (INIS)

Husler, R.O.; Weir, T.J.

1991-01-01

An enhanced maintenance program is being established to characterize and monitor cables, components, and process response at the Savannah River Site, Defense Waste Processing Facility. This facility was designed and constructed to immobilize the radioactive waste currently stored in underground storage tanks and is expected to begin operation in 1993. The plant is initiating the program to baseline and monitor instrument and control (I ampersand C) and electrical equipment, remote process equipment, embedded instrument and control cables, and in-cell jumper cables used in the facility. This program is based on the electronic characterization and diagnostic (ECAD) system which was modified to include process response analysis and to meet rigid Department of Energy equipment requirements. The system consists of computer-automated, state-of-the-art electronics. The data that are gathered are stored in a computerized database for analysis, trending, and troubleshooting. It is anticipated that the data which are gathered and trended will aid in life extension for the facility

Ecological studies related to construction of the Defense Waste Processing Facility on the Savannah River Site. FY 1989--1990 annual report

Energy Technology Data Exchange (ETDEWEB)

Pechmann, J.H.K.; Scott, D.E.; McGregor, J.H.; Estes, R.A.; Chazal, A.C.

1993-02-01

The Defense Waste Processing Facility (DWPF) was built on the Savannah River Site (SRS) during the mid-1980`s. The Savannah River Ecology Laboratory (SREL) has completed 12 years of ecological studies related to the construction of the DWPF complex. Prior to construction, the 600-acre site (S-Area) contained a Carolina bay and the headwaters of a stream. Research conducted by the SREL has focused primarily on four questions related to these wetlands: (1) Prior to construction, what fauna and flora were present at the DWPF site and at similar, yet undisturbed, alternative sites? (2) By comparing the Carolina bay at the DWPF site (Sun Bay) with an undisturbed control Carolina bay (Rainbow Bay), what effect is construction having on the organisms that inhabited the DWPF site? (3) By comparing control streams with streams on the periphery of the DWPF site, what effect is construction having on the peripheral streams? (4) How effective have efforts been to lessen the impacts of construction, both with respect to erosion control measures and the construction of ``refuge ponds`` as alternative breeding sites for amphibians that formerly bred at Sun Bay? Through the long-term census-taking of biota at the DWPF site and Rainbow Bay, SREL has begun to evaluate the impact of construction on the biota and the effectiveness of mitigation efforts. Similarly, the effects of erosion from the DWPF site on the water quality of S-Area peripheral streams are being assessed. This research provides supporting data relevant to the National Environmental Policy Act (NEPA) of 1969, the Endangered Species Act of 1973, Executive Orders 11988 (Floodplain Management) and 11990 (Protection of Wetlands), and United States Department of Energy (DOE) Guidelines for Compliance with Floodplain/Wetland Environmental Review Requirements (10CFR1022).

Surface and subsurface cleanup protocol for radionuclides, Gunnison, Colorado, UMTRA project processing site

International Nuclear Information System (INIS)

Gonzales, D.

1993-12-01

Surface and subsurface soil cleanup protocols for the Gunnison, Colorado, processing site are summarized as follows: In accordance with EPA-promulgated land cleanup standards, in situ Ra-226 is to be cleaned up based on bulk concentrations not exceeding 5 and 15 pCi/g in 15-cm surface and subsurface depth increments, averaged over 100m 2 grid blocks, where the parent Ra-226 concentrations are greater than, or in secular equilibrium with, the Th-230 parent. In locations where Th-230 has differentially migrated in subsoil relative to Ra-226, a Th-230 clean up protocol has been developed. The cleanup of other radionuclides or nonradiological hazards that pose a significant threat to the public and the environment will be determined and implemented in accordance with pathway analysis to assess impacts and the implications of ALARA specified in 40 CFR Part 192 relative to supplemental standards

Life Cycle Inventory (LCI) Data-Treatment Chemicals, Construction Materials, Transportation, On-site Equipment, and other Processes for Use in Spreadsheets for Environmental Footprint Analysis (SEFA): Revised Addition

Science.gov (United States)

This report estimates environmental emission factors (EmF) for key chemicals, construction and treatment materials, transportation/on-site equipment, and other processes used at remediation sites. The basis for chemical, construction, and treatment material EmFs is life cycle inv...

Uptake of heavy metals by Typha capensis from wetland sites polluted by effluent from mineral processing plants: implications of metal-metal interactions.

Science.gov (United States)

Zaranyika, M F; Nyati, W

2017-10-01

The aim of the present work was to demonstrate the existence of metal-metal interactions in plants and their implications for the absorption of toxic elements like Cr. Typha capensis , a good accumulator of heavy metals, was chosen for the study. Levels of Fe, Cr, Ni, Cd, Pb, Cu and Zn were determined in the soil and roots, rhizomes, stems and leaves of T. capensis from three Sites A, B and C polluted by effluent from a chrome ore processing plant, a gold ore processing plant, and a nickel ore processing plant, respectively. The levels of Cr were extremely high at Site A at 5415 and 786-16,047 μg g -1 dry weight in the soil and the plant, respectively, while the levels of Ni were high at Site C at 176 and 24-891 μg g -1 in the soil and the plant, respectively. The levels of Fe were high at all three sites at 2502-7500 and 906-13,833 μg g -1 in the soil and plant, respectively. For the rest of the metals, levels were modest at 8.5-148 and 2-264 μg g -1 in the soil and plant, respectively. Pearson's correlation analysis confirmed mutual synergistic metal-metal interactions in the uptake of Zn, Cu, Co, Ni, Fe, and Cr, which are attributed to the similarity in the radii and coordination geometry of the cations of these elements. The implications of such metal-metal interactions (or effects of one metal on the behaviour of another) on the uptake of Cr, a toxic element, and possible Cr detoxification mechanism within the plant, are discussed.

Wind turbine siting: A summary of the state of the art

Science.gov (United States)

Hiester, T. R.

1982-01-01

The process of siting large wind turbines may be divided into two broad steps: site selection, and site evaluation. Site selection is the process of locating windy sites where wind energy development shows promise of economic viability. Site evaluation is the process of determining in detail for a given site the economic potential of the site. The state of the art in the first aspect of siting, site selection is emphasized. Several techniques for assessing the wind resource were explored or developed in the Federal Wind Energy Program. Local topography and meteorology will determine which of the techniques should be used in locating potential sites. None of the techniques can do the job alone, none are foolproof, and all require considerable knowledge and experience to apply correctly. Therefore, efficient siting requires a strategy which is founded on broad based application of several techniques without relying solely on one narrow field of expertise.

Practice of Connectivism As Learning Theory: Enhancing Learning Process Through Social Networking Site (Facebook

Directory of Open Access Journals (Sweden)

Fahriye Altınay Aksal

2013-12-01

Full Text Available The impact of the digital age within learning and social interaction has been growing rapidly. The realm of digital age and computer mediated communication requires reconsidering instruction based on collaborative interactive learning process and socio-contextual experience for learning. Social networking sites such as facebook can help create group space for digital dialogue to inform, question and challenge within a frame of connectivism as learning theory within the digital age. The aim of this study is to elaborate the practice of connectivism as learning theory in terms of internship course. Facebook group space provided social learning platform for dialogue and negotiation beside the classroom learning and teaching process in this study. The 35 internship students provided self-reports within a frame of this qualitative research. This showed how principles of theory practiced and how this theory and facebook group space contribute learning, selfleadership, decision making and reflection skills. As the research reflects a practice of new theory based on action research, learning is not individualistic attempt in the digital age as regards the debate on learning in digital age within a frame of connectivism

Effective stochastic generator with site-dependent interactions

Science.gov (United States)

Khamehchi, Masoumeh; Jafarpour, Farhad H.

2017-11-01

It is known that the stochastic generators of effective processes associated with the unconditioned dynamics of rare events might consist of non-local interactions; however, it can be shown that there are special cases for which these generators can include local interactions. In this paper, we investigate this possibility by considering systems of classical particles moving on a one-dimensional lattice with open boundaries. The particles might have hard-core interactions similar to the particles in an exclusion process, or there can be many arbitrary particles at a single site in a zero-range process. Assuming that the interactions in the original process are local and site-independent, we will show that under certain constraints on the microscopic reaction rules, the stochastic generator of an unconditioned process can be local but site-dependent. As two examples, the asymmetric zero-temperature Glauber model and the A-model with diffusion are presented and studied under the above-mentioned constraints.

Management of Decommissioning on a Multi-Facility Site

International Nuclear Information System (INIS)

Laraia, Michele; McIntyre, Peter; Visagie, Abrie

2008-01-01

The management of the decommissioning of multi-facility sites may be inadequate or inappropriate if based on approaches and strategies developed for sites consisting of only a single facility. The varied nature of activities undertaken, their interfaces and their interdependencies are likely to complicate the management of decommissioning. These issues can be exacerbated where some facilities are entering the decommissioning phase while others are still operational or even new facilities are being built. Multi-facility sites are not uncommon worldwide but perhaps insufficient attention has been paid to optimizing the overall site decommissioning in the context of the entire life cycle of facilities. Decommissioning management arrangements need to be established taking a view across the whole site. A site-wide decommissioning management system is required. This should include a project evaluation and approval process and specific arrangements to manage identified interfaces and interdependencies. A group should be created to manage decommissioning across the site, ensuring adequate and consistent practices in accordance with the management system. Decommissioning management should be aimed at the entire life cycle of facilities. In the case of multi facility sites, the process becomes more complex and decommissioning management arrangements need to be established with a view to the whole site. A site decommissioning management system, a group that is responsible for decommissioning on site, a site project evaluation and approval process and specific arrangements to manage the identified interfaces are key areas of a site decommissioning management structure that need to be addressed to ensure adequate and consistent decommissioning practices. A decommissioning strategy based on single facilities in a sequential manner is deemed inadequate

Application of accident progression event tree technology to the Savannah River Site Defense Waste Processing Facility SAR analysis

International Nuclear Information System (INIS)

Brandyberry, M.D.; Baker, W.H.; Wittman, R.S.; Amos, C.N.

1993-01-01

The Accident Analysis in the Safety Analysis Report (SAR) for the Savannah River Site (SRS) Defense Waste Processing Facility (DWPF) has recently undergone an upgrade. Non-reactor SARs at SRS (and other Department of Energy (DOE) sites) use probabilistic techniques to assess the frequency of accidents at their facilities. This paper describes the application of an extension of the Accident Progression Event Tree (APET) approach to accidents at the SRS DWPF. The APET technique allows an integrated model of the facility risk to be developed, where previous probabilistic accident analyses have been limited to the quantification of the frequency and consequences of individual accident scenarios treated independently. Use of an APET allows a more structured approach, incorporating both the treatment of initiators that are common to more than one accident, and of accident progression at the facility

Hanford Site sustainable development initiatives

International Nuclear Information System (INIS)

Sullivan, C.T.

1994-05-01

Since the days of the Manhattan Project of World War II, the economic well being of the Tri-Cities (Pasco, Kennewick, and Richland) of Washington State has been tied to the US Department of Energy missions at the nearby Hanford Site. As missions at the Site changed, so did the economic vitality of the region. The Hanford Site is now poised to complete its final mission, that of environmental restoration. When restoration is completed, the Site may be closed and the effect on the local economy will be devastating if action is not taken now. To that end, economic diversification and transition are being planned. To facilitate the process, the Hanford Site will become a sustainable development demonstration project

Cost reductions on a site producing soap and detergents

Energy Technology Data Exchange (ETDEWEB)

Clayton, R.W. (UKAEA Harwell Lab. (UK). Energy Technology Div.)

1986-05-01

The company, which is a subsidiary of the multinational Procter and Gamble Company, manufactures soap and detergent products at two UK sites. A process integration study of the West Thurrock site was undertaken with the help of the Energy and Process Integration Service (EPI). This organisation offers a specialist process integration consultancy service. The study cost around Pound 45,000, including consultancy fees and Procter and Gamble staff time. It was completed in 12 months. The study established that the consumption of process energy could be reduced by around 25% if the site was fully integrated. (author).

Possible sites for future nuclear power plants in Israel

Energy Technology Data Exchange (ETDEWEB)

Yaar, Ilan, E-mail: ilany@energy.gov.il [Ministry of National Infrastructure, Energy and Water Resources, Chief Scientist Office, 14 Hartum St., POB 36148, Jerusalem 9136002 (Israel); Walter, Ayelet [Ministry of National Infrastructure, Energy and Water Resources, Chief Scientist Office, 14 Hartum St., POB 36148, Jerusalem 9136002 (Israel); Sanders, Yovav [Sysnet Group, Habarzel St. 32, Tel Aviv 69710 (Israel); Felus, Yaron [Survey of Israel, 1 Lincoln St., POB 14171, Tel-Aviv 61141 (Israel); Calvo, Ran; Hamiel, Yariv [Geological Survey of Israel, 30 Malkhe Israel St., Jerusalem 95501 (Israel)

2016-03-15

A preliminary work aimed at allocating suitable new sites for possible NPPs in Israel is presented. The work is based on Israel's present NPP siting criteria, supported by selected procedure performed by various countries that conducted similar process. The site selection process was conducted in two stages: first, a selection procedure using demographic analysis was conducted; second, a seismological and geological analysis process was performed in the remaining area. From the combined two screening processes results, an overall new area of 569 km{sup 2} was located as a possible area for future construction of NPPs in Israel. Further and more comprehensive work, based on the IAEAs site selection guidelines, has to be performed in the future, in order to verify the preliminary findings presented in this work.

DOE site performance assessment activities

International Nuclear Information System (INIS)

1990-07-01

Information on performance assessment capabilities and activities was collected from eight DOE sites. All eight sites either currently dispose of low-level radioactive waste (LLW) or plan to dispose of LLW in the near future. A survey questionnaire was developed and sent to key individuals involved in DOE Order 5820.2A performance assessment activities at each site. The sites surveyed included: Hanford Site (Hanford), Idaho National Engineering Laboratory (INEL), Los Alamos National Laboratory (LANL), Nevada Test Site (NTS), Oak Ridge National Laboratory (ORNL), Paducah Gaseous Diffusion Plant (Paducah), Portsmouth Gaseous Diffusion Plant (Portsmouth), and Savannah River Site (SRS). The questionnaire addressed all aspects of the performance assessment process; from waste source term to dose conversion factors. This report presents the information developed from the site questionnaire and provides a comparison of site-specific performance assessment approaches, data needs, and ongoing and planned activities. All sites are engaged in completing the radioactive waste disposal facility performance assessment required by DOE Order 5820.2A. Each site has achieved various degrees of progress and have identified a set of critical needs. Within several areas, however, the sites identified common needs and questions

Analysis of cobbly soils for cobbles-to-fines corrections to radionuclide concentrations at the New Rifle, Colorado, processing site

International Nuclear Information System (INIS)

1994-05-01

A contamination depth and cobbly soil characterization study was performed in November and December 1993 at the Uranium Mill Tailings Remedial Action (UMTRA) Projects's New Rifle, Colorado, processing site. This study was initiated due to a concurrence by the US Nuclear Regulatory Commission (NRC) clarifying that the allowable residual contamination in soil should be averaged over the total mass of the soil volume, including cobbles and gravels (i.e., bulk concentration). The New Rifle processing site has a high percentage of cobbles and gravels underlying the pile and other contaminated areas, which preliminary excavation designs have identified for removal and disposal. The main purpose of this study was to evaluate the relative mass percentage and radionuclide concentrations of cobbles and gravels in order to determine the bulk contamination concentrations, revise the underlying excavation design depths, and improve verification methods. Another important goal of the study was to acquire more accurate contamination depth data (profile) for the subpile material. In summary, this recharacterization study will probably reduce the volume of material for excavation/disposal by several hundred thousand cubic yards and significantly reduce the amount of ground water expected to be pumped out of the excavation during cleanup

Monitoring the performance of off-site processors

International Nuclear Information System (INIS)

Miller, C.C.

1995-01-01

Commercial nuclear power plants have been able to utilize the latest technologies and achieve large volume reduction by obtaining off-site waste processor services. Although the use of such services reduce the burden of waste processing it also reduces the utility's control over the process. Monitoring the performance of off-site processors is important so that the utility is cognizant of the waste disposition for required regulatory reporting. In addition to obtaining data for Reg Guide 1.21 reporting, Performance monitoring is important to determine which vendor and which services to utilize. Off-site processor services were initially offered for the decontamination of metallic waste. Since that time the list of services has expanded to include supercompaction, survey for release, incineration and metal melting. The number of vendors offering off-site services has increased and the services they offer vary. processing rates vary between vendors and have different charge bases. Determining which vendor to use for what service can be complicated and confusing

Experience Gained from the Former Uranium Ore Processing and the Remediation of the Legacy Site in Hungary

Energy Technology Data Exchange (ETDEWEB)

Csövári, M.; Földing, G.; Berta, Zs.; Németh, G., E-mail: csovarimihaly@mecsekoko.hu [MECSEK-ÖKO Zrt, Pécs (Hungary)

2014-05-15

Uranium explorations in Hungary started 1953. By 1957 the uranium ore reserves were confirmed and the feasibility of mining in the Mecsek Mountains demonstrated by opening the first shaft. In 1962 the mill was built. The mining and processing of the uranium ore were terminated in 1997 mainly on economical reasons. The remediation of the site has started immediately and had been practically finished in 2008. The paper summarises the remediation work, and some lessons learned from the former mill practice, and from the remediation activity. (author)

Achievement of process control, safety, and regulatory compliance in a mixed waste evaporator system at the Hanford Site using data quality objectives

International Nuclear Information System (INIS)

Von Bargen, B.H.

1995-01-01

The Data Quality Objectives (DQO) Process was applied to the operation of the 242-A Evaporator at the Hanford Site. A team consisting of representatives from process engineering, environmental engineering, regulatory compliance, analytical laboratories, and DOE utilized the step by step DQO process to define the issues, variables, and inputs necessary to develop the decision rules which govern plant operations. The sampling and analyses required to make these decisions was then optimized concerning factors such as sample number, total analyses, cost, radiation exposure, quality assurance, and deliverables

Lessons learned in the implementation of Integrated Safety Management at DOE Order Compliance Sites vs Necessary and Sufficient Sites

International Nuclear Information System (INIS)

Hill, R.L.

2000-01-01

This paper summarizes the development and implementation of Integrated Safety Management (ISM) at an Order Compliance Site (Savannah River Site) and a Necessary and Sufficient Site (Nevada Test Site). A discussion of each core safety function of ISM is followed by an example from an Order Compliance Site and a Necessary and Sufficient Site. The Savannah River Site was the first DOE site to have a DOE Headquarters-validated and approved ISM System. The NTS is beginning the process of verification and validation. This paper defines successful strategies for integrating Environment, Safety, and Health management into work under various scenarios

Geological Site Descriptive Model. A strategy for the model development during site investigations

Energy Technology Data Exchange (ETDEWEB)

Munier, Raymond; Stenberg, Leif [Swedish Nuclear Fuel and Waste Management Co., Stockholm (Sweden); Stanfors, Roy [Roy Stanfors Consulting, Lund (Sweden); Milnes, Allan Geoffrey [GEA Consulting, Uppsala (Sweden); Hermanson, Jan [Golder Associates, Stockholm (Sweden); Triumf, Carl-Axel [Geovista, Luleaa (Sweden)

2003-04-01

The Swedish Nuclear Fuel and Waste Management Company (SKB) is at present conducting site investigations as a preliminary to building an underground nuclear waste disposal facility in Sweden. This report presents a methodology for constructing, visualising and presenting 3-dimensional geological models, based on data from the site investigations. The methodology integrates with the overall work-flow of the site investigations, from the collection of raw data to the complete site description, as proposed in several earlier technical reports. Further, it is specifically designed for interaction with SICADA - SKB's Site Characterisation Database - and RVS - SKB's Rock Visualisation System. This report is one in a series of strategy documents intended to demonstrate how modelling is to be performed within each discipline. However, it also has a wider purpose, since the geological site descriptive model provides the basic geometrical framework for all the other disciplines. Hence, the wider aim is to present a practical and clear methodology for the analysis and interpretation of input data for use in the construction of the geology-based 3D geometrical model. In addition to the various aspects of modelling described above, the methodology presented here should therefore also provide: guidelines and directives on how systematic interpretation and integration of geo-scientific data from the different investigation methods should be carried out; guidelines on how different geometries should be created in the geological models; guidelines on how the assignment of parameters to the different geological units in RVS should be accomplished; guidelines on the handling of uncertainty at different points in the interpretation process. In addition, it should clarify the relation between the geological model and other models used in the processes of site characterisation, repository layout and safety analysis. In particular, integration and transparency should be

Geological Site Descriptive Model. A strategy for the model development during site investigations

International Nuclear Information System (INIS)

Munier, Raymond; Stenberg, Leif; Stanfors, Roy; Milnes, Allan Geoffrey; Hermanson, Jan; Triumf, Carl-Axel

2003-04-01

The Swedish Nuclear Fuel and Waste Management Company (SKB) is at present conducting site investigations as a preliminary to building an underground nuclear waste disposal facility in Sweden. This report presents a methodology for constructing, visualising and presenting 3-dimensional geological models, based on data from the site investigations. The methodology integrates with the overall work-flow of the site investigations, from the collection of raw data to the complete site description, as proposed in several earlier technical reports. Further, it is specifically designed for interaction with SICADA - SKB's Site Characterisation Database - and RVS - SKB's Rock Visualisation System. This report is one in a series of strategy documents intended to demonstrate how modelling is to be performed within each discipline. However, it also has a wider purpose, since the geological site descriptive model provides the basic geometrical framework for all the other disciplines. Hence, the wider aim is to present a practical and clear methodology for the analysis and interpretation of input data for use in the construction of the geology-based 3D geometrical model. In addition to the various aspects of modelling described above, the methodology presented here should therefore also provide: guidelines and directives on how systematic interpretation and integration of geo-scientific data from the different investigation methods should be carried out; guidelines on how different geometries should be created in the geological models; guidelines on how the assignment of parameters to the different geological units in RVS should be accomplished; guidelines on the handling of uncertainty at different points in the interpretation process. In addition, it should clarify the relation between the geological model and other models used in the processes of site characterisation, repository layout and safety analysis. In particular, integration and transparency should be promoted. The