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Sample records for storage site sp

  1. Assessment of 222Rn occupational exposure at IPEN nuclear materials storage site, SP, Brazil

    International Nuclear Information System (INIS)

    Caccuri, Lilian Saueia

    2007-01-01

    In this study it was assessed the occupational exposure to 222 Rn at IPEN, SP, Brazil, nuclear materials storage site through the committed effective dose received by workers exposed to this radionuclide. The radiation dose was calculated through the radon concentrations at nuclear materials storage site. Radon concentrations were determined by passive detection method with solid state nuclear detectors (SSNTD). The SSNTD used in this study was the polycarbonate Makrofol E; each detector is a small square plastic of 1 cm 2 , placed into a diffusion chamber type KFK. It was monitored 14 points at nuclear materials storage site and one external point, over a period of 21 months, changing the detectors every three months, from December 2004 to September 2006. The 222 Rn concentrations varied from 196 ± 9 and 2048 ± 81 Bq·m -3 . The committed effective dose due to radon inhalation at IPEN nuclear materials storage site was obtained from radon activity incorporated and dose conversion factor, according to International Commission on Radiological Protection procedures. The effective committed dose received by workers is below 20 mSv·y -1 . This value is suggested as an annual effective dose limit for occupational exposure by ICRP 60. (author)

  2. Assessment of {sup 222}Rn occupational exposure at IPEN nuclear materials storage site, SP, Brazil; Avaliacao da exposicao ocupacional ao {sup 222}Rn no galpao da Salvaguardas do IPEN, SP

    Energy Technology Data Exchange (ETDEWEB)

    Caccuri, Lilian Saueia

    2007-07-01

    In this study it was assessed the occupational exposure to {sup 222}Rn at IPEN, SP, Brazil, nuclear materials storage site through the committed effective dose received by workers exposed to this radionuclide. The radiation dose was calculated through the radon concentrations at nuclear materials storage site. Radon concentrations were determined by passive detection method with solid state nuclear detectors (SSNTD). The SSNTD used in this study was the polycarbonate Makrofol E; each detector is a small square plastic of 1 cm{sup 2}, placed into a diffusion chamber type KFK. It was monitored 14 points at nuclear materials storage site and one external point, over a period of 21 months, changing the detectors every three months, from December 2004 to September 2006. The {sup 222}Rn concentrations varied from 196 {+-} 9 and 2048 {+-} 81 Bq{center_dot}m{sup -3}. The committed effective dose due to radon inhalation at IPEN nuclear materials storage site was obtained from radon activity incorporated and dose conversion factor, according to International Commission on Radiological Protection procedures. The effective committed dose received by workers is below 20 mSv{center_dot}y{sup -1}. This value is suggested as an annual effective dose limit for occupational exposure by ICRP 60. (author)

  3. 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

  4. Differential regulation of the human progesterone receptor gene through an estrogen response element half site and Sp1 sites.

    Science.gov (United States)

    Petz, Larry N; Ziegler, Yvonne S; Schultz, Jennifer R; Kim, Hwajin; Kemper, J Kim; Nardulli, Ann M

    2004-02-01

    The progesterone receptor (PR) gene is regulated by estrogen in normal reproductive tissues and in MCF-7 human breast cancer cells. Although it is generally thought that estrogen responsiveness is mediated by interaction of the ligand-occupied estrogen receptor (ER) with estrogen response elements (EREs) in target genes, the human progesterone receptor (PR) gene lacks a palindromic ERE. Promoter A of the PR gene does, however, contain an ERE half site upstream of two adjacent Sp1 sites from +571 to +595, the +571 ERE/Sp1 site. We have examined the individual contributions of the ERE half site and the two Sp1 sites in regulating estrogen responsiveness. Transient transfection assays demonstrated that both Sp1 sites were critical for estrogen-mediated activation of the PR gene. Interestingly, rather than decreasing transcription, mutations in the ERE half site increased transcription substantially suggesting that this site plays a role in limiting transcription. Chromatin immunoprecipitation assays demonstrated that Sp1 was associated with the +571 ERE/Sp1 site in the endogenous PR gene in the absence and in the presence of estrogen, but that ERalpha was only associated with this region of the PR gene after MCF-7 cells had been treated with estrogen. Our studies provide evidence that effective regulation of transcription through the +571 ERE/Sp1 site requires the binding of ERalpha and Sp1 to their respective cis elements and the appropriate interaction of ERalpha and Sp1 with other coregulatory proteins and transcription factors.

  5. Radioactive waste on-site storage alternative

    International Nuclear Information System (INIS)

    Dufrane, K.H.

    1983-01-01

    The first, most frequently evaluated approach for the large producer is the construction of a relatively expensive storage building. However, with the likely possibility that at least one disposal site will remain available and the building never used, such expenditures are difficult to justify. A low cost, but effective alternative, is the use of ''On-Site Storage Containers'' (OSSC) when and if required. Radwaste is only stored in the OSSC if a disposal site is not available. A small number of OSSC's would be purchased initially just to assure immediate access to storage. Only in the unlikely event of total disposal sites closure would additional OSSC's have to be obtained and even this is cost effective. With two or three months of storage available on site, production lead time is sufficient for the delivery of additional units at a rate faster than the waste can be produced. The recommended OSSC design would be sized and shielding optimized to meet the needs of the waste generator. Normally, this would duplicate the shipping containers (casks or vans) currently in use. The reinforced concrete design presented is suitable for outside storage, contains a leakproof polyethylene liner and has remote sampling capability. Licensing would be under 10CFR50.59 for interim storage with long-term storage under 10CFR30 not an impossibility. Cost comparisons of this approach vs. building construction show that for a typical reactor plant installation, the OSSC offers direct savings even under the worst case assumption that no disposal sites are available and the time value of money is zero

  6. SP-A binding sites on bovine alveolar macrophages.

    Science.gov (United States)

    Plaga, S; Plattner, H; Schlepper-Schaefer, J

    1998-11-25

    Surfactant protein A (SP-A) binding to bovine alveolar macrophages was examined in order to characterize SP-A binding proteins on the cell surface and to isolate putative receptors from these cells that could be obtained in large amounts. Human SP-A, unlabeled or labeled with gold particles, was bound to freshly isolated macrophages and analyzed with ELISA or the transmission electron microscope. Binding of SP-A was inhibited by Ca2+ chelation, by an excess of unlabeled SP-A, or by the presence of 20 mg/ml mannan. We conclude that bovine alveolar macrophages expose binding sites for SP-A that are specific and that depend on Ca2+ and on mannose residues. For isolation of SP-A receptors with homologous SP-A as ligand we isolated SP-A from bovine lung lavage. SDS-PAGE analysis of the purified SP-A showed a protein of 32-36 kDa. Functional integrity of the protein was demonstrated. Bovine SP-A bound to Dynabeads was used to isolate SP-A binding proteins. From the fractionated and blotted proteins of the receptor preparation two proteins bound SP-A in a Ca2+-dependent manner, a 40-kDa protein showing mannose dependency and a 210-kDa protein, showing no mannose sensitivity. Copyright 1998 Academic Press.

  7. CO2 Storage Feasibility: A Workflow for Site Characterisation

    Directory of Open Access Journals (Sweden)

    Nepveu Manuel

    2015-04-01

    Full Text Available In this paper, we present an overview of the SiteChar workflow model for site characterisation and assessment for CO2 storage. Site characterisation and assessment is required when permits are requested from the legal authorities in the process of starting a CO2 storage process at a given site. The goal is to assess whether a proposed CO2 storage site can indeed be used for permanent storage while meeting the safety requirements demanded by the European Commission (EC Storage Directive (9, Storage Directive 2009/31/EC. Many issues have to be scrutinised, and the workflow presented here is put forward to help efficiently organise this complex task. Three issues are highlighted: communication within the working team and with the authorities; interdependencies in the workflow and feedback loops; and the risk-based character of the workflow. A general overview (helicopter view of the workflow is given; the issues involved in communication and the risk assessment process are described in more detail. The workflow as described has been tested within the SiteChar project on five potential storage sites throughout Europe. This resulted in a list of key aspects of site characterisation which can help prepare and focus new site characterisation studies.

  8. Definitive design status of the SP-100 Ground Engineering System Test Site

    International Nuclear Information System (INIS)

    Renkey, E.J. Jr.; Bazinet, G.D.; Bitten, E.J.; Brackenbury, P.J.; Carlson, W.F.; Irwin, J.J.; Edwards, P.A.; Shen, E.J.; Titzler, P.A.

    1989-05-01

    The SP-100 reactor will be ground tested at the SP-100 Ground Engineering System (GES) Test Site on the US Department of Energy (DOE) Hanford Site near Richland, Washington. Project direction and the flight system design evolution have resulted in a smaller reactor size and the consequential revision to Test Site features to accommodate the design changes and reduce Test Site costs. The significant design events since the completion of the Conceptual Design are discussed in this paper

  9. Definitive design status of the SP-100 Ground Engineering System Test Site

    Energy Technology Data Exchange (ETDEWEB)

    Renkey, E.J. Jr.; Bazinet, G.D.; Bitten, E.J.; Brackenbury, P.J.; Carlson, W.F.; Irwin, J.J.; Edwards, P.A.; Shen, E.J.; Titzler, P.A.

    1989-05-01

    The SP-100 reactor will be ground tested at the SP-100 Ground Engineering System (GES) Test Site on the US Department of Energy (DOE) Hanford Site near Richland, Washington. Project direction and the flight system design evolution have resulted in a smaller reactor size and the consequential revision to Test Site features to accommodate the design changes and reduce Test Site costs. The significant design events since the completion of the Conceptual Design are discussed in this paper.

  10. Storage of intermediate level waste at UKAEA sites

    International Nuclear Information System (INIS)

    Goodill, D.R.; Tymons, B.J.

    1985-08-01

    This report describes the storage of wastes at UKAEA sites and accordingly contributes to the investigations conducted by the Department of the Environment into the Best Practicable Environmental Option (BPEO) for radioactive waste storage and/or disposal. This report on the storage of ILW should be read in conjunction with a similar NII funded CTS study for Licensed Sites in the UK. (author)

  11. Leaking Underground Storage Tank Sites in Iowa

    Data.gov (United States)

    Iowa State University GIS Support and Research Facility — Leaking Underground Storage Tank (LUST) sites where petroleum contamination has been found. There may be more than one LUST site per UST site.

  12. International Symposium on Site Characterization for CO2Geological Storage

    Energy Technology Data Exchange (ETDEWEB)

    Tsang, Chin-Fu

    2006-02-23

    Several technological options have been proposed to stabilize atmospheric concentrations of CO{sub 2}. One proposed remedy is to separate and capture CO{sub 2} from fossil-fuel power plants and other stationary industrial sources and to inject the CO{sub 2} into deep subsurface formations for long-term storage and sequestration. Characterization of geologic formations for sequestration of large quantities of CO{sub 2} needs to be carefully considered to ensure that sites are suitable for long-term storage and that there will be no adverse impacts to human health or the environment. The Intergovernmental Panel on Climate Change (IPCC) Special Report on Carbon Dioxide Capture and Storage (Final Draft, October 2005) states that ''Site characterization, selection and performance prediction are crucial for successful geological storage. Before selecting a site, the geological setting must be characterized to determine if the overlying cap rock will provide an effective seal, if there is a sufficiently voluminous and permeable storage formation, and whether any abandoned or active wells will compromise the integrity of the seal. Moreover, the availability of good site characterization data is critical for the reliability of models''. This International Symposium on Site Characterization for CO{sub 2} Geological Storage (CO2SC) addresses the particular issue of site characterization and site selection related to the geologic storage of carbon dioxide. Presentations and discussions cover the various aspects associated with characterization and selection of potential CO{sub 2} storage sites, with emphasis on advances in process understanding, development of measurement methods, identification of key site features and parameters, site characterization strategies, and case studies.

  13. Risk management guidelines for petroleum storage tank sites

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-10-01

    These guidelines provide a site management process designed particularly for soil and groundwater pollution originating from existing or former petroleum storage tank (PST) facilities and provide uniform standards for the remediation of polluted PST sites in Alberta. The numerical criteria, risk management objectives and technical information described in this document were compiled from four documents including Remediation Guidelines for Petroleum Storage Tank Sites 1994, the Canada-Wide Standards for Petroleum Hydrocarbons in Soil, Alberta Soil and Water Quality Guidelines for Hydrocarbons at Upstream Oil and Gas Facilities, and Guidelines for Managing Risks at Contaminated Sites in Alberta. The changes in these updated guidelines reflect new remediation criteria and provide a process for determining alternate site-specific management objectives for more petroleum storage tank sites. The guidelines were developed using a risk-based approach that ensures the protection of human health, safety and the environment. The guidelines apply to aboveground and underground storage tank facilities that contain gasoline, diesel, heating oil, and aviation fuel. The guidelines specify requirements by Alberta Environment and the Alberta Fire Code. The chapter on risk management process included information on site investigation, determination of soil type, pollution source removal, land use assessment, selection of exposure pathways, depth of remediation, human inhalation and groundwater protection pathways, and verification of remediation. figs, 4 tabs., 2 appendices.

  14. SP Transcription Factor Paralogs and DNA-Binding Sites Coevolve and Adaptively Converge in Mammals and Birds

    Science.gov (United States)

    Yokoyama, Ken Daigoro; Pollock, David D.

    2012-01-01

    Functional modification of regulatory proteins can affect hundreds of genes throughout the genome, and is therefore thought to be almost universally deleterious. This belief, however, has recently been challenged. A potential example comes from transcription factor SP1, for which statistical evidence indicates that motif preferences were altered in eutherian mammals. Here, we set out to discover possible structural and theoretical explanations, evaluate the role of selection in SP1 evolution, and discover effects on coregulatory proteins. We show that SP1 motif preferences were convergently altered in birds as well as mammals, inducing coevolutionary changes in over 800 regulatory regions. Structural and phylogenic evidence implicates a single causative amino acid replacement at the same SP1 position along both lineages. Furthermore, paralogs SP3 and SP4, which coregulate SP1 target genes through competitive binding to the same sites, have accumulated convergent replacements at the homologous position multiple times during eutherian and bird evolution, presumably to preserve competitive binding. To determine plausibility, we developed and implemented a simple model of transcription factor and binding site coevolution. This model predicts that, in contrast to prevailing beliefs, even small selective benefits per locus can drive concurrent fixation of transcription factor and binding site mutants under a broad range of conditions. Novel binding sites tend to arise de novo, rather than by mutation from ancestral sites, a prediction substantiated by SP1-binding site alignments. Thus, multiple lines of evidence indicate that selection has driven convergent evolution of transcription factors along with their binding sites and coregulatory proteins. PMID:23019068

  15. 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

  16. Environmental assessment of SP-100 ground engineering system test site: Hanford Site, Richland, Washington

    Energy Technology Data Exchange (ETDEWEB)

    1988-12-01

    The US Department of Energy (DOE) proposes to modify an existing reactor containment building (decommissioned Plutonium Recycle Test Reactor (PRTR) 309 Building) to provide ground test capability for the prototype SP-100 reactor. The 309 Building (Figure 1.1) is located in the 300 Area on the Hanford Site in Washington State. The National Environmental Policy Act (NEPA) requires that Federal agencies assess the potential impacts that their actions may have on the environment. This Environmental Assessment describes the consideration given to environmental impacts during reactor concept and test site selection, examines the environmental effects of the DOE proposal to ground test the nuclear subsystem, describes alternatives to the proposed action, and examines radiological risks of potential SP-100 use in space. 73 refs., 19 figs., 7 tabs.

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

    International Nuclear Information System (INIS)

    Chandra, U.; Marcelino, S.

    1986-01-01

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

  18. Construction management at the SP-100 ground engineering system test site

    International Nuclear Information System (INIS)

    Burchell, G.P.; Wilson, L.R.

    1991-01-01

    Contractors under the U.S. Department of Energy management have implemented a comprehensive approach to the management of design and construction of the complex facility modifications at the SP-100 Ground Engineering System Test Site on the Hanford Reservation. The SP-100 Test Site employs a multi-organizational integrated management approach with clearly defined responsibilities to assure success. This approach allows for thorough planning and analysis before the project kick off, thus minimizing the number and magnitude of problems which arise during the course of the project. When combined with a comprehensive cost and schedule/project management reporting system the problems which do occur are recognized early enough to assure timely intervention and resolution

  19. Techno-Economic Assessment of Four CO2 Storage Sites

    Directory of Open Access Journals (Sweden)

    Gruson J.-F.

    2015-04-01

    Full Text Available Carbon Capture and Storage (CCS should be a key technology in order to achieve a decline in the CO2 emissions intensity of the power sector and other intensive industry, but this potential deployment could be restricted by cost issues as the International Energy Agency (IEA in their last projections (World Energy Outlook 2013 has considered only around 1% of global fossil fuel-fired power plants could be equipped with CCS by 2035. The SiteChar project funded by 7th Framework Programme of European Commission gives the opportunity to evaluate the most influential parameters of techno-economic evaluations of four feasible European projects for CO2 geological storage located onshore and offshore and related to aquifer storage or oil and gas reservoirs, at different stages of characterization. Four potential CO2 storage sites have been assessed in terms of storage costs per tonne of CO2 permanently stored (equivalent cost based. They are located offshore UK, onshore Denmark, offshore Norway and offshore Italy. The four SiteChar techno-economic evaluations confirm it is not possible to derive any meaningful average cost for a CO2 storage site. The results demonstrate that the structure of costs for a project is heterogeneous and the storage cost is consequently site dependent. The strategy of the site development is fundamental, the technical choices such as the timing, rate and duration of injection are also important. The way monitoring is managed, using observation wells and logging has a strong impact on the estimated monitoring costs. Options to lower monitoring costs, such as permanent surveys, exist and should be further investigated. Table 1 below summarizes the cost range in Euro per tonne (Discount Rate (DR at 8% for the different sites, which illustrates the various orders of magnitude due to the specificities of each site. These figures have how to be considered with care. In particular the Italian and Norwegian sites present very specific

  20. CPA ups storage at Lavera site

    International Nuclear Information System (INIS)

    Back, R.

    1992-01-01

    Compagnie Parisienne des Asphaltes (CPA; Paris) and its subsidiary Pacsud -owned 65% by CPA and 35% by Shell Chimie (Paris) - have inaugurated their new chemicals storage site at Lavera, France, in the Europort South complex near Marseilles. The facilities, with 60,000-m.t./year capacity, also include a barreling plant that will have output of up to 250 bbl/hour when it comes onstream next spring. Total investment for these facilities amount to F122 million ($22.5 million), including F22 million for the barreling unit. CPA, France's number two storage specialist, after LB Chimie (Paris), is jointly owned by investment company Union Normandie (60%), Elf Aquitaine (Paris; 20%), and Total (Paris; 20%). Adding to its existing French storage sites at Dunkirk and Rouen, CPA says it decided to build on the Pacsud venture because it considered it attractive to invest in the petroleum and petrochemical complex of Fos-Berre-Lavera, particularly since the present trend in the oil and chemical industries is to subcontract all ancillary functions, especially logistics. CPA general manager Rafic Charles Rathle says that customer requirements and the role of the service provider are changing. With that in mid, CPA, in addition to providing storage terminals, converts its depots into distribution and packing centers. At Lavera the company has taken over storage, blending, and barreling operations for Pacsud and its direct customers. For example, Pacsud has a long-term contract with Shell Chimie for the latter's additive production at a 10,000-m.t./year rate. Another long-term contract is being negotiated, but the identity of the customer was not revealed

  1. Building arrangement and site layout design guides for on site low level radioactive waste storage facilities

    International Nuclear Information System (INIS)

    McMullen, J.W.; Feehan, M.J.

    1986-01-01

    Many papers have been written by AE's and utilities describing their onsite storage facilities, why they are needed, NRC regulations, and disposal site requirements. This paper discusses a typical storage facility and address the design considerations and operational aspects that are generally overlooked when designing and siting a low level radioactive waste storage facility. Some topics to be addressed are: 1. Container flexibility; 2. Modular expansion capabilities; 3. DOT regulations; 4. Meterological requirements; 5. OSHA; 6. Fire protection; 7. Floods; 8. ALARA

  2. Risk assessment-led characterisation of the SiteChar UK north sea site for the geological storage of CO2

    International Nuclear Information System (INIS)

    Akhurst, Maxine; Hannis, Sarah D.; Quinn, Martyn F.; Long, David; Shi, Ji-Quan; Koenen, Marielle; Pluymaekers, Maarten; Delprat-Jannaud, Florence; Lecomte, Jean-Claude; Bossie-Codreanu, Daniel; Nagy, Stanislaw; Klimkowski, Lukas; Gei, Davide

    2015-01-01

    Risk assessment-led characterisation of a site for the geological storage of CO 2 in the UK northern North Sea was performed for the EU SiteChar research project as one of a portfolio of sites. Implementation and testing of the SiteChar project site characterisation work-flow has produced a 'dry-run' storage permit application that is compliant with regulatory requirements. A site suitable for commercial-scale storage was characterised, compatible with current and future industrial carbon dioxide (CO 2 ) sources in the northern UK. Pre-characterisation of the site, based on existing information acquired during hydrocarbon exploration and production, has been achieved from publicly available data. The project concept is to store captured CO 2 at a rate of 5 Mt per year for 20 years in the Blake Oil Field and surrounding Captain Sandstone saline aquifer. This commercial-scale storage of 100 Mt CO 2 can be achieved through a storage scenario combining injection of CO 2 into the oil field and concurrent water production down-dip of the field. There would be no encroachment of supercritical phase CO 2 for more than two kilometres beyond the field boundary and no adverse influence on operating hydrocarbon fields provided there is pressure management. Components of a storage permit application for the site are presented, developed as far as possible within a research project. Characterisation and technical investigations were guided by an initial assessment of perceived risks to the prospective site and a need to provide the information required for the storage permit application. The emphasis throughout was to reduce risks and uncertainty on the subsurface containment of stored CO 2 , particularly with respect to site technical performance, monitoring and regulatory issues, and effects on other resources. The results of selected risk assessment-led site characterisation investigations and the subsequent risk reassessments are described together with their

  3. Site dose calculations for the INEEL/TMI-2 storage facility

    International Nuclear Information System (INIS)

    Jones, K.B.

    1997-01-01

    The U.S. Department of Energy (DOE) is licensing an independent spent-fuel storage installation (ISFSI) for the Three Mile Island unit 2 (TMI-2) core debris to be constructed at the Idaho Chemical Processing Plant (ICPP) site at the Idaho National Engineering and Environmental Laboratory (INEEL) using the NUHOMS spent-fuel storage system. This paper describes the site dose calculations, performed in support of the license application, that estimate exposures both on the site and for members of the public. These calculations are unusual for dry-storage facilities in that they must account for effluents from the system in addition to skyshine from the ISFSI. The purpose of the analysis was to demonstrate compliance with the 10 CFR 20 and 10 CFR 72.104 exposure limits

  4. Using RFID to Enhance Security in Off-Site Data Storage

    Directory of Open Access Journals (Sweden)

    Enrique de la Hoz

    2010-08-01

    Full Text Available Off-site data storage is one of the most widely used strategies in enterprises of all sizes to improve business continuity. In medium-to-large size enterprises, the off-site data storage processes are usually outsourced to specialized providers. However, outsourcing the storage of critical business information assets raises serious security considerations, some of which are usually either disregarded or incorrectly addressed by service providers. This article reviews these security considerations and presents a radio frequency identification (RFID-based, off-site, data storage management system specifically designed to address security issues. The system relies on a set of security mechanisms or controls that are arranged in security layers or tiers to balance security requirements with usability and costs. The system has been successfully implemented, deployed and put into production. In addition, an experimental comparison with classical bar-code-based systems is provided, demonstrating the system’s benefits in terms of efficiency and failure prevention.

  5. Using RFID to Enhance Security in Off-Site Data Storage

    Science.gov (United States)

    Lopez-Carmona, Miguel A.; Marsa-Maestre, Ivan; de la Hoz, Enrique; Velasco, Juan R.

    2010-01-01

    Off-site data storage is one of the most widely used strategies in enterprises of all sizes to improve business continuity. In medium-to-large size enterprises, the off-site data storage processes are usually outsourced to specialized providers. However, outsourcing the storage of critical business information assets raises serious security considerations, some of which are usually either disregarded or incorrectly addressed by service providers. This article reviews these security considerations and presents a radio frequency identification (RFID)-based, off-site, data storage management system specifically designed to address security issues. The system relies on a set of security mechanisms or controls that are arranged in security layers or tiers to balance security requirements with usability and costs. The system has been successfully implemented, deployed and put into production. In addition, an experimental comparison with classical bar-code-based systems is provided, demonstrating the system’s benefits in terms of efficiency and failure prevention. PMID:22163638

  6. Using RFID to enhance security in off-site data storage.

    Science.gov (United States)

    Lopez-Carmona, Miguel A; Marsa-Maestre, Ivan; de la Hoz, Enrique; Velasco, Juan R

    2010-01-01

    Off-site data storage is one of the most widely used strategies in enterprises of all sizes to improve business continuity. In medium-to-large size enterprises, the off-site data storage processes are usually outsourced to specialized providers. However, outsourcing the storage of critical business information assets raises serious security considerations, some of which are usually either disregarded or incorrectly addressed by service providers. This article reviews these security considerations and presents a radio frequency identification (RFID)-based, off-site, data storage management system specifically designed to address security issues. The system relies on a set of security mechanisms or controls that are arranged in security layers or tiers to balance security requirements with usability and costs. The system has been successfully implemented, deployed and put into production. In addition, an experimental comparison with classical bar-code-based systems is provided, demonstrating the system's benefits in terms of efficiency and failure prevention.

  7. Functions for fission yeast splicing factors SpSlu7 and SpPrp18 in alternative splice-site choice and stress-specific regulated splicing.

    Directory of Open Access Journals (Sweden)

    Geetha Melangath

    Full Text Available Budding yeast spliceosomal factors ScSlu7 and ScPrp18 interact and mediate intron 3'ss choice during second step pre-mRNA splicing. The fission yeast genome with abundant multi-intronic transcripts, degenerate splice signals and SR proteins is an apt unicellular fungal model to deduce roles for core spliceosomal factors in alternative splice-site choice, intron retention and to study the cellular implications of regulated splicing. From our custom microarray data we deduce a stringent reproducible subset of S. pombe alternative events. We examined the role of factors SpSlu7 or SpPrp18 for these splice events and investigated the relationship to growth phase and stress. Wild-type log and stationary phase cells showed ats1+ exon 3 skipped and intron 3 retained transcripts. Interestingly the non-consensus 5'ss in ats1+ intron 3 caused SpSlu7 and SpPrp18 dependent intron retention. We validated the use of an alternative 5'ss in dtd1+ intron 1 and of an upstream alternative 3'ss in DUF3074 intron 1. The dtd1+ intron 1 non-canonical 5'ss yielded an alternative mRNA whose levels increased in stationary phase. Utilization of dtd1+ intron 1 sub-optimal 5' ss required functional SpPrp18 and SpSlu7 while compromise in SpSlu7 function alone hampered the selection of the DUF3074 intron 1 non canonical 3'ss. We analysed the relative abundance of these splice isoforms during mild thermal, oxidative and heavy metal stress and found stress-specific splice patterns for ats1+ and DUF3074 intron 1 some of which were SpSlu7 and SpPrp18 dependent. By studying ats1+ splice isoforms during compromised transcription elongation rates in wild-type, spslu7-2 and spprp18-5 mutant cells we found dynamic and intron context-specific effects in splice-site choice. Our work thus shows the combinatorial effects of splice site strength, core splicing factor functions and transcription elongation kinetics to dictate alternative splice patterns which in turn serve as an additional

  8. Flexible OSSC or the on-site storage alternative and how it grew

    International Nuclear Information System (INIS)

    Dufrane, K.H.

    1986-01-01

    The On-Site Storage Container (OSSC) is an accepted and proven concept currently in widespread use for both operations and the storage of low level radioactive waste. In addition, it represents a very attractive enhancement to a geological low-level waste disposal site. Use of the proven OSSC concept at a site can provide additional safety to the environment by combining the benefits of an engineered storage facility with the proven safety of a sound geological repository. The concept of flexibility which was built into the OSSC concept for the temporary above ground storage of low-level waste is directly applicable to a permanent storage facility. Manufacturing costs, size flexibility, handling systems, and real-world operational advantages are well known and proven. This background provides a high confidence level for adapting this technology to a disposal site while keeping in mind the significance of both operational economics, safety to the environment, and ALARA principles. The development, design and cost effectiveness features of the OSSC as a temporary storage facility are discussed in detail. The flexible OSSC provides significant economic advantages over a permanent storage building. The application of the OSSC to a permanent geological disposal site provides the environmental advantages of an engineered facility while maintaining the inherent operational and economic benefits of the flexible OSSC concept

  9. U.S. Department of Energy's site screening, site selection, and initial characterization for storage of CO2 in deep geological formations

    Science.gov (United States)

    Rodosta, T.D.; Litynski, J.T.; Plasynski, S.I.; Hickman, S.; Frailey, S.; Myer, L.

    2011-01-01

    The U.S. Department of Energy (DOE) is the lead Federal agency for the development and deployment of carbon sequestration technologies. As part of its mission to facilitate technology transfer and develop guidelines from lessons learned, DOE is developing a series of best practice manuals (BPMs) for carbon capture and storage (CCS). The "Site Screening, Site Selection, and Initial Characterization for Storage of CO2 in Deep Geological Formations" BPM is a compilation of best practices and includes flowchart diagrams illustrating the general decision making process for Site Screening, Site Selection, and Initial Characterization. The BPM integrates the knowledge gained from various programmatic efforts, with particular emphasis on the Characterization Phase through pilot-scale CO2 injection testing of the Validation Phase of the Regional Carbon Sequestration Partnership (RCSP) Initiative. Key geologic and surface elements that suitable candidate storage sites should possess are identified, along with example Site Screening, Site Selection, and Initial Characterization protocols for large-scale geologic storage projects located across diverse geologic and regional settings. This manual has been written as a working document, establishing a framework and methodology for proper site selection for CO2 geologic storage. This will be useful for future CO2 emitters, transporters, and storage providers. It will also be of use in informing local, regional, state, and national governmental agencies of best practices in proper sequestration site selection. Furthermore, it will educate the inquisitive general public on options and processes for geologic CO2 storage. In addition to providing best practices, the manual presents a geologic storage resource and capacity classification system. The system provides a "standard" to communicate storage and capacity estimates, uncertainty and project development risk, data guidelines and analyses for adequate site characterization, and

  10. Pyramid mountain diesel fuel storage site remediation

    Energy Technology Data Exchange (ETDEWEB)

    Brolmsa, M.; Sandau, C. [Jacques Whitford Environment Ltd., Burnaby, BC (Canada)

    2005-07-01

    Remediation activities during the decommissioning of a microwave tower facility where a tram line was used to transfer diesel fuel from the base of a mountain to its summit were described. As the site was leased from Parks Canada, federal guidelines were used to assess levels of contamination. Underground storage tanks (USTs) used for diesel storage had been replaced with aboveground storage tanks (AST) in 1994. Remediation was also complicated by the remote location and altitude of the site, as well as by extreme weather conditions. Hand auguring and test pitting were used at both the summit and base to allow characterization and preliminary delineation of impacted soils. A heavy lift helicopter was used to place demolition and excavation equipment on the summit. An excavator was used to remove hydrocarbon impacted soils. Following the remedial excavation for the summit diesel AST, residual soil impacts in excess of the applicable remediation guidelines were present at the bottom of the tank nest and under a floor slab. An environmental liner was installed, and a quantitative screening level risk assessment demonstrated the low level of risk for the area, as well as for waste oil impacted soils on the slope below the summit. Contaminants of potential concern were barium, zinc, naphthalene, and petroleum hydrocarbon fractions F1-F4. It was concluded that there are now no unacceptable ecological or human risks from residual impacts at the site. 1 tab., 19 figs.

  11. Identification and capacity quantification of CO{sub 2} storage sites

    Energy Technology Data Exchange (ETDEWEB)

    Bachu, Stefan [Energy Resources Conservation Board (Canada)

    2008-07-15

    In this presentation the subject of scales of evaluation of the sites of CO{sub 2} storage is commented. Also the criteria to identify river basins and sites appropriated for the CO{sub 2} storage are analyzed and finally the matter of the estimation of the capacities of CO{sub 2} storage is analyzed. [Spanish] En esta presentacion se comenta sobre las escalas de evaluacion de los sitios de almacenamiento de CO{sub 2}. Tambien se analizan los criterios para identificar cuencas y lugares adecuados para el almacenamiento de CO{sub 2} y por ultimo se habla sobre la estimacion de las capacidades de almacenamiento de CO{sub 2}.

  12. Natural phenomena evaluations of the K-25 site UF6 cylinder storage yards

    International Nuclear Information System (INIS)

    Fricke, K.E.

    1996-01-01

    The K-25 Site UF 6 cylinder storage yards are used for the temporary storage of UF 6 normal assay cylinders and long-term storage of other UF 6 cylinders. The K-25 Site UF 6 cylinder storage yards consist of six on-site areas: K-1066-B, K-1066-E, K-1066-F, K-1066-J, K-1066-K and K-1066-L. There are no permanent structures erected on the cylinder yards, except for five portable buildings. The operating contractor for the K-25 Site is preparing a Safety Analysis Report (SAR) to examine the safety related aspects of the K-25 Site UF 6 cylinder storage yards. The SAR preparation encompasses many tasks terminating in consequence analysis for the release of gaseous and liquid UF 6 , one of which is the evaluation of natural phenomena threats, such as earthquakes, floods, and winds. In support of the SAR, the six active cylinder storage yards were evaluated for vulnerabilities to natural phenomena, earthquakes, high winds and tornados, tornado-generated missiles, floods (local and regional), and lightning. This report summarizes those studies. 30 refs

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

    International Nuclear Information System (INIS)

    1991-08-01

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

  14. On-site interim storage of spent nuclear fuel: Emerging public issues

    International Nuclear Information System (INIS)

    Feldman, D.L.; Tennessee Univ., Knoxville, TN

    1992-01-01

    Failure to consummate plans for a permanent repository or above- ground interim Monitored Retrievable Storage (MRS) facility for spent nuclear fuel has spurred innovative efforts to ensure at-reactor storage in an environmentally safe and secure manner. This article examines the institutional and socioeconomic impacts of Dry Cask Storage Technology (DCST)-an approach to spent fuel management that is emerging as the preferred method of on-site interim spent fuel storage by utilities that exhaust existing storage capacity

  15. Contaminated site investigation using nuclear technique: a case study of temporary transformer storage sites in Ghana

    International Nuclear Information System (INIS)

    Sanu, J. K.

    2013-07-01

    Recent introduction of man-made toxic chemicals, and the massive relocation of natural materials to different environmental compartment like soil, ground water and atmosphere, has resulted in severe pressure on the self- cleansing capacity of recipient ecosystems. Various accomulated pollutants and contaminants such as polychlorinated biphenyls (PCBs) are of much concern relative to both human and ecosystemm exposure and potential health impact. PCBs which are resistant to degradation and bioremediation accumulated in different niches of the biosphere. This significantly affects the ecological balances and cause adverse health effect on both human and the environment. Temporal transformer storage sites at four locations in Ghana (Tema, Temale, Bolgatanga and Wa) were investigated for PCB contamination using nuclear techniques. Analysis of soil samples from four temporal transformer storage sites revealed that the soil samples from Tema, Tamale, Bolgatanga and Wa were generally sandy with pH and EC ranging between 6.24 - 7.29 and 44.60 - 188.30 respectively. The PCB levels detected in the soil samples from the various locations varied considerably with mean ranging between 7.69 and 51.92 mg/kg. The highest mean PCB level was recorded at the Tema temporal transformer storage site (51.92 mg/kg), whilst the least mean level of 7.69 mg/kg was recorded at Wa storage site. At Tamale the individual levels range between 3.57 mg/kg and 38.70 mg/kg while at Bolgatanga it was 6.85 - 16.30 mg/kg and Wa, 6.08 - 14.70mg/kg. About 9% of soil samples from temporal transformer storage sites analysed had total PCBs concentrations above the 25mg/kg and 33 mg/kg level recommended by the Canadian Council of Ministers of environment (CCME) and EPA Ghana respectively for the protection of environment and human health. Generally, the Levels of PCBs in soil samples were found to decrease with increasing depth at all the temporal transformer storage sites. Results obtained using the EPA's L

  16. On-site concrete cask storage system for spent nuclear fuel

    International Nuclear Information System (INIS)

    Craig, P.A.; Haelsig, R.T.; Kent, J.D.; Schmoker, D.S.

    1989-01-01

    A method is described of storing spent nuclear fuel assemblies including the steps of: transferring the fuel assemblies from a spent-fuel pool to a moveable concrete storage cask located outside the spent-fuel pool; maintaining a barrier between the fuel and the concrete in the cask to prevent contamination of the concrete by the fuel; maintaining the concrete storage cask containing the spent-fuel on site at the reactor complex for some predetermined period; transferring the fuel assemblies from the concrete storage cask to a shipping container; and, recycling the concrete storage cask

  17. Hazelwood Interim Storage Site annual site environmental report: Calendar year 1986

    International Nuclear Information System (INIS)

    1987-06-01

    During 1986, the environmental monitoring program was continued at the Hazelwood Interim Storage Site (HISS), a US Department of Energy (DOE) facility located in the City of Hazelwood, Missouri. Originally known as the Cotter Corporation site on Latty Avenue in Hazelwood, the HISS is presently used for the storage of soils contaminated with residual radioactive material. As part of the decontamination research and development project authorized by Congress under the 1984 Energy and Water Appropriations Act, remedial action and environmental monitoring program are being conducted at the site and at vicinity properties by Bechtel National, Inc., Project Management Contractor for FUSRAP. The monitoring program at the HISS measures radon gas concentrations in air; external gamma radiation levels; and uranium, radium, and thorium concentrations in surface water, groundwater, and sediment. To verify that the site is in compliance with the DOE radiation protection standard (100 mrem/yr) and assess its potential effect on public health, the radiation dose was calculated for the maximally exposed individual. Based on the scenario described in this report, the maximally exposed individual at the HISS would receive an annual external exposure approximately equivalent to 2% of the DOE radiation protection standard of 100 mrem/yr. This exposure is less than the exposure a person would receive during a round-trip flight from New York to Los Angeles. The cumulative dose to the population within an 80-km (50-mi) radius of the HISS that would result from radioactive materials present at the site would be indistinguishable from the dose that the same population would receive from naturally occurring radioactive sources. Results of the 1986 monitoring show that the HISS is in compliance with the DOE radiation protection standard. 11 refs., 6 figs., 10 tabs

  18. Perry Nuclear Plant's Plans for on-site storage

    International Nuclear Information System (INIS)

    Ratchen, J.T.

    1993-01-01

    Because of current radwaste disposal legislation and the eventual denial of access to the Barnwell, Richland, and Beatty burial sites, it was imperative for the Perry nuclear power plant to develop alternative means for handling its generated radioactive waste. The previous radwaste facilities at Perry were developed for processing, packaging, short-term storage, and shipment for burial. In order to meet the changing needs, new facilities have been constructed to handle the processing, packaging, and 5-yr interim storage of both dry active waste (DAW) and dewatered or solidified resin, filter media, etc

  19. Initial Operation of the Savannah River Site Advanced Storage Monitoring Facility

    International Nuclear Information System (INIS)

    McCurry, D.R.

    2001-01-01

    An advanced storage monitoring facility has been constructed at the Savannah River Site capable of storing sensitive nuclear materials (SNM) with access to monitoring information available over the Internet. This system will also have monitoring information available over the Internet to appropriate users. The programs will ultimately supply authenticated and encrypted data from the storage sites to certified users to demonstrate the capability of using the Internet as a safe and secure communications medium for remote monitoring of sensitive items

  20. The dry spent RBMK fuel cask storage site at the Ignalina NPP in Lithuania

    International Nuclear Information System (INIS)

    Penkov, V.V.; Diersch, R.

    1999-01-01

    At present, there are about 15,000 spent RBMK fuel assemblies stored in the water pools near the reactors at the Ignalina Nuclear Power Plant (INPP). Part of them are cut in two bundles and stored in standardized baskets in the pools. Each basket is loaded with 102 bundles. For long-term interim storage of this fuel, it was decided to use dry storage in casks. For this reason, the total activity to be stored is split into individual units (casks). Each cask represents a closed and independent safety system, fulfilling all safety-relevant requirements for both normal operational and hypothetical accidental conditions. The main safety relevant features of the storage cask system are: (1) Inherent safety system; (2) Double barrier system; (3) Passive cooling by natural convection; (4) Safety against accidents. The cask dry storage system is a cost effective and multi-functional system for storage, transport after the operation time and final disposal under consideration of additional protective elements. From an economical point of view, cask storage has a number of advantages. Two cask types have been intended for the INPP storage site: (1) The CASTOR RBMK cask made of ductile cast iron; (2) The CONSTOR RBMK sandwich cask made of an inner and outer steel shell and reinforced heavy concrete. The CASTOR RBMK and the CONSTOR RBMK casks are designed to withstand severe storage site accidents and with help of impact limiters - to fulfil the IAEA test criteria for type B(U)F packages. The INPP spent RBMK fuel storage site is designed as an open air storage for an operational time of 50 years. The casks are arranged on the concrete storage pad. The site is equipped with a crane for cask handling and technological buildings and security systems. The safety analyses for fuel and cask handling and for cask handling and for cask technology at the site have been made and accepted by the Lithuanian Competent Authority. (author)

  1. The potential of near-surface geophysical methods in a hierarchical monitoring approach for the detection of shallow CO2 seeps at geological storage sites

    Science.gov (United States)

    Sauer, U.; Schuetze, C.; Dietrich, P.

    2013-12-01

    The MONACO project (Monitoring approach for geological CO2 storage sites using a hierarchic observation concept) aims to find reliable monitoring tools that work on different spatial and temporal scales at geological CO2 storage sites. This integrative hierarchical monitoring approach based on different levels of coverage and resolutions is proposed as a means of reliably detecting CO2 degassing areas at ground surface level and for identifying CO2 leakages from storage formations into the shallow subsurface, as well as CO2 releases into the atmosphere. As part of this integrative hierarchical monitoring concept, several methods and technologies from ground-based remote sensing (Open-path Fourier-transform infrared (OP-FTIR) spectroscopy), regional measurements (near-surface geophysics, chamber-based soil CO2 flux measurement) and local in-situ measurements (using shallow boreholes) will either be combined or used complementary to one another. The proposed combination is a suitable concept for investigating CO2 release sites. This also presents the possibility of adopting a modular monitoring concept whereby our monitoring approach can be expanded to incorporate other methods in various coverage scales at any temporal resolution. The link between information obtained from large-scale surveys and local in-situ monitoring can be realized by sufficient geophysical techniques for meso-scale monitoring, such as geoelectrical and self-potential (SP) surveys. These methods are useful for characterizing fluid flow and transport processes in permeable near-surface sedimentary layers and can yield important information concerning CO2-affected subsurface structures. Results of measurements carried out a natural analogue site in the Czech Republic indicate that the hierarchical monitoring approach represents a successful multidisciplinary modular concept that can be used to monitor both physical and chemical processes taking place during CO2 migration and seepage. The

  2. Wayne Interim Storage Site annual environmental report for calendar year 1991, Wayne, New Jersey. [Wayne Interim Storage Site

    Energy Technology Data Exchange (ETDEWEB)

    None

    1992-09-01

    This document describes the envirormental monitoring program at the Wayne Interim Storage Site (WISS) and surrounding area, implementation of the program, and monitoring results for 1991. Environmental monitoring of WISS and surrounding area began in 1984 when Congress added the site to the US Department of Energy's (DOE) Formerly Utilized Sites Remedial Action Program (FUSRAP). FUSRAP is a DOE program to decontaminate or otherwise control sites where residual radioactive materials remain from the early years of the nation's atomic energy program or from commercial operations causing conditions that Congress has authorized DOE to remedy. WISS is a National Priorities List site. The environmental monitoring program at WISS includes sampling networks for radon and thoron concentrations in air; external gamma radiation exposure; and radium-226, radium-228, thorium-232, and total uranium concentrations in surface water, sediment, and groundwater. Several nonradiological parameters are also measured in groundwater. Monitoring results are compared with applicable Environmental Protection Agency standards, DOE derived concentration guides, dose limits, and other requirements in DOE orders. Environmental standards are established to protect public health and the environment.

  3. Closure Report for Corrective Action Unit 134: Aboveground Storage Tanks, Nevada Test Site, Nevada

    International Nuclear Information System (INIS)

    2009-01-01

    Corrective Action Unit (CAU) 134 is identified in the Federal Facility Agreement and Consent Order (FFACO) as 'Aboveground Storage Tanks' and consists of the following four Corrective Action Sites (CASs), located in Areas 3, 15, and 29 of the Nevada Test Site: (1) CAS 03-01-03, Aboveground Storage Tank; (2) CAS 03-01-04, Tank; (3) CAS 15-01-05, Aboveground Storage Tank; and (4) CAS 29-01-01, Hydrocarbon Stain

  4. Thermococcus guaymasensis sp. nov. and Thermococcus aggregans sp. nov., two novel thermophilic archaea isolated from the Guaymas Basin hydrothermal vent site.

    Science.gov (United States)

    Canganella, F; Jones, W J; Gambacorta, A; Antranikian, G

    1998-10-01

    Thermococcus strains TYST and TYT isolated from the Guaymas Basin hydrothermal vent site and previously described were compared by DNA-DNA hybridization analysis with the closest Thermococcus species in terms of physiology and nutritional aspects. On the basis of the new data and taking into consideration the molecular, physiological and morphological traits published previously, it is proposed that strains TYT and TYST should be classified as new species named Thermococcus aggregans sp. nov. and Thermococcus guaymasensis sp. nov., respectively. The type strain of T. aggregans is strain TYT (= DSM 10597T) and the type strain of T. guaymasensis is strain TYST (= DSM 11113T).

  5. Final storage site for radioactive waste. Gorleben mine

    International Nuclear Information System (INIS)

    1995-02-01

    Out of more than 20 salt stocks, the Gorleben salt stock was chosen. In addition to the preliminary information available on its size and depth, detailed exploratory investigations were carried out in order to test its suitability as a site for ultimate storage of all types of radioactive waste. (orig.) [de

  6. 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

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

    International Nuclear Information System (INIS)

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

    1986-04-01

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

  8. How to characterize a potential site for CO2 storage with sparse data coverage - a Danish onshore site case

    International Nuclear Information System (INIS)

    Nielsen, Carsten Moller; Frykman, Peter; Dalhoff, Finn

    2015-01-01

    The paper demonstrates how a potential site for CO 2 storage can be evaluated up to a sufficient level of characterization for compiling a storage permit application, even if the site is only sparsely explored. The focus of the paper is on a risk driven characterization procedure. In the initial state of a site characterization process with sparse data coverage, the regional geological and stratigraphic understanding of the area of interest can help strengthen a first model construction for predictive modeling. Static and dynamic modeling in combination with a comprehensive risk assessment can guide the different elements needed to be evaluated for fulfilling a permit application. Several essential parameters must be evaluated; the storage capacity for the site must be acceptable for the project life of the operation, the trap configuration must be efficient to secure long term containment, the injectivity must be sufficient to secure a longstanding stable operation and finally a satisfactory and operational measuring strategy must be designed. The characterization procedure is demonstrated for a deep onshore aquifer in the northern part of Denmark, the Vedsted site. The site is an anticlinal structural closure in an Upper Triassic - Lower Jurassic sandstone formation at 1 800-1 900 m depth. (authors)

  9. Niagara Falls Storage Site annual environmental report for calendar year 1991, Lewiston, New York. [Niagara Falls Storage Site

    Energy Technology Data Exchange (ETDEWEB)

    1992-09-01

    This document describes the environmental monitoring program at the Niagara Falls Storage Site (NFSS) and surrounding area, implementation of the program, and monitoring results for 1991. Environmental monitoring at NFSS began in 1981. The site is owned by the US Department of Energy (DOE) and is assigned to the DOE Formerly Utilized Sites Remedial Action Program (FUSRAP). FUSRAP is a program to decontaminate or otherwise control sites where residual radioactive materials remain from the early years of the nation's atomic energy program or from commercial operations causing conditions that Congress has authorized DOE to remedy. The environmental monitoring program at NFSS includes sampling networks for radon concentrations in air; external gamma radiation exposure; and total uranium and radium-226 concentrations in surface water, sediments, and groundwater. Additionally, several nonradiological parameters including seven metals are routinely measured in groundwater. Monitoring results are compared with applicable Environmental Protection Agency (EPA) standards, DOE derived concentration guides (DCGs), dose limits, and other requirements in DOE orders. Environmental standards are established to protect public health and the environment.

  10. Maywood Interim Storage Site annual environmental report for calendar year 1991, Maywood, New Jersey. [Maywood Interim Storage Site

    Energy Technology Data Exchange (ETDEWEB)

    None

    1992-09-01

    This document describes the environmental monitoring program at the Maywood Interim Storage Site (MISS) and surrounding area, implementation of the program, and monitoring results for 1991. Environmental monitoring of MISS began in 1984 when congress added the site to the US Department of Energy's (DOE) Formerly Utilized Sites Remedial Action Program (FUSRAP). FUSRAP is a DOE program to identify and decontaminate or otherwise control sites where residual radioactive materials remain from the early years of the nation's atomic energy program or from commercial operations causing conditions that Congress has authorized DOE to remedy. The environmental monitoring program at MISS includes sampling networks for radon and thoron concentrations in air; external gamma radiation-exposure; and total uranium, radium-226, radium-228, thorium-232, and thorium-230 concentrations in surface water, sediment, and groundwater. Additionally, several nonradiological parameters are measured in surface water, sediment, and groundwater. Monitoring results are compared with applicable Environmental Protection Agency standards, DOE derived concentration guides (DCGs), dose limits, and other requirements in DOE orders. Environmental standards are established to protect public health and the environment.

  11. CLOSURE REPORT FOR CORRECTIVE ACTION UNIT 204: STORAGE BUNKERS, NEVADA TEST SITE, NEVADA

    International Nuclear Information System (INIS)

    2006-01-01

    Corrective Action Unit (CAU) 330 consists of four Corrective Action Sites (CASs) located in Areas 6, 22, and 23 of the Nevada Test Site (NTS). The unit is listed in the Federal Facility Agreement and Consent Order (FFACO, 1996) as CAU 330: Areas 6, 22, and 23 Tanks and Spill Sites. CAU 330 consists of the following CASs: CAS 06-02-04, Underground Storage Tank (UST) and Piping CAS 22-99-06, Fuel Spill CAS 23-01-02, Large Aboveground Storage Tank (AST) Farm CAS 23-25-05, Asphalt Oil Spill/Tar Release

  12. Pengaruh Perbedaan Konsentrasi Ekstrak Sargassum sp. dan Lama Penyimpanan terhadap Oksidasi Lemak pada Fillet Ikan Patin (Pangasius sp.

    Directory of Open Access Journals (Sweden)

    Fatin Hidayati

    2017-05-01

    storage time in inhibiting the oxidation process in catfish fillet. The materials used in this research were Sargassum sp. extracts and catfish fillet. This research was using experimental laboratories research method with factorial Completely Randomized Research Design (CRD of 2 factors which were concentrations of Sargassum sp. extracts (0%, 1%, 1.5%, and 2% and storage time (0 day, 2 days, 4 days, and 6 days. The results showed that the adding of different concentrations of Sargassum sp. extracts and storage time gave significant effect to the PV value, TBA value, fat content, protein content, moisture content, as well as organoleptic point (P < 0.05. The results obtained from stage I research were the yields of Sargassum sp. with ethanol 96% solvent was 1.39%, phenol content was 1.813%, flavonoid was 0.278%, and antioxidant activity was 99.1659 ppm (categorized as strong antioxidant. The results obtained from stage II research were the PV value were ranged from 2.03 to 19.82 meq/kg, TBA value were ranged from 0.63 to 6.72 mg.mal/kg. The 1.5% concentration was the best concentration of Sargassum sp. extracts in inhibiting the lipid oxidation of catfish fillet during storage. Keywords: Antioxidant, Sargassum sp. Extracts, Storage Time, Lipid Oxidation, Catfish Fillet Citation: Hidayati, F., Darmanto, Y.S. dan Romadhon. (2017. Pengaruh Perbedaan Konsentrasi Ekstrak Sargassum sp. dan Lama Penyimpanan terhadap Oksidasi Lemak pada Fillet Ikan Patin (Pangasius sp.. Jurnal Ilmu Lingkungan, 15(1, 64-73, doi:10.14710/jil.15.1.64-73

  13. Hanford Site Waste Storage Tank Information Notebook

    International Nuclear Information System (INIS)

    Husa, E.I.; Raymond, R.E.; Welty, R.K.; Griffith, S.M.; Hanlon, B.M.; Rios, R.R.; Vermeulen, N.J.

    1993-07-01

    This report provides summary data on the radioactive waste stored in underground tanks in the 200 East and West Areas at the Hanford Site. The summary data covers each of the existing 161 Series 100 underground waste storage tanks (500,000 gallons and larger). It also contains information on the design and construction of these tanks. The information in this report is derived from existing reports that document the status of the tanks and their materials. This report also contains interior, surface photographs of each of the 54 Watch List tanks, which are those tanks identified as Priority I Hanford Site Tank Farm Safety Issues in accordance with Public Law 101-510, Section 3137*

  14. Niagara Falls Storage Site, Lewiston, New York: geologic report

    International Nuclear Information System (INIS)

    1984-06-01

    This report is one of a series of engineering and environmental reports planned for the US Department of Energy's properties at Niagara Falls, New York. It describes the essential geologic features of the Niagara Falls Storage Site. It is not intended to be a definitive statement of the engineering methods and designs required to obtain desired performance features for any permanent waste disposal at the site. Results are presented of a geological investigation that consisted of two phases. Phase 1 occurred during July 1982 and included geologic mapping, geophysical surveys, and a limited drilling program in the vicinity of the R-10 Dike, planned for interim storage of radioactive materials. Phase 2, initiated in December 1982, included excavation of test pits, geophysical surveys, drilling, observation well installation, and field permeability testing in the South Dike Area, the Northern Disposal Area, and the K-65 Tower Area

  15. Niagara Falls Storage Site, Lewiston, New York: geologic report

    Energy Technology Data Exchange (ETDEWEB)

    1984-06-01

    This report is one of a series of engineering and environmental reports planned for the US Department of Energy's properties at Niagara Falls, New York. It describes the essential geologic features of the Niagara Falls Storage Site. It is not intended to be a definitive statement of the engineering methods and designs required to obtain desired performance features for any permanent waste disposal at the site. Results are presented of a geological investigation that consisted of two phases. Phase 1 occurred during July 1982 and included geologic mapping, geophysical surveys, and a limited drilling program in the vicinity of the R-10 Dike, planned for interim storage of radioactive materials. Phase 2, initiated in December 1982, included excavation of test pits, geophysical surveys, drilling, observation well installation, and field permeability testing in the South Dike Area, the Northern Disposal Area, and the K-65 Tower Area.

  16. Site safety progress review of spent fuel central interim storage facility. Final report

    International Nuclear Information System (INIS)

    Gurpinar, A.; Serva, L.; Giuliani

    1995-01-01

    Following the request of the Czech Power Board (CEZ) and within the scope of the Technical Cooperation Project CZR/9/003, a progress review of the site safety of the Spent Fuel Central Interim Storage Facility (SFCISF) was performed. The review involved the first two stages of the works comprising the regional survey and identification of candidate sites for the underground and surface storage options. Five sites have been identified as a result of the previous works. The following two stages will involved the identification of the preferred candidate sites for the two options and the final site qualification. The present review had the purpose of assessing the work already performed and making recommendations for the next two stages of works

  17. Maywood Interim Storage Site environmental report for calendar year 1989, Maywood, New Jersey

    International Nuclear Information System (INIS)

    1990-05-01

    The environmental monitoring program, which began in 1984, was continued in 1989 at the Maywood Interim Storage Site (MISS), a US Department of Energy (DOE) facility located in the Borough of Maywood and the Township of Rochelle Park, New Jersey. MISS is currently used for storage of soils contaminated with low-level radioactivity. MISS is part of the Formerly Utilized Sites Remedial Action Program (FUSRAP), a DOE program to identify and decontaminate or otherwise control sites where residual radioactive materials are present. The monitoring program at MISS measures thoron and radon concentrations in air; external gamma radiation levels; and thorium, uranium, and radium concentrations in surface water, groundwater, and sediment. Additionally, several nonradiological parameters are measured in groundwater. The radiation dose was calculated for a hypothetical maximally exposed individual to verify that the site is in compliance with the DOE radiation protection standard (100 mrem/yr) and to assess its potential effects on public health. This report presents the results of the environmental monitoring program conducted at the US Department of Energy's (DOE) Maywood Interim Storage Site (MISS) during calendar year 1989. Environmental monitoring began at MISS in 1984. 19 refs., 23 figs., 14 tabs

  18. Maywood Interim Storage Site environmental report for calendar year 1989, Maywood, New Jersey

    Energy Technology Data Exchange (ETDEWEB)

    1990-05-01

    The environmental monitoring program, which began in 1984, was continued in 1989 at the Maywood Interim Storage Site (MISS), a US Department of Energy (DOE) facility located in the Borough of Maywood and the Township of Rochelle Park, New Jersey. MISS is currently used for storage of soils contaminated with low-level radioactivity. MISS is part of the Formerly Utilized Sites Remedial Action Program (FUSRAP), a DOE program to identify and decontaminate or otherwise control sites where residual radioactive materials are present. The monitoring program at MISS measures thoron and radon concentrations in air; external gamma radiation levels; and thorium, uranium, and radium concentrations in surface water, groundwater, and sediment. Additionally, several nonradiological parameters are measured in groundwater. The radiation dose was calculated for a hypothetical maximally exposed individual to verify that the site is in compliance with the DOE radiation protection standard (100 mrem/yr) and to assess its potential effects on public health. This report presents the results of the environmental monitoring program conducted at the US Department of Energy's (DOE) Maywood Interim Storage Site (MISS) during calendar year 1989. Environmental monitoring began at MISS in 1984. 19 refs., 23 figs., 14 tabs.

  19. Fires at storage sites of organic materials, waste fuels and recyclables.

    Science.gov (United States)

    Ibrahim, Muhammad Asim; Alriksson, Stina; Kaczala, Fabio; Hogland, William

    2013-09-01

    During the last decade, the European Union has enforced the diversion of organic wastes and recyclables to waste management companies operating incineration plants, composting plants and recycling units instead of landfills. The temporary storage sites have been established as a buffer against fluctuations in energy demand throughout the year. Materials also need to be stored at temporary storage sites before recovery and recycling. However, regulations governing waste fuel storage and handling have not yet been developed, and, as a result, companies have engaged in risky practices that have resulted in a high number of fire incidents. In this study, a questionnaire survey was distributed to 249 of the 400 members of Avfall Sverige (Swedish Waste Management Association), which represents the waste management of 95% of the Swedish population. Information regarding 122 storage facilities owned by 69 companies was obtained; these facilities were responsible for the storage of 47% of the total treated waste (incineration + digestion + composting) in 2010 in Sweden. To identify factors related to fire frequency, the questionnaire covered the amounts of material handled and burnt per year, financial losses due to fires, storage duration, storage method and types of waste. The results show that 217 fire incidents corresponded to 170 kilotonnes of material burnt and cumulative losses of 49 million SEK (€4.3 million). Fire frequency and amount of material burnt per fire was found to be dependent upon type of management group (waste operator). Moreover, a correlation was found between fire frequency and material recycled during past years. Further investigations of financial aspects and externalities of fire incidents are recommended.

  20. Criticality Safety Evaluation of Hanford Site High Level Waste Storage Tanks

    Energy Technology Data Exchange (ETDEWEB)

    ROGERS, C.A.

    2000-02-17

    This criticality safety evaluation covers operations for waste in underground storage tanks at the high-level waste tank farms on the Hanford site. This evaluation provides the bases for criticality safety limits and controls to govern receipt, transfer, and long-term storage of tank waste. Justification is provided that a nuclear criticality accident cannot occur for tank farms operations, based on current fissile material and operating conditions.

  1. Criticality Safety Evaluation of Hanford Site High-Level Waste Storage Tanks

    International Nuclear Information System (INIS)

    ROGERS, C.A.

    2000-01-01

    This criticality safety evaluation covers operations for waste in underground storage tanks at the high-level waste tank farms on the Hanford site. This evaluation provides the bases for criticality safety limits and controls to govern receipt, transfer, and long-term storage of tank waste. Justification is provided that a nuclear criticality accident cannot occur for tank farms operations, based on current fissile material and operating conditions

  2. A Bookless Library, Part I: Relocating Print Materials to Off-Site Storage

    Science.gov (United States)

    Sewell, Bethany B.

    2013-01-01

    This article presents an analysis of the feasibility of a bookless library in a research setting. As spaces for collections are being converted for increased study and community spaces, many libraries have been moving low-use collections to off-site storage. Issues regarding the types of storage spaces available are addressed. Concerns and…

  3. Spent-fuel storage - MRS and/or on-site?

    International Nuclear Information System (INIS)

    Fuierer, A.A.

    1991-01-01

    The US government through the Office of Civilian Radioactive Waste Management (OCRWM) is seeking by the use of an authorized negotiator a site for a monitored retrievable storage (MRS) facility. Based on a public information document provided by the office of the negotiator, the MRS will be an integral part of the federal system for safe and permanent disposal of the nation's high-level radioactive wastes. It is planned that the MRS will accept and store spent fuel above ground until a repository opens and spent fuel that has been stored is shipped from the MRS to the repository. Additional spent fuel stored at reactor sites will be shipped to the MRS, which will be used as a staging area to assemble dedicated trains for shipment to the repository. The intent of the MRS is to reduce utilities' needs to expand on-site storage of spent fuel. A utility viewpoint may emphasize an alternate set of priorities. The waste management system must be considered as an overall system involving both the utility and DOE that begins with the first discharge of spent nuclear fuel from a commercial reactor and ends with high-level waste in a final repository. Many studies have been made on individual components of a waste system. This study, with the benefit of past hands-on experience as a guide, looks at costs and reliability for a total system concept with particular emphasis on the interface between the utility and Department of Energy

  4. Overview of the spent nuclear fuel storage facilities at the Savannah River Site

    International Nuclear Information System (INIS)

    Conatser, E.R.; Thomas, J.E.

    2000-01-01

    The May 1996 Record of Decision on a Proposed Nuclear Weapons Nonproliferation Policy concerning Foreign Research Reactor Spent Nuclear Fuel initiated a 13 year campaign renewing a policy to support the return of spent nuclear fuel containing uranium of U.S. origin from foreign research reactors to the United States. As of December 1999, over 22% of the approximately 13,000 spent nuclear fuel assemblies from participating countries have been returned to the Savannah River Site (SRS). These ∼2650 assemblies are currently stored in two dedicated SRS wet storage facilities. One is the Receiving Basin for Off-site Fuels (RBOF) and the other as L-Basin. RBOF, built in the early 60's to support the 'Atoms for Peace' program, has been receiving off-site fuel for over 35 years. RBOF has received approximately 1950 casks since startup and has the capability of handling all of the casks currently used in the FRR program. However, RBOF is 90% filled to capacity and is not capable of storing all of the fuel to be received in the program. L-Basin was originally used as temporary storage for materials irradiated in SRS's L-Reactor. New storage racks and other modifications were completed in 1996 that improved water quality and allowed the L-Basin to receive, handle and store spent nuclear fuel assemblies and components from off-site. The first foreign cask was received into the L-Area in April 1997 and approximately 105 foreign and domestic casks have been received since that time. This paper provides an overview of activities related to fuel receipt and storage in both the Receiving Basin for Off-site Fuels (RBOF) and L-Basin facilities. It will illustrate each step of the fuel receipt program from arrival of casks at SRS through cask unloading and decontamination. It will follow the fuel handling process, from fuel unloading, through the cropping and bundling stages, and final placement in the wet storage rack. Decontamination methods and equipment will be explained to show

  5. Overview of the spent nuclear fuel storage facilities at the Savannah River Site

    International Nuclear Information System (INIS)

    Thomas, Jay

    1999-01-01

    The May 1996 Record of Decision on a Proposed Nuclear Weapons Nonproliferation Policy concerning Foreign Research Reactor Spent Nuclear Fuel initiated a 13 year campaign renewing a policy to support the return of spent nuclear fuel containing uranium of U.S.-origin from foreign research reactors to the United States. As of July 1999, over 18% of the approximately 13,000 spent nuclear fuel assemblies from participating countries have been returned to the Savannah River Site (SRS). These 2400 assemblies are currently stored in two dedicated SRS wet storage facilities. One is the Receiving Basin for Off-site Fuels (RBOF) and the other as L-Basin. RBOF, built in the early 60's to support the 'Atoms for Peace' program, has been receiving off-site fuel for over 35 years. RBOF has received approximately 1950 casks since startup and has the capability of handling all of the casks currently used in the FRR program. However, RBOF is 90% filled to capacity and is not capable of storing all of the fuel to be received in the program. L-Basin was originally used as temporary storage for materials irradiated in SRS's L-Reactor. New storage racks and other modifications were completed in 1996 that improved water quality and allowed L-Basin to receive, handle and store spent nuclear fuel assemblies and components from off-site. The first foreign cask was received into L-Area in April 1997 and approximately 86 foreign and domestic casks have been received since that time. This paper provides an overview of activities related to fuel receipt and storage in both the Receiving Basin for Off-site Fuels (RBOF) and L-Basin facilities. It will illustrate each step of the fuel receipt program from arrival of casks at SRS through cask unloading and decontamination. It will follow the fuel handling process, from fuel unloading, through the cropping and bundling stages, and final placement in the wet storage rack. Decontamination methods and equipment will be explained to show how the empty

  6. Overview of the spent nuclear fuel storage facilities at the Savannah River Site

    Energy Technology Data Exchange (ETDEWEB)

    Conatser, E.R.; Thomas, J.E. [Westinghouse Savannah River Company, Aiken, SC 29808 (United States)

    2000-07-01

    The May 1996 Record of Decision on a Proposed Nuclear Weapons Nonproliferation Policy concerning Foreign Research Reactor Spent Nuclear Fuel initiated a 13 year campaign renewing a policy to support the return of spent nuclear fuel containing uranium of U.S. origin from foreign research reactors to the United States. As of December 1999, over 22% of the approximately 13,000 spent nuclear fuel assemblies from participating countries have been returned to the Savannah River Site (SRS). These {approx}2650 assemblies are currently stored in two dedicated SRS wet storage facilities. One is the Receiving Basin for Off-site Fuels (RBOF) and the other as L-Basin. RBOF, built in the early 60's to support the 'Atoms for Peace' program, has been receiving off-site fuel for over 35 years. RBOF has received approximately 1950 casks since startup and has the capability of handling all of the casks currently used in the FRR program. However, RBOF is 90% filled to capacity and is not capable of storing all of the fuel to be received in the program. L-Basin was originally used as temporary storage for materials irradiated in SRS's L-Reactor. New storage racks and other modifications were completed in 1996 that improved water quality and allowed the L-Basin to receive, handle and store spent nuclear fuel assemblies and components from off-site. The first foreign cask was received into the L-Area in April 1997 and approximately 105 foreign and domestic casks have been received since that time. This paper provides an overview of activities related to fuel receipt and storage in both the Receiving Basin for Off-site Fuels (RBOF) and L-Basin facilities. It will illustrate each step of the fuel receipt program from arrival of casks at SRS through cask unloading and decontamination. It will follow the fuel handling process, from fuel unloading, through the cropping and bundling stages, and final placement in the wet storage rack. Decontamination methods and equipment

  7. Method of impact evaluation of storage sites for uranium ore tailings

    International Nuclear Information System (INIS)

    Servant, A.C.; Cessac, B.

    2001-11-01

    Mining and ore processing generate liquid effluents and solid waste ( tailings) in important quantities. On fifty years exploitation, 50 millions tons of tailings have been stored on twenty sites in France. From a radiological point of view, the uranium tailings contain only natural radioisotopes, daughters of 238 U and 235 U families and for a low part daughter's of 232 Th family. Their activity stay low to very low, under the ore activity. It decreases very slowly because of the long period of some radionuclides ( 230 Th, 75 000 years, 226 Ra, 1600 years). generally stored on the exploitation site, these tailings constitute a radiological source term of which it is necessary to evaluate the impact on man and environment. At close-down of an uranium ore exploitation site, the operator is required to give to the prefect of his region a file of rehabilitation with the dispositions to take to limit the radiological impact of the storage. It is in this frame that the direction of pollutions and risks prevention (D.P.P.R.) from the Minister of Territory landscaping and the Institute of protection and nuclear safety (I.R.S.N.) established a convention, reference 56/2000, relative to investigations in matter of radiological impact evaluation of uranium tailings storage sites, in order to supply a document allowing to judge the pertinence of the different files made by Cogema in the frame of tailings storage of uranium ore processing. The present document constitutes the report planned at the 3. article ( 3. paragraph) of the convention. It gives the information necessary to the evaluation of impact studies for the sites in question. (N.C.)

  8. Remediation and assessment of the national radioactive waste storage and disposal site in Tajikistan - 59110

    International Nuclear Information System (INIS)

    Buriev, Nazirzhon T.; Abdushukurov, Dzhamshed A.; Vandergraaf, Tjalle T.

    2012-01-01

    The National Radioactive Waste Storage and Disposal Site was established in 1959 in the Faizabad region approximately 50 km east of the capital, Dushanbe. The site is located on the southern flank of the Fan Mountains facing the Gissar Valley in a sparsely populated agricultural area, with the nearest villages located a few km from the site. The site was initially designed to accept a wide range of contaminated materials, including obsolete smoke detectors, sealed radioactive sources, waste from medical institutions, and radioactive liquids. Between 1962 and 1976, 363 tonnes and 1146 litres of material, contaminated with a range of radionuclides were shipped to the site. Between 1972 - 1980 and 1985 - 1991, ∼4.8 x 10 14 and 2 x 10 13 Bq, respectively, were shipped to the site. An additional 7 x 10 14 Bq was shipped to the site in 1996. Partly as a result of the dissolution of the former Soviet Union, the disposal site had fallen into disrepair and currently presents both an environmental hazard and a potential for the proliferation of radionuclides that could potentially be used for illicit purposes. Remediation of the disposal site was started in 2005. New security fences were erected and a new superstructure over an in-ground storage site constructed. A central alarm monitoring and observation station has been constructed and is now operational. The geology, flora, and fauna of the region have been documented. Radiation surveys of the buildings and the storage and disposal sites have been carried out. Samples of soil, surface water and vegetation have been taken and analyzed by gamma spectrometry. Results show a slight extent of contamination of soils near the filling ports of the underground liquid storage container where a Cs-137 concentration of 2.3 x 104 Bq/kg was obtained. Similar values were obtained for Ra- 226. Radiation fields of the in-ground storage site were generally 3 . Most of the activity appears to be associated with the sediments in the tank

  9. On-site waste storage assuring the success of on-site, low-level nuclear waste storage

    International Nuclear Information System (INIS)

    Preston, E.L.

    1986-01-01

    Waste management has reached paramount importance in recent years. The successful management of radioactive waste is a key ingredient in the successful operation of any nuclear facility. This paper discusses the options available for on-site storage of low-level radioactive waste and those options that have been selected by the Department of Energy facilities operated by Martin Marietta Energy Systems, Inc. in Oak Ridge, Tennessee. The focus of the paper is on quality assurance (QA) features of waste management activities such as accountability and retrievability of waste materials and waste packages, retrievability of data, waste containment, safety and environmental monitoring. Technical performance and careful documentation of that performance are goals which can be achieved only through the cooperation of numerous individuals from waste generating and waste managing organizations, engineering, QA, and environmental management

  10. Geological Storage of CO2. Site Selection Criteria

    International Nuclear Information System (INIS)

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

    2007-01-01

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

  11. Geological Storage of CO2. Site Selection Criteria

    International Nuclear Information System (INIS)

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

    2006-01-01

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

  12. Probabilistic Assessment of Above Zone Pressure Predictions at a Geologic Carbon Storage Site

    Energy Technology Data Exchange (ETDEWEB)

    Namhata, Argha; Oladyshkin, Sergey; Dilmore, Robert M.; Zhang, Liwei; Nakles, David V.

    2016-12-01

    Carbon dioxide (CO2) storage into geological formations is regarded as an important mitigation strategy for anthropogenic CO2 emissions to the atmosphere. This study first simulates the leakage of CO2 and brine from a storage reservoir through the caprock. Then, we estimate the resulting pressure changes at the zone overlying the caprock also known as Above Zone Monitoring Interval (AZMI). A data-driven approach of arbitrary Polynomial Chaos (aPC) Expansion is then used to quantify the uncertainty in the above zone pressure prediction based on the uncertainties in different geologic parameters. Finally, a global sensitivity analysis is performed with Sobol indices based on the aPC technique to determine the relative importance of different parameters on pressure prediction. The results indicate that there can be uncertainty in pressure prediction locally around the leakage zones. The degree of such uncertainty in prediction depends on the quality of site specific information available for analysis. The scientific results from this study provide substantial insight that there is a need for site-specific data for efficient predictions of risks associated with storage activities. The presented approach can provide a basis of optimized pressure based monitoring network design at carbon storage sites.

  13. Niagara Falls Storage Site environmental surveillance report for calendar year 1993

    International Nuclear Information System (INIS)

    1994-06-01

    This report summarizes the results of environmental surveillance activities conducted at the Niagara Falls Storage Site (NFSS) during calendar year 1993. It includes an overview of site operations, the basis for radiological and nonradiological monitoring, a summary of the results, and the estimated dose to the offsite population. Environmental surveillance activities were conducted in accordance with the site environmental monitoring plan, which describes the rationale and design criteria for the surveillance program, the frequency of sampling and analysis, specific sampling and analysis procedures, and quality assurance requirements. NFSS is in compliance with National Emission Standards for Hazardous Air Pollutants (NESHAPs) Subpart H of the Clean Air Act as well as the requirements of the National Pollutant Discharge Elimination System (NPDES) under the Clean Water Act. Located in northwestern New York, the site covers 191 acres. From 1944 to the present, the primary use of NFSS has been storage of radioactive residues that were by-products of uranium production. Most onsite areas of residual radioactivity above regulatory guidelines were remediated during the early 1980s. Additional isolated areas of onsite contamination were remediated in 1989, and the materials were consolidated into the waste containment structure in 1991. Remediation of the site has now been completed

  14. 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)

  15. Rigorous Screening Technology for Identifying Suitable CO2 Storage Sites II

    Energy Technology Data Exchange (ETDEWEB)

    George J. Koperna Jr.; Vello A. Kuuskraa; David E. Riestenberg; Aiysha Sultana; Tyler Van Leeuwen

    2009-06-01

    This report serves as the final technical report and users manual for the 'Rigorous Screening Technology for Identifying Suitable CO2 Storage Sites II SBIR project. Advanced Resources International has developed a screening tool by which users can technically screen, assess the storage capacity and quantify the costs of CO2 storage in four types of CO2 storage reservoirs. These include CO2-enhanced oil recovery reservoirs, depleted oil and gas fields (non-enhanced oil recovery candidates), deep coal seems that are amenable to CO2-enhanced methane recovery, and saline reservoirs. The screening function assessed whether the reservoir could likely serve as a safe, long-term CO2 storage reservoir. The storage capacity assessment uses rigorous reservoir simulation models to determine the timing, ultimate storage capacity, and potential for enhanced hydrocarbon recovery. Finally, the economic assessment function determines both the field-level and pipeline (transportation) costs for CO2 sequestration in a given reservoir. The screening tool has been peer reviewed at an Electrical Power Research Institute (EPRI) technical meeting in March 2009. A number of useful observations and recommendations emerged from the Workshop on the costs of CO2 transport and storage that could be readily incorporated into a commercial version of the Screening Tool in a Phase III SBIR.

  16. Analysis of the interim safe storage of reactors at the Hanford site

    International Nuclear Information System (INIS)

    Wang Hailiang

    2014-01-01

    The nine production reactors, i.e. B, C, D, DR, F, H, KE, KW and N, at the Hanford site are all water-cooled and graphite-moderated reactors with natural uranium fuel. In 1993, the U.S. Department of Energy (DOE) decided to put eight production reactors (except for B) into Interim Safe Storage (ISS) for 75 years followed by deferred one-piece removal. Reactor B will remain as a national historical landmark. By the end of 2013, six reactors C, F, D, DR, H and N had been successfully put into the ISS. Reactors KE and KW will be put into the ISS in the coming years. Taking reactor C as an example, this paper mainly talks about how to put the production reactors in the Interim Safe Storage, e.g. how to make site preparation, how to construct the safe storage enclosure (SSE) and how to perform surveillance and maintenance during the ISS period, etc. (authors)

  17. Monitored Retrievable Storage facility site screening and evaluation report

    International Nuclear Information System (INIS)

    1985-05-01

    The Nuclear Waste Policy Act of 1982 directs the Department of Energy to ''complete a detailed study of the need for and feasibility of, and to submit to the Congress a proposal for, the construction of one or more monitored retrievable storage facilities for high level radioactive waste and spent nuclear fuel.'' The Act directs that the proposal includes site specific designs. Further, the proposal is to include, ''for the first such facility, at least three alternative sites and at least five alternative combinations of such proposed sites and facility designs hor-ellipsis'' as well as a recommendation of ''the combination among the alternatives that the Secretary deems preferable.'' An MRS Site Screening Task Force has been formed to help identify and evaluate potential MRS facility sites within a preferred region and with the application of a siting process and criteria developed by the DOE. The activities of the Task Force presented in this report, all site evaluations (sections 13 through 16) where the rationale for the site evaluations are presented, along with each evaluation and findings of the Task Force. This is Volume 3 of a three volume document. References are also included in this volume

  18. Monitored retrievable storage facility site screening and evaluation report

    International Nuclear Information System (INIS)

    1985-05-01

    The Nuclear Waste Policy Act of 1982 directs the Department of Energy to ''complete a detailed study of the need for and feasibility of, and to submit to the Congress a proposal for, the construction of one or more monitored retrievable storage facilities for high level radioactive waste and spent nuclear fuel.'' The Act directs that the proposal includes site specific designs. Further, the proposal is to include, ''for the first such facility, at least three alternative sites and at least five alternative combinations of such proposed sites and facility designs hor-ellipsis'' as well as a recommendation of ''the combination among the alternatives that the Secretary deems preferable.'' An MRS Site Screening Task Force has been formed to help identify and evaluate potential MRS facility sites within a preferred region and with the application of a siting process and criteria developed by the DOE. The activities of the Task Force presented in this report include: site evaluations (sections 10 through 12) where the rationale for the site evaluations are presented, along with each evaluation and findings of the Task Force. This in Volume 2 of a three volume document

  19. Monitored retrievable storage facility site screening and evaluation report

    Energy Technology Data Exchange (ETDEWEB)

    none,

    1985-05-01

    The Nuclear Waste Policy Act of 1982 directs the Department of Energy to complete a detailed study of the need for and feasibility of, and to submit to the Congress a proposal for, the construction of one or more monitored retrievable storage facilities for high level radioactive waste and spent nuclear fuel.'' The Act directs that the proposal includes site specific designs. Further, the proposal is to include, for the first such facility, at least three alternative sites and at least five alternative combinations of such proposed sites and facility designs{hor ellipsis}'' as well as a recommendation of the combination among the alternatives that the Secretary deems preferable.'' An MRS Site Screening Task Force has been formed to help identify and evaluate potential MRS facility sites within a preferred region and with the application of a siting process and criteria developed by the DOE. The activities of the Task Force presented in this report include: site evaluations (sections 10 through 12) where the rationale for the site evaluations are presented, along with each evaluation and findings of the Task Force. This in Volume 2 of a three volume document.

  20. Comprehensive characterization and hazard assessment of the DOE-Niagara Falls storage site

    International Nuclear Information System (INIS)

    Anderson, T.L.; Dettorre, J.F.; Jackson, D.R.; Ausmus, B.S.

    1981-06-01

    A comprehensive radioecological and nonradiological characterization and hazards assessment was conducted on DOE-Niagara Falls Storage Site. Pitchblende residues and other low-level nuclear waste have been stored on the site since 1944. The most highly radioactive residues were stored in four abandoned buildings, while other wastes were deposited in pits or piled on surface soils on the Site. Several ditches were constructed on the Site to facilitate drainage or excess precipitation. Results of the study will permit the US DOE to form an appropriate remedial action plan for the Site

  1. Fuel Assemblies Thermal Analysis in the New Spent Fuel Storage Facility at Inshass Site

    International Nuclear Information System (INIS)

    Khattab, M.; Mariy, Ahmed

    1999-01-01

    New Wet Storage Facility (NSF) is constructed at Inshass site to solve the problem of spent fuel storage capacity of ETRR-1 reactor . The Engineering Safety Heat Transfer Features t hat characterize the new facility are presented. Thermal analysis including different scenarios of pool heat load and safety limits are discussed . Cladding temperature limit during handling and storage process are specified for safe transfer of fuel

  2. Distributed Energy Resources On-Site Optimization for Commercial Buildings with Electric and Thermal Storage Technologies

    International Nuclear Information System (INIS)

    Lacommare, Kristina S H; Stadler, Michael; Aki, Hirohisa; Firestone, Ryan; Lai, Judy; Marnay, Chris; Siddiqui, Afzal

    2008-01-01

    The addition of storage technologies such as flow batteries, conventional batteries, and heat storage can improve the economic as well as environmental attractiveness of on-site generation (e.g., PV, fuel cells, reciprocating engines or microturbines operating with or without CHP) and contribute to enhanced demand response. In order to examine the impact of storage technologies on demand response and carbon emissions, a microgrid's distributed energy resources (DER) adoption problem is formulated as a mixed-integer linear program that has the minimization of annual energy costs as its objective function. By implementing this approach in the General Algebraic Modeling System (GAMS), the problem is solved for a given test year at representative customer sites, such as schools and nursing homes, to obtain not only the level of technology investment, but also the optimal hourly operating schedules. This paper focuses on analysis of storage technologies in DER optimization on a building level, with example applications for commercial buildings. Preliminary analysis indicates that storage technologies respond effectively to time-varying electricity prices, i.e., by charging batteries during periods of low electricity prices and discharging them during peak hours. The results also indicate that storage technologies significantly alter the residual load profile, which can contribute to lower carbon emissions depending on the test site, its load profile, and its adopted DER technologies

  3. Monitored retrievable storage facility site screening and evaluation report

    International Nuclear Information System (INIS)

    1985-05-01

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

  4. Monitored retrievable storage facility site screening and evaluation report

    Energy Technology Data Exchange (ETDEWEB)

    none,

    1985-05-01

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

  5. Conceptual design report for regional low-level waste interim storage site

    International Nuclear Information System (INIS)

    Bird, M.V.; Thompson, J.D.

    1981-08-01

    An interim storage site design concept was developed for receiving 100,000 ft 3 low-level waste per year, in the form of solidified wastes in 55-gallon drums with a dose rate of < 200 mrem per hour at contact

  6. Shaft sealing issue in CO2 storage sites

    Science.gov (United States)

    Dieudonné, A.-C.; Charlier, R.; Collin, F.

    2012-04-01

    Carbon capture and storage is an innovating approach to tackle climate changes through the reduction of greenhouse gas emissions. Deep saline aquifers, depleted oil and gas reservoirs and unmineable coal seams are among the most studied reservoirs. However other types of reservoir, such as abandonned coal mines, could also be used for the storage of carbon dioxide. In this case, the problem of shaft sealing appears to be particularly critical regarding to the economic, ecologic and health aspects of geological storage. The purpose of the work is to study shaft sealing in the framework of CO2 storage projects in abandoned coal mines. The problem of gas transfers around a sealing system is studied numerically using the finite elements code LAGAMINE, which has been developped for 30 years at the University of Liege. A coupled hydro-mechanical model of unsaturated geomaterials is used for the analyses. The response of the two-phase flow model is first studied through a simple synthetic problem consisting in the injection of gas in a concrete-made column. It stands out of this first modeling that the advection of the gas phase represents the main transfer mechanism of CO2 in highly unsaturated materials. Furthermore the setting of a bentonite barrier seal limits considerably the gas influx into the biosphere. A 2D axisymetric hydromechanical modeling of the Anderlues natural gas storage site is then performed. The geological and hydrogeological contexts of the site are used to define the problem, for the initial and boundary conditions, as well as the material properties. In order to reproduce stress and water saturation states in the shale before CO2 injection in the mine, different phases corresponding to the shaft sinking, the mining and the set up of the sealing system are simulated. The system efficiency is then evaluated by simulating the CO2 injection with the imposed pressure at the shaft wall. According to the modeling, the low water saturation of concrete and

  7. Site characterization of the highest-priority geologic formations for CO2 storage in Wyoming

    Energy Technology Data Exchange (ETDEWEB)

    Surdam, Ronald C. [Univ. of Wyoming, Laramie, WY (United States); Bentley, Ramsey [Univ. of Wyoming, Laramie, WY (United States); Campbell-Stone, Erin [Univ. of Wyoming, Laramie, WY (United States); Dahl, Shanna [Univ. of Wyoming, Laramie, WY (United States); Deiss, Allory [Univ. of Wyoming, Laramie, WY (United States); Ganshin, Yuri [Univ. of Wyoming, Laramie, WY (United States); Jiao, Zunsheng [Univ. of Wyoming, Laramie, WY (United States); Kaszuba, John [Univ. of Wyoming, Laramie, WY (United States); Mallick, Subhashis [Univ. of Wyoming, Laramie, WY (United States); McLaughlin, Fred [Univ. of Wyoming, Laramie, WY (United States); Myers, James [Univ. of Wyoming, Laramie, WY (United States); Quillinan, Scott [Univ. of Wyoming, Laramie, WY (United States)

    2013-12-07

    This study, funded by U.S. Department of Energy National Energy Technology Laboratory award DE-FE0002142 along with the state of Wyoming, uses outcrop and core observations, a diverse electric log suite, a VSP survey, in-bore testing (DST, injection tests, and fluid sampling), a variety of rock/fluid analyses, and a wide range of seismic attributes derived from a 3-D seismic survey to thoroughly characterize the highest-potential storage reservoirs and confining layers at the premier CO2 geological storage site in Wyoming. An accurate site characterization was essential to assessing the following critical aspects of the storage site: (1) more accurately estimate the CO2 reservoir storage capacity (Madison Limestone and Weber Sandstone at the Rock Springs Uplift (RSU)), (2) evaluate the distribution, long-term integrity, and permanence of the confining layers, (3) manage CO2 injection pressures by removing formation fluids (brine production/treatment), and (4) evaluate potential utilization of the stored CO2

  8. Monitored Retrievable Storage facility site screening and evaluation report

    Energy Technology Data Exchange (ETDEWEB)

    none,

    1985-05-01

    The Nuclear Waste Policy Act of 1982 directs the Department of Energy to complete a detailed study of the need for and feasibility of, and to submit to the Congress a proposal for, the construction of one or more monitored retrievable storage facilities for high level radioactive waste and spent nuclear fuel.'' The Act directs that the proposal includes site specific designs. Further, the proposal is to include, for the first such facility, at least three alternative sites and at least five alternative combinations of such proposed sites and facility designs {hor ellipsis}'' as well as a recommendation of the combination among the alternatives that the Secretary deems preferable.'' An MRS Site Screening Task Force has been formed to help identify and evaluate potential MRS facility sites within a preferred region and with the application of a siting process and criteria developed by the DOE. The activities of the Task Force presented in this report, all site evaluations (sections 13 through 16) where the rationale for the site evaluations are presented, along with each evaluation and findings of the Task Force. This is Volume 3 of a three volume document. References are also included in this volume.

  9. 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)

  10. Modeling the accumulation of As, Cd, Cu, Pb and Zn in grasses (Agrotis sp. and Poa sp. and stinging nettle (Urtica dioica on selected sites taking into account soil physico-chemical properties

    Directory of Open Access Journals (Sweden)

    Boshoff M.C.

    2014-07-01

    Full Text Available The effect of soil properties on the accumulation of metals in two vegetation types was evaluated at 10 sites with a wide variation in soil physicochemical properties pH, organic carbon, clay percentage , total soil metal concentration and exchangeable soil metal content. Accumulation modeling was conducted for grasses (Agrostis sp. and Poa sp. and stinging nettle (Urtica dioica.

  11. Modeling the accumulation of As, Cd, Cu, Pb and Zn in grasses (Agrotis sp. and Poa sp. and stinging nettle (Urtica dioica on selected sites taking into account soil physico-chemical properties

    Directory of Open Access Journals (Sweden)

    Boshoff M. C.

    2013-04-01

    Full Text Available The effect of soil properties on the accumulation of metals in two vegetation types was evaluated at 10 sites with a wide variation in soil physicochemical properties pH, organic carbon, clay percentage , total soil metal concentration and exchangeable soil metal content. Accumulation modeling was conducted for grasses (Agrostis sp. and Poa sp. and stinging nettle (Urtica dioica.

  12. Analysis of long-term impacts of TRU waste remaining at generator/storage sites for No Action Alternative 2

    International Nuclear Information System (INIS)

    Buck, J.W.; Bagaasen, L.M.; Bergeron, M.P.; Streile, G.P.

    1997-09-01

    This report is a supplement to the Waste Isolation Pilot Plant Disposal-Phase Final Supplemental Environmental Impact Statement (SEIS-II). Described herein are the underlying information, data, and assumptions used to estimate the long-term human-health impacts from exposure to radionuclides and hazardous chemicals in transuranic (TRU) waste remaining at major generator/storage sites after loss of institutional control under No Action Alternative 2. Under No Action Alternative 2, TRU wastes would not be emplaced at the Waste Isolation Pilot Plant (WIPP) but would remain at generator/storage sites in surface or near-surface storage. Waste generated at smaller sites would be consolidated at the major generator/storage sites. Current TRU waste management practices would continue, but newly generated waste would be treated to meet the WIPP waste acceptance criteria. For this alternative, institutional control was assumed to be lost 100 years after the end of the waste generation period, with exposure to radionuclides and hazardous chemicals in the TRU waste possible from direct intrusion and release to the surrounding environment. The potential human-health impacts from exposure to radionuclides and hazardous chemicals in TRU waste were analyzed for two different types of scenarios. Both analyses estimated site-specific, human-health impacts at seven major generator/storage sites: the Hanford Site (Hanford), Idaho National Engineering and Environmental Laboratory (INEEL), Lawrence Livermore National Laboratory (LLNL), Los Alamos National Laboratory (LANL), Oak Ridge National Laboratory (ORNL), Rocky Flats Environmental Technology Site (RFETS), and Savannah River Site (SRS). The analysis focused on these seven sites because 99 % of the estimated TRU waste volume and inventory would remain there under the assumptions of No Action Alternative 2

  13. Weldon Spring storage site environmental-monitoring report for 1979 and 1980

    International Nuclear Information System (INIS)

    Weidner, R.B.; Boback, M.W.

    1982-01-01

    The US Department of Energy (DOE) Weldon Spring Site consists of two separate radioactive waste storage properties: a 52-acre site which is a remnant of the Weldon Spring Feed Materials Plant; and a 9-acre abandoned rock quarry. The larger property has four pits which contain settled sludge from uranium and thorium processing operations. At the quarry, part of the excavation contains contaminated building rubble, scrap, and various residues. During 1979 and 1980 these storage locations were managed by NLO, Inc., contract operator of the DOE Feed Materials Production Center. Air and water samples were collected to provide information about the transfer of radionuclides in the offsite environment. Monitoring results show that uranium and radium concentrations in offsite surface and well water were within DOE Guide values for uncontrolled areas. At offsite locations, radon-222 concentrations in air were well within the Guide value

  14. Analysis of carbohydrate storage granules in the diazotrophic cyanobacterium Cyanothece sp. PCC 7822

    Energy Technology Data Exchange (ETDEWEB)

    Welkie, David G. [Purdue Univ., West Lafayette, IN (United States); Sherman, Debra M. [Purdue Univ., West Lafayette, IN (United States); Chrisler, William B. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Orr, Galya [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Sherman, Louis A. [Purdue Univ., West Lafayette, IN (United States)

    2013-10-19

    The unicellular diazotrophic cyanobacteria of the genus Cyanothece demonstrate oscillations in nitrogenase activity and H2 production when grown under 12h light-12h dark cycles. We established that Cyanothece sp. PCC 7822 allows for the construction of knock-out mutants and our objective was to improve the growth characteristics of this strain and to identify the nature of the intracellular storage granules. We report the physiological and morphological effects of reduction in nitrate and phosphate concentrations in BG-11 media on this strain. We developed a series of BG-11-derived growth media and monitored batch culture growth, nitrogenase activity and nitrogenase-mediated hydrogen production, culture synchronicity, and intracellular storage content. Reduction in NaNO3 and K2HPO4 concentrations from 17.6 and 0.23 mM to 4.41 and 0.06 mM, respectively, improved growth characteristics such as cell size and uniformity, and enhanced the rate of cell division. Cells grown in this low NP BG-11 were less complex, a parameter that related to the composition of the intracellular storage granules. Cells grown in low NP BG-11 had less polyphosphate, fewer polyhydroxybutyrate granules and many smaller granules became evident. Biochemical analysis and transmission electron microscopy using the histocytochemical PATO technique demonstrated that these small granules contained glycogen. The glycogen levels and the number of granules per cell correlated nicely with a 2.3 to 3.3-fold change from the minimum at L0 to the maximum at D0. The differences in granule morphology and enzymes between Cyanothece ATCC 51142 and Cyanothece PCC 7822 provide insights into the formation of large starch-like granules in some cyanobacteria.

  15. Surface decontamination in the old storage shed number 99 of the General Plan of IPEN/CNEN-SP, containing production equipment of natural uranium hexafluoride (UF6), aiming at its decommissioning

    International Nuclear Information System (INIS)

    Almeida, Claudio C. de; Cambises, Paulo B.S.; Paiva, Julio E. de; Paiva, Julio E. de; Silva, Teresina M.; Rodrigues, Demerval L.

    2013-01-01

    This paper presents the steps adopted in the operation planned for the decontamination of surfaces in the old storage shed number 99 the general layout of the Energy Research and Nuclear IPEN-CNEN/SP, Brazil, and contained various types of equipment originating from production hexafluoride natural uranium (UF6). This operation involved the planning, training of operators of the facility, analysis of workplaces and radiometric surveys for monitoring of external radiation and surface contamination. The training involved the procedures for decontamination of surfaces, segregation of materials and practical procedures for individual monitoring of contamination outside of the body. Were also established rules for the transport of radioactive materials in the internal and external facility and release of material and sites already decontaminated

  16. Using Geographic Information Systems to Determine Site Suitability for a Low-Level Radioactive Waste Storage Facility.

    Science.gov (United States)

    Wilson, Charles A; Matthews, Kennith; Pulsipher, Allan; Wang, Wei-Hsung

    2016-02-01

    Radioactive waste is an inevitable product of using radioactive material in education and research activities, medical applications, energy generation, and weapons production. Low-level radioactive waste (LLW) makes up a majority of the radioactive waste produced in the United States. In 2010, over two million cubic feet of LLW were shipped to disposal sites. Despite efforts from several states and compacts as well as from private industry, the options for proper disposal of LLW remain limited. New methods for quickly identifying potential storage locations could alleviate current challenges and eventually provide additional sites and allow for adequate regional disposal of LLW. Furthermore, these methods need to be designed so that they are easily communicated to the public. A Geographic Information Systems (GIS) based method was developed to determine suitability of potential LLW disposal (or storage) sites. Criteria and other parameters of suitability were based on the Code of Federal Regulation (CFR) requirements as well as supporting literature and reports. The resultant method was used to assess areas suitable for further evaluation as prospective disposal sites in Louisiana. Criteria were derived from the 10 minimum requirements in 10 CFR Part 61.50, the Nuclear Regulatory Commission's Regulatory Guide 0902, and studies at existing disposal sites. A suitability formula was developed permitting the use of weighting factors and normalization of all criteria. Data were compiled into GIS data sets and analyzed on a cell grid of approximately 14,000 cells (covering 181,300 square kilometers) using the suitability formula. Requirements were analyzed for each cell using multiple criteria/sub-criteria as well as surrogates for unavailable datasets. Additional criteria were also added when appropriate. The method designed in this project proved to be sufficient for initial screening tests in determining the most suitable areas for prospective disposal (or storage

  17. Planning, Coordinating, and Managing Off-Site Storage is an Area of Increasing, Professional Responsibility for Special Collections Departments

    Directory of Open Access Journals (Sweden)

    Melissa Goertzen

    2016-03-01

    Full Text Available Objective – To measure the use of off-site storage for special collections materials and to examine how this use impacts core special collections activities. Design – Survey questionnaire containing both structured and open ended questions. Follow-up interviews were also conducted. Setting – Association of Research Libraries (ARL member institutions in the United States of America. Subjects – 108 directors of special collections. Methods – Participants were recruited via email; contact information was compiled through professional directories, web searches, and referrals from professionals at ARL member libraries. The survey was sent out on October 31, 2013, and two reminder emails were distributed before it closed three weeks later. The survey was created and distributed using Qualtrics, a research software that supports online data collection and analysis. All results were analyzed using Microsoft Excel and Qualtrics. Main Results – The final response rate was 58% (63 out of 108. The majority (51 participants, or 81% reported use of off-site storage for library collections. Of this group, 91% (47 out of 51 house a variety of special collections in off-site storage. The criteria most frequently utilized to designate these materials to off-site storage are use (87%, size (66%, format (60%, and value (57%. The authors found that special collections directors are most likely to send materials to off-site storage facilities that are established and in use by other departments at their home institution; access to established workflows, especially those linked to transit and delivery, and space for expanding collections are benefits. In regard to core special collections activities, results indicated that public service was most impacted by off-site storage. The authors discussed challenges related to patron use and satisfaction. In regard to management and processing, directors faced challenges using the same level of staff to maintain

  18. Final storage high-level radioactive waste in Sweden - the way to the 2009 siting decision

    International Nuclear Information System (INIS)

    Schneider, Horst

    2010-01-01

    In Sweden, high-level radioactive waste producing heat, i.e. spent fuel, is to be emplaced for final storage on the site of Forsmark, which also holds three reactor units. The siting decision was taken in June 2009. A 100 percent private company, a merger of the commercial nuclear power plant operators as producers of the waste, is responsible for the siting decision as well as for waste storage. Major impulses were given to the back-end fuel cycle policy in the early 1970s. Sweden practically gave up the reprocessing option very soon, but kept on pursuing final storage in deep geologic formations. Between 1977, when legislation was adopted with conditions relating to repository storage, and 2009, when the decision in favour of the Forsmark site was taken, the path followed was not always a straight line. The boundary conditions, such as the organization of the repository and procedural and safety criteria established by the government, are interesting with regard to their influence on the siting decision, if any. For this reason, the approaches chosen and their connections with government criteria and with geological conditions in Sweden, including their impacts on the repository concept chosen, will be examined. After a summary review of developments in Sweden, filing of the licensing application and the accompanying documents up to commissioning of the repository, a short comparison will be made with the situation in Germany, especially the status reached of the Gorleben salt dome, highlighting and evaluating important criteria and parameters. Sweden as a model is important especially in these respects: A repository site was found by a private company in consensus with the local government within the framework of government criteria, and with ultimate responsibility resting with the government; the local government of a place not winning the siting decision is disappointed although it will have the conditioning plant and receive higher grants; it was not only

  19. CCS acceptability: social site characterization and advancing awareness at prospective storage sites in Poland and Scotland

    International Nuclear Information System (INIS)

    Brunsting, Suzanne; Mastop, Jessanne; Kaiser, Marta; Zimmer, Rene; Shackley, Simon; Mabon, Leslie; Howell, Rhys

    2015-01-01

    This paper summarizes the work on the social dimension conducted within the EU FP7 SiteChar project. The most important aim of the research was to advance public awareness and draw lessons for successful public engagement activities when developing a CO 2 storage permit application. To this end, social site characterization (e.g. representative surveys) and public participation activities (focus conference) were conducted at two prospective Carbon Capture and Storage (CCS) sites: an onshore site in Poland and an offshore site in Scotland. The research consisted of four steps over a time period of 1.5 year, from early 2011 to mid-2012. The first step consisted of four related qualitative and quantitative research activities to provide a social characterization of the areas: desk research, stakeholder interviews, media analyses, and a survey among representative samples of the local community. The aim was to identify: - stakeholders or interested parties; - factors that may drive their perceptions of and attitudes towards CCS. Results were used to as input for the second step, in which a new format for public engagement named 'focus conferences' was tested at both sites involving a small sample of the local community. The third step consisted of making available generic as well as site-specific information to the general and local public, by: - setting up a bilingual set of information pages on the project web site suitable for a lay audience; - organizing information meetings at both sites that were open to all who took interest. The fourth step consisted of a second survey among a new representative sample of the local community. The survey was largely identical to the survey in step 1 to enable the monitoring of changes in awareness, knowledge and opinions over time. Results provide insight in the way local CCS plans may be perceived by the local stakeholders, how this can be reliably assessed at early stage without raising unnecessary concerns, and how

  20. Maywood Interim Storage Site: Annual site environmental report, Maywood, New Jersey, Calendar year 1986: Formerly Utilized Sites Remedial Action Program

    Energy Technology Data Exchange (ETDEWEB)

    None

    1987-06-01

    During 1986, the environmental monitoring program was continued at the Maywood Interim Storage Site (MISS), a US Department of Energy (DOE) facility located in the Borough of Maywood and the Township of Rochelle Park, New Jersey. The MISS is presently used for the storage of low-level radioactively contaminated soils. The MISS is part of the Formerly Utilized Sites Remedial Action Program (FUSRAP). As part of the decontamination research and development project authorized by Congress under the 1984 Energy and Water Appropriations Act, remedial action and environmental monitoring programs are being conducted at this site and at vicinity properties by Bechtel National, Inc., Project Management Contractor for FUSRAP. The monitoring program at the MISS measures thoron and radon gas concentrations in air; external gamma radiation levels; and thorium, uranium, and radium concentrations in surface water, groundwater, and sediment. To verify that the site is in compliance with the DOE radiation protection standard (100 mrem/y) and to assess the potential effect on public health, the radiation dose was calculated for the maximally exposed individual. Based on the conservative scenario described in the report, the maximally exposed individual would receive an annual external exposure approximately equivalent to 1% of the DOE radiation protection standard of 100 mrem/y. This exposure is less than the exposure a person would receive during a round-trip flight from New York to Los Angeles (due to greater amounts of cosmic radiation at higher altitudes). The cumulative dose to the population within an 80-km (50-mi) radius of the MISS that would result from radioactive materials present at the site would be indistinguishable from the dose the same population would receive from naturally occurring radioactive sources. Results of the 1986 monitoring show that the MISS is in compliance with the DOE radiation protection standard. 16 refs., 8 figs., 15 tabs.

  1. Finding of no significant impact. Consolidation and interim storage of special nuclear material at Rocky Flats Environmental Technology Site

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-06-01

    The Department of Energy (DOE) has prepared an environmental assessment (EA), DOE/EA -- 1060, for the consolidation, processing, and interim storage of Category I and II special nuclear material (SNM) in Building 371 at the Rocky Flats Environmental Technology Site (hereinafter referred to as Rocky Flats or Site), Golden, Colorado. The scope of the EA included alternatives for interim storage including the no action alternative, the construction of a new facility for interim storage at Rocky Flats, and shipment to other DOE facilities for interim storage.

  2. Finding of no significant impact. Consolidation and interim storage of special nuclear material at Rocky Flats Environmental Technology Site

    International Nuclear Information System (INIS)

    1995-06-01

    The Department of Energy (DOE) has prepared an environmental assessment (EA), DOE/EA -- 1060, for the consolidation, processing, and interim storage of Category I and II special nuclear material (SNM) in Building 371 at the Rocky Flats Environmental Technology Site (hereinafter referred to as Rocky Flats or Site), Golden, Colorado. The scope of the EA included alternatives for interim storage including the no action alternative, the construction of a new facility for interim storage at Rocky Flats, and shipment to other DOE facilities for interim storage

  3. The prototype HIV-1 maturation inhibitor, bevirimat, binds to the CA-SP1 cleavage site in immature Gag particles

    Directory of Open Access Journals (Sweden)

    Nguyen Albert T

    2011-12-01

    Full Text Available Abstract Background Bevirimat, the prototype Human Immunodeficiency Virus type 1 (HIV-1 maturation inhibitor, is highly potent in cell culture and efficacious in HIV-1 infected patients. In contrast to inhibitors that target the active site of the viral protease, bevirimat specifically inhibits a single cleavage event, the final processing step for the Gag precursor where p25 (CA-SP1 is cleaved to p24 (CA and SP1. Results In this study, photoaffinity analogs of bevirimat and mass spectrometry were employed to map the binding site of bevirimat to Gag within immature virus-like particles. Bevirimat analogs were found to crosslink to sequences overlapping, or proximal to, the CA-SP1 cleavage site, consistent with previous biochemical data on the effect of bevirimat on Gag processing and with genetic data from resistance mutations, in a region predicted by NMR and mutational studies to have α-helical character. Unexpectedly, a second region of interaction was found within the Major Homology Region (MHR. Extensive prior genetic evidence suggests that the MHR is critical for virus assembly. Conclusions This is the first demonstration of a direct interaction between the maturation inhibitor, bevirimat, and its target, Gag. Information gained from this study sheds light on the mechanisms by which the virus develops resistance to this class of drug and may aid in the design of next-generation maturation inhibitors.

  4. Small constrained SP1-7 analogs bind to a unique site and promote anti-allodynic effects following systemic injection in mice.

    Science.gov (United States)

    Jonsson, A; Fransson, R; Haramaki, Y; Skogh, A; Brolin, E; Watanabe, H; Nordvall, G; Hallberg, M; Sandström, A; Nyberg, F

    2015-07-09

    Previous results have shown that the substance P (SP) N-terminal fragment SP1-7 may attenuate hyperalgesia and produce anti-allodynia in animals using various experimental models for neuropathic pain. The heptapeptide was found to induce its effects through binding to and activating specific sites apart from any known neurokinin or opioid receptor. Furthermore, we have applied a medicinal chemistry program to develop lead compounds mimicking the effect of SP1-7. The present study was designed to evaluate the pharmacological effect of these compounds using the mouse spared nerve injury (SNI) model of chronic neuropathic pain. Also, as no comprehensive screen with the aim to identify the SP1-7 target has yet been performed we screened our lead compound H-Phe-Phe-NH2 toward a panel of drug targets. The extensive target screen, including 111 targets, did not reveal any hit for the binding site among a number of known receptors or enzymes involved in pain modulation. Our animal studies confirmed that SP1-7, but also synthetic analogs thereof, possesses anti-allodynic effects in the mouse SNI model of neuropathic pain. One of the lead compounds, a constrained H-Phe-Phe-NH2 analog, was shown to exhibit a significant anti-allodynic effect. Copyright © 2015 IBRO. Published by Elsevier Ltd. All rights reserved.

  5. Site Specific Waste Management Instruction for the 116-F-4 soil storage unit

    International Nuclear Information System (INIS)

    Hopkins, G.G.

    1996-08-01

    This Site Specific Waste Management Instruction provides guidance for management of waste generated during the excavation and remediation of soil and debris from the 116-4 soil storage unit located at the Hanford Site in Richland, Washington. This document outlines the waste management practices that will be performed in the field to implement federal, state, and US Department of Energy requirements

  6. Technical factors in the site selection for a radioactive wastes storage of low and intermediate level

    International Nuclear Information System (INIS)

    Badillo A, V. E.; Ramirez S, J. R.; Palacios H, J. C.

    2009-10-01

    The storage on surface or near surface it is viable for wastes of low and intermediate level which contain radio nuclides of short half life that would decay at insignificant levels of radioactivity in some decades and also radio nuclides of long half life but in very low concentrations. The sites selection, for the construction of radioactive waste storages, that present an appropriate stability at long term, a foreseeable behavior to future and a capacity to fulfill other operational requirements, is one of the great tasks that confront the waste disposal agencies. In the selection of potential sites for the construction of a radioactive wastes storage of low and intermediate level, several basic judgments should be satisfied that concern to physiography, climatology, geologic, geo-hydrology, tectonic and seismic aspects; as well as factors like the population density, socioeconomic develops and existent infrastructure. the necessary technician-scientific investigations for the selection of a site for the construction of radioactive waste storages are presented in this work and they are compared with the pre-selection factors realized in specify areas in previous studies in different regions of the Mexican Republic. (Author)

  7. Testing in support of on-site storage of residues in the Pipe Overpack Container

    International Nuclear Information System (INIS)

    Ammerman, D.J.; Bobbe, J.G.; Arviso, M.

    1997-02-01

    The disposition of the large back-log of plutonium residues at the Rocky Flats Environmental Technology Site (Rocky Flats) will require interim storage and subsequent shipment to a waste repository. Current plans call for disposal at the Waste Isolation Pilot Plant (WIPP) and the transportation to WIPP in the TRUPACT-II. The transportation phase will require the residues to be packaged in a container that is more robust than a standard 55-gallon waste drum. Rocky Flats has designed the Pipe Overpack Container to meet this need. It is desirable to use this same waste packaging for interim on-site storage in non-hardened buildings. To meet the safety concerns for this storage the Pipe Overpack Container has been subjected to a series of tests at Sandia National Laboratories in Albuquerque, New Mexico. In addition to the tests required to qualify the Pipe Overpack Container as a waste container for shipment in the TRUPACT-II several tests were performed solely for the purpose of qualifying the container for interim storage. This report will describe these tests and the packages response to the tests. 12 figs., 3 tabs

  8. An economic analysis of a monitored retrievable storage site for Tennessee

    Energy Technology Data Exchange (ETDEWEB)

    Fox, W.F.; Mayo, J.W.; Hansen, L.T.; Quindry, K.E.

    1985-12-17

    The United States Department of Energy is charged with the task of identifying potential sites for a Monitored Retrievable Storage (MRS) Facility and reporting the results of its analysis to Congress by January 1986. DOE chose three finalist sites from 11 sites DOE analysts evaluated earlier. All three are in Tennessee, including two in Oak Ridge and one in Trousdale/Smith Counties. This paper is a summary of research undertaken on the economic effects of establishing the MRS facility in Tennessee. All three locations were considered in the analysis, but on some occasions attention is focused on the site preferred by DOE. The research was undertaken by the Center for Business and Economic Research (CBER), College of Business Administration, the University of Tennessee, Knoxville, under contract with the Tennessee Department of Economic and Community Development.

  9. Hazelwood Interim Storage Site environmental surveillance report for calendar year 1993

    International Nuclear Information System (INIS)

    1994-06-01

    This report summarizes the results of environmental surveillance activities conducted at the Hazelwood Interim Storage Site (HISS) during calendar year 1993. It includes an overview of site operations, the basis for monitoring for radioactive and non-radioactive parameters, summaries of environmental program at HISS, a summary of the results, and the calculated hypothetical radiation dose to the offsite population. Environmental surveillance activities were conducted in accordance with the site environmental monitoring plan, which describes the rationale and design criteria for the surveillance program, the frequency of sampling and analysis, specific sampling and analysis procedures, and quality assurance requirements. The US Department of Energy (DOE) began environmental monitoring of HISS in 1984, when the site was assigned to DOE by Congress through the energy and Water Development Appropriations Act and subsequent to DOE's Formerly Utilized Sites Remediation Action Program (FUSRAP). Contamination at HISS originated from uranium processing work conducted at Mallinckrodt Chemical Works at the St. Louis Downtown Site (SLDS) from 1942 through 1957

  10. Loads imposed on dual purpose casks in German on-site-storage facilities for long term intermediate storage of spent nuclear fuel

    Energy Technology Data Exchange (ETDEWEB)

    Wetzel, N.; Rabe, O. [TUeV NORD EnSys Hannover GmbH und Co. KG, Hanover (Germany)

    2004-07-01

    In accordance with recent changes of the atomic energy act and in order to secure reliable removal of spent fuel from the nuclear power plants' fuel storage ponds the German utilities filed license applications for a total of 12 onsite- storage facilities for spent fuel assemblies. By the end of 2003 the last of these storage facilities were licensed and are currently under construction. The first on-site-storage facility of that line became operational in late 2002. There are several design lines of storage facilities with different handling procedures or possible accident conditions. Short term interim storage facilities for a few casks are characterized by individual concrete hoods shielding the casks in horizontal position whereas long term intermediate storage facilities currently erected for large numbers of casks typically feature a condensed pattern of casks stored in upright position and massive structures of reinforced concrete. TUeV Hannover/Sachsen-Anhalt e. V. (now TUeV NORD EnSys Hannover GmbH and Co. KG) has been contracted as a body of independent experts for the assessment of all related safety requirements on behalf of the national licensing authority, the federal office for radiation protection (BfS).

  11. Loads imposed on dual purpose casks in German on-site-storage facilities for long term intermediate storage of spent nuclear fuel

    International Nuclear Information System (INIS)

    Wetzel, N.; Rabe, O.

    2004-01-01

    In accordance with recent changes of the atomic energy act and in order to secure reliable removal of spent fuel from the nuclear power plants' fuel storage ponds the German utilities filed license applications for a total of 12 onsite- storage facilities for spent fuel assemblies. By the end of 2003 the last of these storage facilities were licensed and are currently under construction. The first on-site-storage facility of that line became operational in late 2002. There are several design lines of storage facilities with different handling procedures or possible accident conditions. Short term interim storage facilities for a few casks are characterized by individual concrete hoods shielding the casks in horizontal position whereas long term intermediate storage facilities currently erected for large numbers of casks typically feature a condensed pattern of casks stored in upright position and massive structures of reinforced concrete. TUeV Hannover/Sachsen-Anhalt e. V. (now TUeV NORD EnSys Hannover GmbH and Co. KG) has been contracted as a body of independent experts for the assessment of all related safety requirements on behalf of the national licensing authority, the federal office for radiation protection (BfS)

  12. Hazelwood interim storage site: Annual site environmental report, Hazelwood, Missouri, Calendar Year 1988

    International Nuclear Information System (INIS)

    1989-04-01

    The monitoring program at Hazelwood Interim Storage Site (HISS) measures radon concentrations in air; external gamma radiation levels; and uranium, radium, and thorium, concentrations in surface water, groundwater and sediment. To verify that the site is in compliance with the DOE radiation protection standard (100 mrem/yr) and assess its potential effect or public health, the radiation dose was calculated for a hypothetical maximally exposed individual. Based on the scenario described in this report, this hypothetical individual at HISS would receive an annual external exposure approximately equivalent to 1 percent of the DOE radiation protection standard. This exposure is less than the exposure a person receives during a flight from New York to Los Angeles (because of the greater amounts of cosmic radiation at higher altitudes). The cumulative dose to the population within an 80-km (50-mi) radius of HISS that results from radioactive materials present at the site is indistinguishable from the dose that the same population receives from naturally occurring radioactive sources. The results of 1988 monitoring show that HISS is in compliance with the DOE radiation protection standard. 15 refs., 16 figs., 13 tabs

  13. The Cabril: The Spanish Storage Site for Low and medium Level Radioactive Wastes

    International Nuclear Information System (INIS)

    Zuloaga, P.

    1993-01-01

    The new installations at El Cabril are one of the most modern storage sites for low and medium level radioactive wastes worldwide. The site was conceived in such a way that it is possible its reutilization without any radiological restriction after its current surveillance period of 300 years. Additionally, the installations have enough of a capacity to store all the medium and low level wastes to be produced in Spain during the next 30 years plus all the already gathered ones at the three old installations. In order to achieve all the objectives a storage system, a control network and installations for sewage water treatment are available. An incinerator to burn biological and organic wastes from hospitals and a laboratory of wastes characterization complete the variety of installations

  14. General safety guidelines for looking for a low mass activity-long life waste storage site

    International Nuclear Information System (INIS)

    2008-01-01

    The objective of this document is to define general guidelines which must be followed during the stages of search for a site and stages of design of a storage facility for low activity-long life radioactive wastes, in order to ensure its safety after closure. After having specified the considered wastes, geological shapes, and situations, this document defines the fundamental objective and the associated criteria (protection against chemical risk, radioprotection). It presents the design aspects related to safety (safety principles and functions, waste packages, public works engineering, geological environment, storage concepts). The last part deals with the safety demonstration after site closure which includes the control of some components, the assessment of disturbances in the storage facility or due to its presence, the taking of uncertainty and sensitivity studies into account, the influence of natural events

  15. Feasibility studies for pump and treat technology at leaking underground storage tank sites in Michigan

    International Nuclear Information System (INIS)

    O'Brien, J.M.; Pekas, B.S.

    1993-01-01

    Releases from underground storage tanks have resulted in impacts to groundwater at thousands of sites across the US. Investigations of these sites were initiated on a national basis with the implementation of federal laws that became effective December 22, 1989 (40 CFR 280). Completion of these investigations has led to a wave of design and installation of pump and treat aquifer restoration systems where impacts to groundwater have been confirmed. The purpose of this paper is to provide managers with a demonstration of some of the techniques that can be used by the consulting industry in evaluating the feasibility of pump and treat systems. With knowledge of these tools, managers can better evaluate proposals for system design and their cost effectiveness. To evaluate the effectiveness of typical pump and treat systems for leaking underground storage tank (LUST) sites in Michigan, ten sites where remedial design had been completed were randomly chosen for review. From these ten, two sites were selected that represented the greatest contrast in the types of site conditions encountered. A release of gasoline at Site 1 resulted in contamination of groundwater and soil with benzene, toluene, ethylbenzene, and xylenes

  16. Site specific comparison of H2, CH4 and compressed air energy storage in porous formations

    Science.gov (United States)

    Tilmann Pfeiffer, Wolf; Wang, Bo; Bauer, Sebastian

    2016-04-01

    The supply of energy from renewable sources like wind or solar power is subject to fluctuations determined by the climatic and weather conditions, and shortage periods can be expected on the order of days to weeks. Energy storage is thus required if renewable energy dominates the total energy production and has to compensate the shortages. Porous formations in the subsurface could provide large storage capacities for various energy carriers, such as hydrogen (H2), synthetic methane (CH4) or compressed air (CAES). All three energy storage options have similar requirements regarding the storage site characteristics and consequently compete for suitable subsurface structures. The aim of this work is to compare the individual storage methods for an individual storage site regarding the storage capacity as well as the achievable delivery rates. This objective is pursued using numerical simulation of the individual storage operations. In a first step, a synthetic anticline with a radius of 4 km, a drop of 900 m and a formation thickness of 20 m is used to compare the individual storage methods. The storage operations are carried out using -depending on the energy carrier- 5 to 13 wells placed in the top of the structure. A homogeneous parameter distribution is assumed with permeability, porosity and residual water saturation being 500 mD, 0.35 and 0.2, respectively. N2 is used as a cushion gas in the H2 storage simulations. In case of compressed air energy storage, a high discharge rate of 400 kg/s equating to 28.8 mio. m³/d at surface conditions is required to produce 320 MW of power. Using 13 wells the storage is capable of supplying the specified gas flow rate for a period of 31 hours. Two cases using 5 and 9 wells were simulated for both the H2 and the CH4 storage operation. The target withdrawal rates of 1 mio. sm³/d are maintained for the whole extraction period of one week in all simulations. However, the power output differs with the 5 well scenario producing

  17. Sp1/Sp3 and DNA-methylation contribute to basal transcriptional activation of human podoplanin in MG63 versus Saos-2 osteoblastic cells

    Directory of Open Access Journals (Sweden)

    Puri Christina

    2007-03-01

    Full Text Available Abstract Background Podoplanin is a membrane mucin that, among a series of tissues, is expressed on late osteoblasts and osteocytes. Since recent findings have focussed on podoplanin's potential role as a tumour progression factor, we aimed at identifying regulatory elements conferring PDPN promoter activity. Here, we characterized the molecular mechanism controlling basal PDPN transcription in human osteoblast-like MG63 versus Saos-2 cells. Results We cloned and sequenced 2056 nucleotides from the 5'-flanking region of the PDPN gene and a computational search revealed that the TATA and CAAT box-lacking promoter possesses features of a growth-related gene, such as a GC-rich 5' region and the presence of multiple putative Sp1, AP-4 and NF-1 sites. Reporter gene assays demonstrated a functional promoter in MG63 cells exhibiting 30-fold more activity than in Saos-2 cells. In vitro DNase I footprinting revealed eight protected regions flanked by DNaseI hypersensitive sites within the region bp -728 to -39 present in MG63, but not in Saos-2 cells. Among these regions, mutation and supershift electrophoretic mobility shift assays (EMSA identified four Sp1/Sp3 binding sites and two binding sites for yet unknown transcription factors. Deletion studies demonstrated the functional importance of two Sp1/Sp3 sites for PDPN promoter activity. Overexpression of Sp1 and Sp3 independently increased the stimulatory effect of the promoter and podoplanin mRNA levels in MG63 and Saos-2 cells. In SL2 cells, Sp3 functioned as a repressor, while Sp1 and Sp3 acted positively synergistic. Weak PDPN promoter activity of Saos-2 cells correlated with low Sp1/Sp3 nuclear levels, which was confirmed by Sp1/Sp3 chromatin immunoprecipitations in vivo. Moreover, methylation-sensitive Southern blot analyses and bisulfite sequencing detected strong methylation of CpG sites upstream of bp -464 in MG63 cells, but hypomethylation of these sites in Saos-2 cells. Concomitantly

  18. Report on site-independent environmental impacts of radioactive waste storage and management

    International Nuclear Information System (INIS)

    1985-10-01

    The organisation responsible for radioactive wastes in the Netherlands is COVRA: Centrale Organisatie Voor Radioactief Afval. It deals especially with storage and management of these wastes. For that purpose, COVRA will build a waste managing and storage facility at a central site in the Netherlands. In this report, environmental impacts of these activities are studied, that are independent of the location. The report is readable and useful for a broad audience. In the main report, the general features are outlined starting from figures and tables on environmental effects. In a separate volume, detailed numerical data are presented. (G.J.P.)

  19. Magnox Swarf Storage Silo Liquor Effluent Management -Sellafield Site, Cumbria, UK - Legacy radioactive waste storage - 59271

    International Nuclear Information System (INIS)

    Le Clere, Stephen

    2012-01-01

    The Sellafield Magnox Swarf Storage Silo (MSSS) was constructed to provide an underwater storage facility for irradiated magnox cladding metal Swarf, as well as miscellaneous beta-gamma waste from several sources. Liquid effluent arisings from hazard reduction activities at this facility represent the toughest effluent treatment challenge within the company's Legacy Ponds and Silos portfolio. The key requirement for hazard reduction has generated many substantial challenges as the facility is readied for decommissioning. This has demanded the production of carefully thought out strategies for managing, and overcoming, the key difficulties to be encountered as hazard reduction progresses. The complexity associated with preparing for waste retrievals from the Magnox Swarf Storage Silo, has also generated the demand for a mix of creativity and perseverance to meet the challenges and make progress. Challenging the status quo and willingness to accept change is not easy and the road to overall hazard reduction for the high hazard MSSS facility will demand the skills and investment of individuals, teams, and entire facility work-forces. The first steps on this road have been taken with the successful introduction of liquor management operations, however much more is yet to be achieved. Clear communication, investing in stakeholder management, perseverance in the face of difficulty and a structured yet flexible programme delivery approach, will ensure the continued success of tackling the complex challenges of treating liquid effluent from a legacy fuel storage silo at the Sellafield Site. (authors)

  20. Siting-selection study for the Soyland Power Cooperative, Inc. , compressed-air energy-storage system (CAES)

    Energy Technology Data Exchange (ETDEWEB)

    1982-01-01

    A method used for siting a compressed air energy storage (CAES) system using geotechnical and environmental criteria is explained using the siting of a proposed 220 MW water-compensated CAES plant in Illinois as an example. Information is included on the identification and comparative ranking of 28 geotechnically and environmental sites in Illinois, the examination of fatal flaws, e.g., mitigation, intensive studies, costly studies, permit denials, at 7 sites; and the selection of 3 sites for further geological surveying. (LCL)

  1. SP-100 Test Site

    International Nuclear Information System (INIS)

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

    1988-01-01

    Preparatory activities are well under way at Hanford to convert the 309 Containment Building and its associated service wing to a 2.5 MWt nuclear test facility for the SP-100 Ground Engineering System (GES) test. Preliminary design is complete, encompassing facility modifications, a secondary heat transport system, a large vacuum system to enclose the high temperature reactor, a test assembly cell and handling system, control and data processing systems, and safety and auxiliary systems. The design makes extensive use of existing equipment to minimize technical risk and cost. Refurbishment of this equipment is 75% complete. The facility has been cleared of obstructing equipment from its earlier reactor test. Current activities are focusing on definitive design and preparation of the Preliminary Safety Analysis Report (PSAR) aimed at procurement and construction approvals and schedules to achieve reactor criticality by January 1992. 6 refs

  2. Silver Niobate Lead-Free Antiferroelectric Ceramics: Enhancing Energy Storage Density by B-Site Doping.

    Science.gov (United States)

    Zhao, Lei; Gao, Jing; Liu, Qing; Zhang, Shujun; Li, Jing-Feng

    2018-01-10

    Lead-free dielectric ceramics with high recoverable energy density are highly desired to sustainably meet the future energy demand. AgNbO 3 -based lead-free antiferroelectric ceramics with double ferroelectric hysteresis loops have been proved to be potential candidates for energy storage applications. Enhanced energy storage performance with recoverable energy density of 3.3 J/cm 3 and high thermal stability with minimal energy density variation (<10%) over a temperature range of 20-120 °C have been achieved in W-modified AgNbO 3 ceramics. It is revealed that the W 6+ cations substitute the B-site Nb 5+ and reduce the polarizability of B-site cations, leading to the enhanced antiferroelectricity, which is confirmed by the polarization hysteresis and dielectric tunability. It is believed that the polarizability of B-site cations plays a dominant role in stabilizing the antiferroelectricity in AgNbO 3 system, in addition to the tolerance factor, which opens up a new design approach to achieve stable antiferroelectric materials.

  3. The National Institute on Aging Genetics of Alzheimer’s Disease Data Storage Site (NIAGADS)

    Data.gov (United States)

    U.S. Department of Health & Human Services — The National Institute on Aging Genetics of Alzheimer's Disease Data Storage Site (NIAGADS) is a national genetics data repository facilitating access to genotypic...

  4. Identifying suitable piercement salt domes for nuclear waste storage sites

    International Nuclear Information System (INIS)

    Kehle, R.; e.

    1980-08-01

    Piercement salt domes of the northern interior salt basins of the Gulf of Mexico are being considered as permanent storage sites for both nuclear and chemically toxic wastes. The suitable domes are stable and inactive, having reached their final evolutionary configuration at least 30 million years ago. They are buried to depths far below the level to which erosion will penetrate during the prescribed storage period and are not subject to possible future reactivation. The salt cores of these domes are themselves impermeable, permitting neither the entry nor exit of ground water or other unwanted materials. In part, a stable dome may be recognized by its present geometric configuration, but conclusive proof depends on establishing its evolutionary state. The evolutionary state of a dome is obtained by reconstructing the growth history of the dome as revealed by the configuration of sedimentary strata in a large area (commonly 3,000 square miles or more) surrounding the dome. A high quality, multifold CDP reflection seismic profile across a candidate dome will provide much of the necessary information when integrated with available subsurface control. Additional seismic profiles may be required to confirm an apparent configuration of the surrounding strata and an interpreted evolutionary history. High frequency seismic data collected in the near vicinity of a dome are also needed as a supplement to the CDP data to permit accurate depiction of the configuration of shallow strata. Such data must be tied to shallow drill hole control to confirm the geologic age at which dome growth ceased. If it is determined that a dome reached a terminal configuration many millions of years ago, such a dome is incapable of reactivation and thus constitutes a stable storage site for nuclear wastes

  5. Corrective Action Investigation Plan for Corrective Action Unit 321: Area 22 Weather Station Fuel Storage, Nevada Test Site, Nevada; TOPICAL

    International Nuclear Information System (INIS)

    1999-01-01

    This Corrective Action Investigation Plan (CAIP) has been developed in accordance with the Federal Facility Agreement and Consent Order (FFACO) that was agreed to by the US Department of Energy, Nevada Operations Office (DOE/NV); the State of Nevada Division of Environmental Protection (NDEP); and the US Department of Defense (FFACO, 1996). The CAIP is a document that provides or references all of the specific information for investigation activities associated with Corrective Action Units (CAUs) or Corrective Action Sites (CASs). According to the FFACO (1996), CASs are sites potentially requiring corrective action(s) and may include solid waste management units or individual disposal or release sites. A CAU consists of one or more CASs grouped together based on geography, technical similarity, or agency responsibility for the purpose of determining corrective actions. This CAIP contains the environmental sample collection objectives and the criteria for conducting site investigation activities at the CAU 321 Area 22 Weather Station Fuel Storage, CAS 22-99-05 Fuel Storage Area. For purposes of this discussion, this site will be referred to as either CAU 321 or the Fuel Storage Area. The Fuel Storage Area is located in Area 22 of the Nevada Test Site (NTS). The NTS is approximately 105 kilometers (km) (65 miles[mi]) northwest of Las Vegas, Nevada (Figure 1-1) (DOE/NV, 1996a). The Fuel Storage Area (Figure 1-2) was used to store fuel and other petroleum products necessary for motorized operations at the historic Camp Desert Rock facility which was operational from 1951 to 1958 at the Nevada Test Site, Nevada. The site was dismantled after 1958 (DOE/NV, 1996a)

  6. Diaphite, a new type of surface with mixed sp{sup 2}-sp{sup 3} hybridization for adsorption and functionalization

    Energy Technology Data Exchange (ETDEWEB)

    Radosinski, Lukasz, E-mail: lukasz.radosinski@pwr.edu.pl [Wroclaw University of Science and Technology, Chemistry Department, Group of Bioprocess and Biomedical Engineering, Wybrzeze Wyspianskiego 27, 50-370 Wroclaw (Poland); Formalik, Filip [Wroclaw University of Science and Technology, Chemistry Department, Group of Bioprocess and Biomedical Engineering, Wybrzeze Wyspianskiego 27, 50-370 Wroclaw (Poland); Olejniczak, Adam [Department of Spectroscopy of Excited States, Institute of Low Temperature and Structure Research, Polish Academy of Sciences, Okolna 2, 50-422 Wroclaw (Poland); Radosz, Andrzej [Wroclaw University of Science and Technology, Faculty of Fundamental Problems of Technology, Department of Quantum Technologies, Wybrzeze Wyspianskiego 27, 50-370 Wroclaw (Poland)

    2017-05-15

    Highlights: • Recent discoveries show a possibility of photoinduced formation of a structure of mixed sp{sub 2}-sp{sub 3} hybridization out of graphite and graphene–diaphite. • Ab initio and molecular mechanics calculations indicate that the surface exhibits large enhancement of binding energy due to favorable sp{sub 3} like hybridization. • The binding energy varies upon configuration of occupied adsorption sites and the adsorption sites form a regular bed-like matrix. - Abstract: We theoretically study a new carbon phase with mixed sp{sup 2}-sp{sup 3} bond hybridization called diaphite. Using ab initio calculations and the adaptive intermolecular reactive bond order (AIREBO) potential approach, we show that the surface of this structure exhibits enhanced adsorption capabilities. Specifically, using hydrogen as a test adsorbate, we calculate that the chemical binding energy, depending on the configuration of hydrogen atoms, varies from 2.08 to 2.9 eV. Furthermore, the adsorption sites form a regular matrix; thus, we postulate that this new stable carbon phase may be a universal matrix for functionalization.

  7. Referenced-site environmental document for a Monitored Retrievable Storage facility: backup waste management option for handling 1800 MTU per year

    International Nuclear Information System (INIS)

    Silviera, D.J.; Aaberg, R.L.; Cushing, C.E.; Marshall, A.; Scott, M.J.; Sewart, G.H.; Strenge, D.L.

    1985-06-01

    This environmental document includes a discussion of the purpose of a monitored retrievable storage facility, a description of two facility design concepts (sealed storage cask and field drywell), a description of three reference sites (arid, warm-wet, and cold-wet), and a discussion and comparison of the impacts associated with each of the six site/concept combinations. This analysis is based on a 15,000-MTU storage capacity and a throughput rate of up to 1800 MTU per year

  8. Referenced-site environmental document for a Monitored Retrievable Storage facility: backup waste management option for handling 1800 MTU per year

    Energy Technology Data Exchange (ETDEWEB)

    Silviera, D.J.; Aaberg, R.L.; Cushing, C.E.; Marshall, A.; Scott, M.J.; Sewart, G.H.; Strenge, D.L.

    1985-06-01

    This environmental document includes a discussion of the purpose of a monitored retrievable storage facility, a description of two facility design concepts (sealed storage cask and field drywell), a description of three reference sites (arid, warm-wet, and cold-wet), and a discussion and comparison of the impacts associated with each of the six site/concept combinations. This analysis is based on a 15,000-MTU storage capacity and a throughput rate of up to 1800 MTU per year.

  9. Streamlined approach for environmental restoration closure report for Corrective Action Unit 464: Historical underground storage tank release sites, Nevada Test Site, Nevada

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-04-01

    This report addresses the site characterization of two historical underground storage tank petroleum hydrocarbon release sites identified by Corrective Action Site (CAS) Numbers 02-02-03 and 09-02-01. The sites are located at the Nevada Test Site in Areas 2 and 9 and are concrete bunker complexes (Bunker 2-300, and 9-300). Characterization was completed using drilling equipment to delineate the extent of petroleum hydrocarbons at release site 2-300-1 (CAS 02-02-03). Based on site observations, the low hydrocarbon concentrations detected, and the delineation of the vertical and lateral extent of subsurface hydrocarbons, an ``A through K`` evaluation was completed to support a request for an Administrative Closure of the site.

  10. Streamlined approach for environmental restoration closure report for Corrective Action Unit 464: Historical underground storage tank release sites, Nevada Test Site, Nevada

    International Nuclear Information System (INIS)

    1998-04-01

    This report addresses the site characterization of two historical underground storage tank petroleum hydrocarbon release sites identified by Corrective Action Site (CAS) Numbers 02-02-03 and 09-02-01. The sites are located at the Nevada Test Site in Areas 2 and 9 and are concrete bunker complexes (Bunker 2-300, and 9-300). Characterization was completed using drilling equipment to delineate the extent of petroleum hydrocarbons at release site 2-300-1 (CAS 02-02-03). Based on site observations, the low hydrocarbon concentrations detected, and the delineation of the vertical and lateral extent of subsurface hydrocarbons, an ''A through K'' evaluation was completed to support a request for an Administrative Closure of the site

  11. Closure Report for Corrective Action Unit 135: Areas 25 Underground Storage Tanks, Nevada Test Site, Nevada

    Energy Technology Data Exchange (ETDEWEB)

    D. H. Cox

    2001-06-01

    Corrective Action Unit (CAU) 135, Area 25 Underground Storage Tanks, was closed in accordance with the approved Corrective Action Plan (DOE/NV, 2000). CAU 135 consists of three Corrective Action Sites (CAS). Two of these CAS's were identified in the Corrective Action Investigation Data Quality Objective meeting as being improperly identified as underground storage tanks. CAS 25-02-03 identified as the Deluge Valve Pit was actually an underground electrical vault and CAS 25-02-10 identified as an Underground Storage Tank was actually a former above ground storage tank filled with demineralized water. Both of these CAS's are recommended for a no further action closure. CAS 25-02-01 the Underground Storage Tanks commonly referred to as the Engine Maintenance Assembly and Disassembly Waste Holdup Tanks and Vault was closed by decontaminating the vault structure and conducting a radiological verification survey to document compliance with the Nevada Test Site unrestricted use release criteria. The Area 25 Underground Storage Tanks, (CAS 25-02-01), referred to as the Engine Maintenance, Assembly, and Disassembly (E-MAD) Waste Holdup Tanks and Vault, were used to receive liquid waste from all of the radioactive and cell service area drains at the E-MAD Facility. Based on the results of the Corrective Action Investigation conducted in June 1999, discussed in ''The Corrective Action Investigation Plan for Corrective Action Unit 135: Area 25 Underground Storage Tanks, Nevada Test Site, Nevada'' (DOE/NV, 199a), one sample from the radiological survey of the concrete vault interior exceeded radionuclide preliminary action levels. The analytes from the sediment samples exceeded the preliminary action levels for polychlorinated biphenyls, Resource Conservation and Recovery Act metals, total petroleum hydrocarbons as diesel-range organics, and radionuclides. The CAU 135 closure activities consisted of scabbling radiological ''hot spots

  12. Risks and mitigation options for on-site storage of wastewater from shale gas and tight oil development

    International Nuclear Information System (INIS)

    Kuwayama, Yusuke; Roeshot, Skyler; Krupnick, Alan; Richardson, Nathan; Mares, Jan

    2017-01-01

    We provide a critical review of existing research and information regarding the sources of risk associated with on-site shale gas and tight oil wastewater storage in the United States, the gaps that exist in knowledge regarding these risks, policy and technology options for addressing the risks, and the relative merits of those options. Specifically, we (a) identify the potential risks to human and ecological health associated with on-site storage of shale gas and tight oil wastewater via a literature survey and analysis of data on wastewater spills and regulatory violations, (b) provide a detailed description of government regulations or industry actions that may mitigate these risks to human and ecological health, and (c) provide a critical review of this information to help generate progress toward concrete action to make shale gas and tight oil development more sustainable and more acceptable to a skeptical public, while keeping costs down. - Highlights: • We review current research/information on shale gas and tight oil wastewater storage. • Pit overflows, tank overfills, and liner malfunctions are common spill causes. • Tanks lead to smaller and less frequent spills than pits, but are not a magic bullet. • State regulations for on-site oil and gas wastewater storage are very heterogeneous.

  13. Corrosion surveillance program of aluminum spent fuel elements in wet storage sites

    International Nuclear Information System (INIS)

    Linardi, E; Haddad, R

    2012-01-01

    Due to different degradation issues observed in aluminum-clad spent fuel during long term storage in water, the IAEA implemented in 1996 a Coordinated Research Project (CRP) and a Regional Project for Latin America, on Corrosion of Research Reactor Aluminum Clad Spent Fuel in Water. Argentine has been among the participant countries of these projects, carrying out spent fuel corrosion surveillance activities in its storage facilities. As a result of the research a large database on corrosion of aluminum-clad fuel has been generated. It was determined that the main types of corrosion affecting the spent fuel are pitting and galvanic corrosion due to contact with stainless steel. It was concluded that the quality of the water is the critical factor to control in a spent fuel storage facility. Another phase of the program is being conducted currently, which began in 2011 with the immersion of test racks in the RA1 reactor pool, and in the Research Reactor Spent Fuel Storage Facility (FACIRI), located in Ezeiza Atomic Center. This paper presents the results of the chemical analysis of the water performed so far, and its relationship with the examination of the coupons extracted from the sites (author)

  14. Monitoring of injected CO2 at two commercial geologic storage sites with significant pressure depletion and/or re-pressurization histories: A case study

    Directory of Open Access Journals (Sweden)

    Dayanand Saini

    2017-03-01

    The monitoring technologies that have been used/deployed/tested at both the normally pressured West Hastings and the subnormally pressured Bell Creek storage sites appear to adequately address any of the potential “out of zone migration” of injected CO2 at these sites. It would be interesting to see if any of the collected monitoring data at the West Hastings and the Bell Creek storage sites could also be used in future to better understand the viability of initially subnormally pressured and subsequently depleted and re-pressurized oil fields as secure geologic CO2 storage sites with relatively large storage CO2 capacities compared to the depleted and re-pressurized oil fields that were initially discovered as normally pressured.

  15. Radionuclide migration at sites of temporary storage of SNF and RW in North-West Russia - Contribution to regulatory development

    International Nuclear Information System (INIS)

    Sneve, M.K.; Shandala, N.K.; Orlova, E.I.; Titov, A.V.; Kochetkov, O.A.; Smith, G.M.; Barraclough, I.M.

    2007-01-01

    Two technical bases of the Northern Fleet were created in the Russian northwest in the 1960s at Andreeva in the Kola Bay and Gremikha village on the coast of the Barents Sea. They maintained nuclear submarines, performing receipt and storage of radioactive waste and spent nuclear fuel. No further stored material was received after 1985. These technical bases have since been re-categorised as sites of temporary storage. It is necessary to note that, during the storage of RW and SNF, certain conditions arose which resulted in failure of the storage barrier system, resulting in release of radionuclides. Remediation activities at the site focus on reduction of major risks associated with most hazardous radioactive source terms. In addition, the long term management of the sites includes consideration of how to remediate contaminated areas, not only because they affect continuing work at the site, but also because this work will influence final radiological status of the sites. The optimum approach to remediation will be affected by how quickly radionuclides could move, both during the remediation works and, so far as any residual activity is concerned, after the works are completed. Present investigations reported here are directed to determination of sorption-desorption parameters of radionuclides in the studied areas, which will affect their underground migration, with the purpose of accounting for regional peculiarities in optimization process of the STSs remediation. The work is being carried out by the TSO State Research Centre - Institute of Biophysics, of Russian Federation, with assistance from western experts. The work forms part of a regulatory collaboration programme on-going between the Norwegian Radiation Protection Authority and the Federal Medical-Biological Agency which is designed to support the development of norms and standards to be applied in the remediation of these sites of temporary storage. (author)

  16. Comparing CO2 Storage and Advection Conditions at Night at Different Carboeuroflux Sites

    Science.gov (United States)

    Aubinet, M.; Berbigier, P.; Bernhofer, Ch.; et al.

    Anemometer and CO2 concentration data from temporary campaigns performed at six CARBOEUROFLUX forest sites were used to estimate the importance of non-turbulent fluxes in nighttime conditions. While storage was observed to be significant only during periods of both low turbulence and low advection, the advective fluxes strongly influence the nocturnal CO2 balance, with the exception of almost flat and highly homogeneous sites. On the basis of the main factors determining the onset of advective fluxes, the ‘advection velocity’, which takes net radiation and local topography into account, was introduced as a criterion to characterise the conditions of storage enrichment/depletion. Comparative analyses of the six sites showed several common features of the advective fluxes but also some substantial differences. In particular, all sites where advection occurs show the onset of a boundary layer characterised by a downslope flow, negative vertical velocities and negative vertical CO2 concentration gradients during nighttime. As a consequence, vertical advection was observed to be positive at all sites, which corresponds to a removal of CO2 from the ecosystem. The main differences between sites are the distance from the ridge, which influences the boundary-layer depth, and the sign of the mean horizontal CO2 concentration gradients, which is probably determined by the source/sink distribution. As a consequence, both positive and negative horizontal advective fluxes (corresponding respectively to CO2 removal from the ecosystem and to CO2 supply to the ecosystem) were observed. Conclusive results on the importance of non-turbulent components in the mass balance require, however, further experimental investigations at sites with different topographies, slopes, different land covers, which would allow a more comprehensive analysis of the processes underlying the occurrence of advective fluxes. The quantification of these processes would help to better quantify nocturnal

  17. Enhancement of the catalytic activity of ferulic acid decarboxylase from Enterobacter sp. Px6-4 through random and site-directed mutagenesis.

    Science.gov (United States)

    Lee, Hyunji; Park, Jiyoung; Jung, Chaewon; Han, Dongfei; Seo, Jiyoung; Ahn, Joong-Hoon; Chong, Youhoon; Hur, Hor-Gil

    2015-11-01

    The enzyme ferulic acid decarboxylase (FADase) from Enterobacter sp. Px6-4 catalyzes the decarboxylation reaction of lignin monomers and phenolic compounds such as p-coumaric acid, caffeic acid, and ferulic acid into their corresponding 4-vinyl derivatives, that is, 4-vinylphenol, 4-vinylcatechol, and 4-vinylguaiacol, respectively. Among various ferulic acid decarboxylase enzymes, we chose the FADase from Enterobacter sp. Px6-4, whose crystal structure is known, and produced mutants to enhance its catalytic activity by random and site-directed mutagenesis. After three rounds of sequential mutations, FADase(F95L/D112N/V151I) showed approximately 34-fold higher catalytic activity than wild-type for the production of 4-vinylguaiacol from ferulic acid. Docking analyses suggested that the increased activity of FADase(F95L/D112N/V151I) could be due to formation of compact active site compared with that of the wild-type FADase. Considering the amount of phenolic compounds such as lignin monomers in the biomass components, successfully bioengineered FADase(F95L/D112N/V151I) from Enterobacter sp. Px6-4 could provide an ecofriendly biocatalytic tool for producing diverse styrene derivatives from biomass.

  18. Methodology of site generation for evaluation of the behaviour of radioactive waste storage

    International Nuclear Information System (INIS)

    Ruiz Rivas, C.; Eguilior Diez, S.

    1997-01-01

    The present report summarizes the purpose of methodology for the site generation in the evaluation of high-level radioactive waste storage for long-term. This work is developed into the project Safety analysis long-term of high-level radioactive waste. This project is carried on for CIEMAT and ENRESA

  19. Verification of geomechanical integrity and prediction of long-term mineral trapping for the Ketzin CO2 storage pilot site

    Science.gov (United States)

    Kempka, Thomas; De Lucia, Marco; Kühn, Michael

    2014-05-01

    Static and dynamic numerical modelling generally accompany the entire CO2 storage site life cycle. Thereto, it is required to match the employed models with field observations on a regular basis in order to predict future site behaviour. We investigated the coupled processes at the Ketzin CO2 storage pilot site [1] using a model coupling concept focusing on the temporal relevance of processes involved (hydraulic, chemical and mechanical) at given time-scales (site operation, abandonment and long-term stabilization). For that purpose, long-term dynamic multi-phase flow simulations [2], [3] established the basis for all simulations discussed in the following. Hereby, pressure changes resulting in geomechanical effects are largest during site operation, whereas geochemical reactions are governed by slow kinetics resulting in a long-term stabilization. To account for mechanical integrity, which may be mainly affected during site operation, we incorporated a regional-scale coupled hydro-mechanical model. Our simulation results show maximum ground surface displacements of about 4 mm, whereas shear and tensile failure are not observed. Consequently, the CO2 storage operation at the Ketzin pilot site does not compromise reservoir, caprock and fault integrity. Chemical processes responsible for mineral trapping are expected to mainly occur during long-term stabilization at the Ketzin pilot site [4]. Hence, our previous assessment [3] was extended by integrating two long-term mineral trapping scenarios. Thereby, mineral trapping contributes to the trapping mechanisms with 11.7 % after 16,000 years of simulation in our conservative and with 30.9 % in our maximum reactivity scenarios. Dynamic flow simulations indicate that only 0.2 % of the CO2 injected (about 67,270 t CO2 in total) is in gaseous state, but structurally trapped after 16,000 years. Depending on the studied long-term scenario, CO2 dissolution is the dominating trapping mechanism with 68.9 % and 88

  20. Pemacuan Pertumbuhan Melon (Cucumis melo L. dengan Cendawan Mikoriza Arbuskula dan Bakteri Azospirillum sp.

    Directory of Open Access Journals (Sweden)

    Lady Diana Tetelepta

    2016-10-01

    Full Text Available ABSTRACTMelon (Cucumis melo L. is a high economic value horticultural crop that is cultivated in some regions of Indonesia under fertilization management. Application of inorganic fertilizer continuously can reduce soil microbial abundance. One of the soil microbial that promote plant growth is arbuscular mycorrhizal fungi (AMF and Azospirillum sp. The aim of this study was to analysed the effect of AMF and Azospirillum sp. in promoting growth and production of melon. The experiment was carried out in a greenhouse and was arranged in a completely randomized design with five replicates. Five treatments tested were: control, fertilized with NPK, inoculated with AMF, inoculated with Azospirillum sp., inoculated with AMF + Azospirillum sp. The results showed that the effect of AMF on root growth and shoot growth were similar to NPK fertilizer. Azospirillum sp. increased root growth. On the other side, the effect of Azospirillum sp. on shoot growth was similar to NPK fertilizer. However, AMF and Azospirillum sp. inoculation solely increased plant height, fruit weight, fruit diameter, flavor and length of fruit storage. Meanwhile, combination of AMF and Azospirillum sp. increased plant height, root growth, shoot growth, fruit weight, fruit diameter, flavor and length of fruit storage. This study revealed that application of AMF and Azospirillum sp. in melon cultivation was more effective and efficient than NPK fertilizer.Keywords: arbuscular mycorrhizal fungi, Azospirillum sp., Cucumis melo L.

  1. Colonie Interim Storage Site environmental surveillance report for calendar year 1993

    International Nuclear Information System (INIS)

    1994-06-01

    This report summarizes the results of environmental surveillance activities conducted at the Colonie Interim Storage Site (CISS) during calendar year 1993. It includes an overview of site operations, the basis for radiological and nonradiological monitoring, dose to the offsite population, and summaries of environmental programs at CISS. Environmental surveillance activities were conducted in accordance with the site environmental monitoring plan, which describes the rationale and design criteria for the surveillance program, the frequency of sampling and analysis, specific sampling and analysis procedures, and quality assurance requirements. Appendix A contains a discussion of the nature of radiation, the way it is measured, and common sources of it. The primary environmental guidelines and limits applicable to CISS are given in US Department of Energy (DOE) orders and mandated by six federal acts: the Clean Air Act; the Clean Water Act; the Resource Conservation and Recovery Act (RCRA); the Toxic Substances Control Act; the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA); and the National Environmental Policy Act (NEPA). DOE began environmental monitoring of CISS in 1984 when DOE was authorized by Congress through the Energy and Water Development Appropriations Act to conduct a decontamination research and development program at the site. The site was subsequently assigned to DOE's Formerly Utilized Sites Remedial Action Program (FUSRAP)

  2. Los Alamos National Laboratory Site Integrated Management plan, uranium 233 storage and disposition. Volume 1: Project scope and description

    International Nuclear Information System (INIS)

    Nielsen, J.B.; Erickson, R.

    1997-01-01

    This Site Integration Management plan provides the Los Alamos Response to the Defense Nuclear Facility Safety Board (DNFSB) Recommendation 97-1. This recommendation addresses the safe storage and management of the Departments uranium 233 ( 233 U) inventory. In the past, Los Alamos has used 233 U for a variety of different weapons related projects. The material was used at a variety of sites in varying quantities. Now, there is a limited need for this material and the emphasis has shifted from use to storage and disposition of the material. The Los Alamos program to address the DNFSB Recommendation 97-1 has two emphases. First, take corrective action to address near term deficiencies required to provide safe interim storage of 233 U. Second, provide a plan to address long term storage and disposition of excess inventory at Los Alamos

  3. Closure Report for Corrective Action Unit 166: Storage Yards and Contaminated Materials, Nevada Test Site, Nevada

    Energy Technology Data Exchange (ETDEWEB)

    NSTec Environmental Restoration

    2009-08-01

    Corrective Action Unit (CAU) 166 is identified in the Federal Facility Agreement and Consent Order (FFACO) as 'Storage Yards and Contaminated Materials' and consists of the following seven Corrective Action Sites (CASs), located in Areas 2, 3, 5, and 18 of the Nevada Test Site: CAS 02-42-01, Condo Release Storage Yd - North; CAS 02-42-02, Condo Release Storage Yd - South; CAS 02-99-10, D-38 Storage Area; CAS 03-42-01, Conditional Release Storage Yard; CAS 05-19-02, Contaminated Soil and Drum; CAS 18-01-01, Aboveground Storage Tank; and CAS 18-99-03, Wax Piles/Oil Stain. Closure activities were conducted from March to July 2009 according to the FF ACO (1996, as amended February 2008) and the Corrective Action Plan for CAU 166 (U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office, 2007b). The corrective action alternatives included No Further Action and Clean Closure. Closure activities are summarized. CAU 166, Storage Yards and Contaminated Materials, consists of seven CASs in Areas 2, 3, 5, and 18 of the NTS. The closure alternatives included No Further Action and Clean Closure. This CR provides a summary of completed closure activities, documentation of waste disposal, and confirmation that remediation goals were met. The following site closure activities were performed at CAU 166 as documented in this CR: (1) At CAS 02-99-10, D-38 Storage Area, approximately 40 gal of lead shot were removed and are currently pending treatment and disposal as MW, and approximately 50 small pieces of DU were removed and disposed as LLW. (2) At CAS 03-42-01, Conditional Release Storage Yard, approximately 7.5 yd{sup 3} of soil impacted with lead and Am-241 were removed and disposed as LLW. As a BMP, approximately 22 ft{sup 3} of asbestos tile were removed from a portable building and disposed as ALLW, approximately 55 gal of oil were drained from accumulators and are currently pending disposal as HW, the portable building was removed and

  4. Closure Report for Corrective Action Unit 166: Storage Yards and Contaminated Materials, Nevada Test Site, Nevada

    International Nuclear Information System (INIS)

    2009-01-01

    Corrective Action Unit (CAU) 166 is identified in the Federal Facility Agreement and Consent Order (FFACO) as 'Storage Yards and Contaminated Materials' and consists of the following seven Corrective Action Sites (CASs), located in Areas 2, 3, 5, and 18 of the Nevada Test Site: CAS 02-42-01, Condo Release Storage Yd - North; CAS 02-42-02, Condo Release Storage Yd - South; CAS 02-99-10, D-38 Storage Area; CAS 03-42-01, Conditional Release Storage Yard; CAS 05-19-02, Contaminated Soil and Drum; CAS 18-01-01, Aboveground Storage Tank; and CAS 18-99-03, Wax Piles/Oil Stain. Closure activities were conducted from March to July 2009 according to the FF ACO (1996, as amended February 2008) and the Corrective Action Plan for CAU 166 (U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office, 2007b). The corrective action alternatives included No Further Action and Clean Closure. Closure activities are summarized. CAU 166, Storage Yards and Contaminated Materials, consists of seven CASs in Areas 2, 3, 5, and 18 of the NTS. The closure alternatives included No Further Action and Clean Closure. This CR provides a summary of completed closure activities, documentation of waste disposal, and confirmation that remediation goals were met. The following site closure activities were performed at CAU 166 as documented in this CR: (1) At CAS 02-99-10, D-38 Storage Area, approximately 40 gal of lead shot were removed and are currently pending treatment and disposal as MW, and approximately 50 small pieces of DU were removed and disposed as LLW. (2) At CAS 03-42-01, Conditional Release Storage Yard, approximately 7.5 yd 3 of soil impacted with lead and Am-241 were removed and disposed as LLW. As a BMP, approximately 22 ft 3 of asbestos tile were removed from a portable building and disposed as ALLW, approximately 55 gal of oil were drained from accumulators and are currently pending disposal as HW, the portable building was removed and disposed as LLW, and

  5. Safety issues in construction of facilities for long-term storage of radioactive waste at vector site

    Energy Technology Data Exchange (ETDEWEB)

    Tokarevskyi, O.; Alekseeva, Z.; Kondratiev, S. [State Scientific and Technical Center for Nuclear and Radiation Safety, Kyiv (Ukraine); Rybalka, N. [State Nuclear Regulatory Inspectorate of Ukraine, Kyiv (Ukraine)

    2013-07-01

    In Ukraine, it is planned to create a number of near-surface facilities for disposal of short-lived RW and long-term (up to 100 years) storage of long-lived RW at the Vector site in the Chernobyl exclusion zone. The expected streams of long-lived RW are analyzed in the paper. According to the analysis of RW streams, in particular, issues are considered on development of RW acceptance criteria, admissible radiological impacts during preparation of RW for long-term storage, reliability of barriers (RW packages, modules and structures, etc.) during long-term storage of RW. (orig.)

  6. Environmental Assessment: Relocation and storage of TRIGA reg-sign reactor fuel, Hanford Site, Richland, Washington

    International Nuclear Information System (INIS)

    1995-08-01

    In order to allow the shutdown of the Hanford 308 Building in the 300 Area, it is proposed to relocate fuel assemblies (101 irradiated, three unirradiated) from the Mark I TRIGA Reactor storage pool. The irradiated fuel assemblies would be stored in casks in the Interim Storage Area in the Hanford 400 Area; the three unirradiated ones would be transferred to another TRIGA reactor. The relocation is not expected to change the offsite exposure from all Hanford Site 300 and 400 Area operations

  7. Safety and optimization aspects of radioactive waste long-term storage at the ''Vector'' site

    International Nuclear Information System (INIS)

    Tokarevs'kij, O.V.; Kondrat'jev, S.M.; Aleksjejeva, Z.M.; Ribalka, N.V.

    2015-01-01

    The paper analyzes links between the final disposal option and needs for long-term storage of radioactive waste taking into proposals on possible changes in radwaste classification as regards disposal. It considers the conceptual approach to design facilities for long-term storage of long-lived radioactive waste at the Vector site and approaches to apply requirements of regulatory documents, radiation safety principles and criteria for long-term storage of radwaste and safety assessment.

  8. Geological evaluation of spent fuel storage and low-intermediate level radwaste disposal in the site of NPP candidate

    International Nuclear Information System (INIS)

    Sucipta; Yatim, S.; Martono, H.; Pudyo, A.

    1997-01-01

    Based on the consideration of techno-economy and environmental safety, the radioactive waste treatment installation (RWI), interim storage of spen fuel (ISSF) and low-intermediate level disposal shall be sited in the surrounding of NPP area. The land suitability of NPP's site candidate at Muria Peninsula as spent fuel storage and low-intermediate level radwaste disposal need to be studied. Site selection was conducted by overlay method and scoring method, and based on safety criteria which include geological and environmental aspects. Land evaluation by overlay method has given result a potential site which have highest suitable land at surrounding of borehole L-15 about 17.5 hectares. Land evaluation by scoring method has given result two land suitability classes, i.e. moderate suitability class (includes 14 borehole) and high suitability class, include borehole L-2, L-14 and L-15 (author)

  9. Radioactive solid waste inventories at United States Department of Energy burial and storage sites

    International Nuclear Information System (INIS)

    Watanabe, T.

    1987-06-01

    Radioactive solid waste inventories are given for United States Department of Energy (DOE) burial and storage sites. These data are obtained from the Solid Waste Information Management System (SWIMS) and reflect the inventories as of the end of the calendar year 1986. 4 figs., 7 tabs

  10. Streamlined approach for environmental restoration closure report for Corrective Action Unit 452: Historical underground storage tank release sites, Nevada Test Site, Nevada

    International Nuclear Information System (INIS)

    1998-04-01

    This report addresses the site characterization of three historical underground storage tank (UST) petroleum hydrocarbon release sites identified as 25-3101-1, 25-3102-3, and 25-3152-1. The sites are located within the Nevada Test Site in Area 25 at Buildings 3101, 3102, and 3152. The characterization was completed to support administrative closure of the sites. Characterization was completed using drilling equipment to delineate the extent of hydrocarbon impact. Clean closure had been previously attempted at each of these sites using backhoe equipment without success due to adjacent structures, buried utilities, or depth restrictions associated with each site. Although the depth and extent of hydrocarbon impact was determined to be too extensive for clean closure, it was verified through drilling that the sites should be closed through an administrative closure. The Nevada Administrative Code ''A Through K'' evaluation completed for each site supports that there is no significant risk to human health or the environment from the impacted soils remaining at each site

  11. Sp1 and Sp3 Are the Transcription Activators of Human ek1 Promoter in TSA-Treated Human Colon Carcinoma Cells.

    Science.gov (United States)

    Kuan, Chee Sian; See Too, Wei Cun; Few, Ling Ling

    2016-01-01

    Ethanolamine kinase (EK) catalyzes the phosphorylation of ethanolamine, the first step in the CDP-ethanolamine pathway for the biosynthesis of phosphatidylethanolamine (PE). Human EK exists as EK1, EK2α and EK2β isoforms, encoded by two separate genes, named ek1 and ek2. EK activity is stimulated by carcinogens and oncogenes, suggesting the involvement of EK in carcinogenesis. Currently, little is known about EK transcriptional regulation by endogenous or exogenous signals, and the ek gene promoter has never been studied. In this report, we mapped the important regulatory regions in the human ek1 promoter. 5' deletion analysis and site-directed mutagenesis identified a Sp site at position (-40/-31) that was essential for the basal transcription of this gene. Treatment of HCT116 cells with trichostatin A (TSA), a histone deacetylase inhibitor, significantly upregulated the ek1 promoter activity through the Sp(-40/-31) site and increased the endogenous expression of ek1. Chromatin immunoprecipitation assay revealed that TSA increased the binding of Sp1, Sp3 and RNA polymerase II to the ek1 promoter in HCT116 cells. The effect of TSA on ek1 promoter activity was cell-line specific as TSA treatment did not affect ek1 promoter activity in HepG2 cells. In conclusion, we showed that Sp1 and Sp3 are not only essential for the basal transcription of the ek1 gene, their accessibility to the target site on the ek1 promoter is regulated by histone protein modification in a cell line dependent manner.

  12. Niagara Falls Storage Site, Annual site environmental report, Lewiston, New York, Calendar year 1986: Surplus Facilities Management Program (SFMP)

    International Nuclear Information System (INIS)

    1987-06-01

    During 1986, the environmental monitoring program was continued at the Niagara Falls Storage Site (NFSS), a US Department of Energy (DOE) surplus facility located in Niagara County, New York, presently used for the interim storage of radioactive residues and contaminated soils and rubble. The monitoring program is being conducted by Bechtel National, Inc. The monitoring program at the NFSS measures radon gas concentrations in air; external gamma radiation levels; and uranium and radium concentrations in surface water, groundwater, and sediment. To verify that the site is in compliance with the DOE radiation protection standard and to assess its potential effect on public health, the radiation dose was calculated for the maximally exposed individual. Based on the conservative scenario described in the report, this individual would receive an annual external exposure approximately equivalent to 6% of the DOE radiation protection standard of 100 mrem/yr. By comparison, the incremental dose received from living in a brick house versus a wooden house is 10 mrem/yr above background. The cumulative dose to the population within an 80-km (50-mi) radius of the NFSS that would result from radioactive materials present at the site would be indistinguishable from the dose that the same population would receive from naturally occurring radioactive sources. Results of the 1986 monitoring show that the NFSS is in compliance with the DOE radiation protection standard. 14 refs., 11 figs., 14 tabs

  13. Niagara Falls Storage Site, Annual site environmental report, Lewiston, New York, Calendar year 1986: Surplus Facilities Management Program (SFMP)

    Energy Technology Data Exchange (ETDEWEB)

    1987-06-01

    During 1986, the environmental monitoring program was continued at the Niagara Falls Storage Site (NFSS), a US Department of Energy (DOE) surplus facility located in Niagara County, New York, presently used for the interim storage of radioactive residues and contaminated soils and rubble. The monitoring program is being conducted by Bechtel National, Inc. The monitoring program at the NFSS measures radon gas concentrations in air; external gamma radiation levels; and uranium and radium concentrations in surface water, groundwater, and sediment. To verify that the site is in compliance with the DOE radiation protection standard and to assess its potential effect on public health, the radiation dose was calculated for the maximally exposed individual. Based on the conservative scenario described in the report, this individual would receive an annual external exposure approximately equivalent to 6% of the DOE radiation protection standard of 100 mrem/yr. By comparison, the incremental dose received from living in a brick house versus a wooden house is 10 mrem/yr above background. The cumulative dose to the population within an 80-km (50-mi) radius of the NFSS that would result from radioactive materials present at the site would be indistinguishable from the dose that the same population would receive from naturally occurring radioactive sources. Results of the 1986 monitoring show that the NFSS is in compliance with the DOE radiation protection standard. 14 refs., 11 figs., 14 tabs.

  14. Colonie Interim Storage Site: Annual site environmental report, Colonie, New York, Calendar year 1986: Formerly Utilized Sites Remedial Action Program (FUSRAP)

    International Nuclear Information System (INIS)

    1987-06-01

    During 1986, the environmental monitoring program continued at the Colonie Interim Storage Site (CISS), a US Department of Energy (DOE) facility located in Colonie, New York. The CISS is part of the Formerly Utilized Sites Remedial Action Program (FUSRAP), a DOE program to decontaminate or otherwise control sites where residual radioactive materials remain from the early years of the nation's atomic energy program or from commercial operations causing conditions that Congress has mandated DOE to remedy. As part of the decontamination research and development project authorized by Congress under the 1984 Energy and Water Appropriations Act, remedial action is being conducted at the site and at vicinity properties by Bechtel National Inc. (BNI), Project Management Contractor for FUSRAP. The environmental monitoring program is also carried out by BNI. The monitoring program at the CISS measures external gamma radiation levels as well as uranium and radium-226 concentrations in surface water, groundwater, and sediment. To verify that the site is in compliance with the DOE radiation protection standard and to assess the potential effect of the site on public health, the radiation dose was calculated for the maximally exposed individual. Based on the conservative scenario described in the report, the maximally exposed individual would receive an annual external exposure approximately equivalent to 5% of the DOE radiation protection standard of 100 mrem/y. Results of 1986 monitoring show that the CISS is in compliance with the DOE radiation protection standard. 14 refs., 9 figs., 9 tabs

  15. Storage of radioactive wastes in geological formations. Technical criteria for site selection. Report by the work-group chaired by Professor Goguel

    International Nuclear Information System (INIS)

    Goguel, Jean; Candes, Pierre; Izabel, Cecile; Autran, Albert; Barthoux, Alain; Baudin, Guy; Devillers, Christian; Habib, Pierre; Lafuma, Jacques; Lefevre, Jean; Peaudecerf, Pierre; Pradel, Jacques; Salle, Claude; Treuil, Michel; Lebrun, Patrick; Tissier, Marie-Solange

    1985-06-01

    This document is the result of a prospective mission on the long term storage of radioactive wastes containing long-period emitters (wastes of B and C categories), and notably on a definitive storage in deep continental geological formations. After a presentation of hypotheses (brief description of the storage concept, main safety principles, objectives in terms of radiological safety, safety options, time-related considerations), the authors addressed the following issues: safety before closing during the exploitation period, and safety after closure (after backfilling and sealing of all underground cavities). For the first issue, they discuss the impacts of works on safety and thermal effects during exploitation. For the second issue, they discuss the site natural hydro-geological context, the disturbances brought by the storage (access of water to the storage, and return of water into the biosphere), and the influence of external factors (geological phenomena, human intrusion). Then, the authors make recommendations regarding reconnaissance programs and studies for the selection and qualification of a site. They finally propose technical criteria and main recommendations for site selection. Appendices propose a list of hearings, a presentation of the storage concept, a report on the impact of works, a report on the presence of mineralisation in granite massifs, reports on radiological consequences of intrusions in salt formations and in granite massif containing storage of radioactive wastes or vitrified wastes, a report on the characterization of unsteady parts of the French continental construction, a presentation of the evolution of climate and icings, and a study of seismic movements in the case of deep storages

  16. Surface-downhole and crosshole geoelectrics for monitoring of brine injection at the Ketzin CO2 storage site

    Science.gov (United States)

    Rippe, Dennis; Bergmann, Peter; Labitzke, Tim; Wagner, Florian; Schmidt-Hattenberger, Cornelia

    2016-04-01

    The Ketzin pilot site in Germany is the longest operating on-shore CO2 storage site in Europe. From June 2008 till August 2013, a total of ˜67,000 tonnes of CO2 were safely stored in a saline aquifer at depths of 630 m to 650 m. The storage site has now entered the abandonment phase, and continuation of the multi-disciplinary monitoring as part of the national project "CO2 post-injection monitoring and post-closure phase at the Ketzin pilot site" (COMPLETE) provides the unique chance to participate in the conclusion of the complete life cycle of a CO2 storage site. As part of the continuous evaluation of the functionality and integrity of the CO2 storage in Ketzin, from October 12, 2015 till January 6, 2015 a total of ˜2,900 tonnes of brine were successfully injected into the CO2 reservoir, hereby simulating in time-lapse the natural backflow of brine and the associated displacement of CO2. The main objectives of this brine injection experiment include investigation of how much of the CO2 in the pore space can be displaced by brine and if this displacement of CO2 during the brine injection differs from the displacement of formation fluid during the initial CO2 injection. Geophysical monitoring of the brine injection included continuous geoelectric measurements accompanied by monitoring of pressure and temperature conditions in the injection well and two adjacent observation wells. During the previous CO2 injection, the geoelectrical monitoring concept at the Ketzin pilot site consisted of permanent crosshole measurements and non-permanent large-scale surveys (Kiessling et al., 2010). Time-lapse geoelectrical tomographies derived from the weekly crosshole data at near-wellbore scale complemented by six surface-downhole surveys at a scale of 1.5 km showed a noticeable resistivity signature within the target storage zone, which was attributed to the CO2 plume (Schmidt-Hattenberger et al., 2011) and interpreted in terms of relative CO2 and brine saturations (Bergmann

  17. Surface decontamination in the old storage shed number 99 of the General Plan of IPEN/CNEN-SP, containing production equipment of natural uranium hexafluoride (UF{sub 6}), aiming at its decommissioning; Descontaminacao de superficies no antigo galpao de estocagem numero 99 da planta geral do IPEN/CNEN-SP, contendo equipamentos da producao de hexafluoreto de uranio natural, (UF{sub 6}), visando seu descomissionamento

    Energy Technology Data Exchange (ETDEWEB)

    Almeida, Claudio C. de; Cambises, Paulo B.S.; Paiva, Julio E. de; Paiva, Julio E. de; Silva, Teresina M.; Rodrigues, Demerval L., E-mail: calmeida@ipen.br, E-mail: cambises@ipen.br [Instituto de Pesquisas Energeticas e Nucleares (IPEN), Sao Paulo, SP (Brazil)

    2013-11-01

    This paper presents the steps adopted in the operation planned for the decontamination of surfaces in the old storage shed number 99 the general layout of the Energy Research and Nuclear IPEN-CNEN/SP, Brazil, and contained various types of equipment originating from production hexafluoride natural uranium (UF6). This operation involved the planning, training of operators of the facility, analysis of workplaces and radiometric surveys for monitoring of external radiation and surface contamination. The training involved the procedures for decontamination of surfaces, segregation of materials and practical procedures for individual monitoring of contamination outside of the body. Were also established rules for the transport of radioactive materials in the internal and external facility and release of material and sites already decontaminated.

  18. Priority and construction sites of water storage in a watershed in response to climate change

    Science.gov (United States)

    Lin, Cheng-Yu; Zhang, Wen-Yan; Lin, Chao-Yuan

    2014-05-01

    Taiwan is located at the Eastern Asia Monsoon climate zone. Typhoons and/or convectional rains occur frequently and result in high intensity storms in the summer season. Once the detention facilities are shortage or soil infiltration rate become worse in a watershed due to land use, surface runoff is easily to concentrate and threaten the protected areas. Therefore, it is very important to examine the functionality of water storage for a watershed. The purpose of this study is to solve the issue of flooding in the Puzi Creek. A case study of Yizen Bridge Watershed, in which the SCS curve number was used as an index to extract the spatial distribution of the strength of water storage, and the value of watershed mean CN along the main channel was calculated using area-weighting method. Therefore, the hotspot management sites were then derived and the priority method was applied to screen the depression sites for the reference of management authorities in detention ponds placement. The results show that the areas of subzone A with the characteristics of bad condition in topography and soil, which results in poor infiltration. However, the areas are mostly covered with forest and are difficult to create the artificial water storage facilities. Detention dams are strongly recommended at the site of depression in the river channel to decrease discharge velocity and reduce impact from flood disaster. The areas of subzone B are mainly located at the agriculture slope land. The topographic depressions in the farmland are the suitable places to construct the farm ponds for the use of flood detention and sediment deposition in the rainy seasons and irrigation in the dry seasons. Areas of subzone C are mainly occupied the gentle slope land with a better ability in water storage due to low CN value. Farm ponds constructed in the riparian to bypass the nearby river channel can create multifunctional wetland to effectively decrease the peak discharge in the downstream during

  19. Corrective Action Investigation Plan for Corrective Action Unit 214: Bunkers and Storage Areas Nevada Test Site, Nevada

    International Nuclear Information System (INIS)

    2003-01-01

    This Corrective Action Investigation Plan contains the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office's approach to collect the data necessary to evaluate corrective action alternatives appropriate for the closure of Corrective Action Unit (CAU) 214 under the Federal Facility Agreement and Consent Order. Located in Areas 5, 11, and 25 of the Nevada Test Site, CAU 214 consists of nine Corrective Action Sites (CASs): 05-99-01, Fallout Shelters; 11-22-03, Drum; 25-99-12, Fly Ash Storage; 25-23-01, Contaminated Materials; 25-23-19, Radioactive Material Storage; 25-99-18, Storage Area; 25-34-03, Motor Dr/Gr Assembly (Bunker); 25-34-04, Motor Dr/Gr Assembly (Bunker); and 25-34-05, Motor Dr/Gr Assembly (Bunker). These sites are being investigated because existing information on the nature and extent of potential contamination is insufficient to evaluate and recommend corrective action alternatives (CAAs). The suspected contaminants and critical analyte s for CAU 214 include oil (total petroleum hydrocarbons-diesel-range organics [TPH-DRO], polychlorinated biphenyls [PCBs]), pesticides (chlordane, heptachlor, 4,4-DDT), barium, cadmium, chronium, lubricants (TPH-DRO, TPH-gasoline-range organics [GRO]), and fly ash (arsenic). The land-use zones where CAU 214 CASs are located dictate that future land uses will be limited to nonresidential (i.e., industrial) activities. The results of this field investigation will support a defensible evaluation of viable corrective action alternatives that will be presented in the corrective action decision document

  20. Bacterial communities in an ultrapure water containing storage tank of a power plant.

    Science.gov (United States)

    Bohus, Veronika; Kéki, Zsuzsa; Márialigeti, Károly; Baranyi, Krisztián; Patek, Gábor; Schunk, János; Tóth, Erika M

    2011-12-01

    Ultrapure waters (UPWs) containing low levels of organic and inorganic compounds provide extreme environment. On contrary to that microbes occur in such waters and form biofilms on surfaces, thus may induce corrosion processes in many industrial applications. In our study, refined saltless water (UPW) produced for the boiler of a Hungarian power plant was examined before and after storage (sampling the inlet [TKE] and outlet [TKU] waters of a storage tank) with cultivation and culture independent methods. Our results showed increased CFU and direct cell counts after the storage. Cultivation results showed the dominance of aerobic, chemoorganotrophic α-Proteobacteria in both samples. In case of TKU sample, a more complex bacterial community structure could be detected. The applied molecular method (T-RFLP) indicated the presence of a complex microbial community structure with changes in the taxon composition: while in the inlet water sample (TKE) α-Proteobacteria (Sphingomonas sp., Novosphingobium hassiacum) dominated, in the outlet water sample (TKU) the bacterial community shifted towards the dominance of α-Proteobacteria (Rhodoferax sp., Polynucleobacter sp., Sterolibacter sp.), CFB (Bacteroidetes, formerly Cytophaga-Flavobacterium-Bacteroides group) and Firmicutes. This shift to the direction of fermentative communities suggests that storage could help the development of communities with an increased tendency toward corrosion.

  1. Wayne Interim Storage Site: Annual environmental report for calendar year 1990, Wayne, New Jersey

    International Nuclear Information System (INIS)

    1991-09-01

    Environmental monitoring of the US Department of Energy's (DOE) Wayne Interim Storage Site (WISS) (a National Priorities List site) and surrounding area began in 1984. WISS is part of the Formerly Utilized Sites Remedial Action Program (FUSRAP), a DOE program to decontaminate or otherwise control sites where residual radioactive materials remain from the early years of the nation's atomic energy program or from commercial operations causing conditions that Congress has authorized DOE to remedy. The environmental monitoring program at WISS includes sampling networks for radon and thoron concentrations in air; external gamma radiation exposure; and radium-226, thorium-232, and total uranium concentrations in surface water, sediment, and groundwater. Sediment samples were also analyzed for thorium-230, and several nonradiological parameters were measured in groundwater. 16 refs., 12 figs., 23 tabs

  2. GHGT-10 : Assessing the integrity of fault- and top seals at CO2 storage sites

    NARCIS (Netherlands)

    Orlic, B.; Heege J.H. ter; Wassing, B.

    2011-01-01

    Induced stress changes due to CO2 injection into geological reservoirs can mechanically damage bounding fault- and top seals creating preferential pathways for CO2 migration from the containment or trigger existing faults causing seismic activity at storage sites. In this paper we present

  3. Corrective Action Decision Document for Corrective Action Unit 166: Storage Yards and Contaminated Materials, Nevada Test Site, Nevada with Errata Sheet

    Energy Technology Data Exchange (ETDEWEB)

    Grant Evenson

    2007-03-01

    This Corrective Action Decision Document (CADD) has been prepared for Corrective Action Unit (CAU) 166, Storage Yards and Contaminated Materials, in accordance with the Federal Facility Agreement and Consent Order (1996). The corrective action sites (CASs) are located in Areas 2, 3, 5, and 18 of the Nevada Test Site, Nevada. Corrective Action Unit 166 is comprised of the following CASs: • 02-42-01, Cond. Release Storage Yd - North • 02-42-02, Cond. Release Storage Yd - South • 02-99-10, D-38 Storage Area • 03-42-01, Conditional Release Storage Yard • 05-19-02, Contaminated Soil and Drum • 18-01-01, Aboveground Storage Tank • 18-99-03, Wax Piles/Oil Stain The purpose of this CADD is to identify and provide the rationale for the recommendation of a corrective action alternative (CAA) for the seven CASs within CAU 166. Corrective action investigation (CAI) activities were performed from July 31, 2006, through February 28, 2007, as set forth in the CAU 166 Corrective Action Investigation Plan (NNSA/NSO, 2006).

  4. Microalgal biomass production and on-site bioremediation of carbon dioxide, nitrogen oxide and sulfur dioxide from flue gas using Chlorella sp. cultures.

    Science.gov (United States)

    Chiu, Sheng-Yi; Kao, Chien-Ya; Huang, Tzu-Ting; Lin, Chia-Jung; Ong, Seow-Chin; Chen, Chun-Da; Chang, Jo-Shu; Lin, Chih-Sheng

    2011-10-01

    The growth and on-site bioremediation potential of an isolated thermal- and CO₂-tolerant mutant strain, Chlorella sp. MTF-7, were investigated. The Chlorella sp. MTF-7 cultures were directly aerated with the flue gas generated from coke oven of a steel plant. The biomass concentration, growth rate and lipid content of Chlorella sp. MTF-7 cultured in an outdoor 50-L photobioreactor for 6 days was 2.87 g L⁻¹ (with an initial culture biomass concentration of 0.75 g L⁻¹), 0.52 g L⁻¹ d⁻¹ and 25.2%, respectively. By the operation with intermittent flue gas aeration in a double-set photobioreactor system, average efficiency of CO₂ removal from the flue gas could reach to 60%, and NO and SO₂ removal efficiency was maintained at approximately 70% and 50%, respectively. Our results demonstrate that flue gas from coke oven could be directly introduced into Chlorella sp. MTF-7 cultures to potentially produce algal biomass and efficiently capture CO₂, NO and SO₂ from flue gas. Copyright © 2011 Elsevier Ltd. All rights reserved.

  5. Site selection experience for a new low-level radioactive waste storage/disposal facility at the Savannah River Plant

    International Nuclear Information System (INIS)

    Towler, O.A.; Cook, J.R.; Helton, B.D.

    1985-10-01

    Preliminary performance criteria and site selection guides specific to the Savannah River Plant, were developed for a new low-level radioactive waste storage/disposal facility. These site selection guides were applied to seventeen potential sites identified at SRP. The potential site were ranked based on how well they met a set of characteristics considered important in site selection for a low-level radioactive waste disposal facility. The characteristics were given a weighting factor representing its relative importance in meeting site performance criteria. A candidate site was selected and will be the subject of a site characterization program

  6. The human luteinizing hormone receptor gene promoter: activation by Sp1 and Sp3 and inhibitory regulation.

    Science.gov (United States)

    Geng, Y; Tsai-Morris, C H; Zhang, Y; Dufau, M L

    1999-09-24

    To understand the transcriptional mechanism(s) of human LH receptor (LHR) gene expression, we have identified the dominant functional cis-elements that regulate the activity of the promoter domain (-1 to -176 bp from ATG). Mutagenesis demonstrated that the promoter activity was dependent on two Sp1 domains (-79 bp, -120 bp) in a transformed normal placental cell (PLC) and the choriocarcinoma JAR cell. Both elements interacted with endogenous Sp1 and Sp3 factors but not with Sp2 or Sp4. In Drosophila SL2 cells, the promoter was activated by either Sp1 or Sp3. An ERE half-site (EREhs) at -174 bp was inhibitory (by 100%), but was unresponsive to estradiol and did not bind the estrogen receptor or orphan receptors ERR1 and SF-1. The 5' upstream sequence (-177 to -2056 bp) inhibited promoter activity in PLC by 60%, but only minimally in JAR cells. Activation of the human LHR promoter through Sp1/3 factors is negatively regulated through EREhs and upstream sequences to exert control of gene expression. Copyright 1999 Academic Press.

  7. Screening and identification of sites for a proposed Monitored Retrievable Storage Facility

    International Nuclear Information System (INIS)

    1985-04-01

    The Director, Office of Civilian Radioactive Waste Management (OCRWM), Department of Energy (DOE), has identified the Clinch River Breeder Reactor site, the DOE Oak Ridge Reservation and the Tennessee Valley Authority (TVA) Hartsville Nuclear Plant site as preferred and alternative sites, respectively, for development of site-specific designs as part of the proposal for construction of an integrated Monitored Retrievable Storage (MRS) Facility. The proposal, developed pursuant to Section 141 (b) of the Nuclear Waste Policy Act of 1982, will be submitted to Congress in January 1986. The Director expects to propose to Congress that an MRS be constructed at the perferred site. His judgment could change based on information to be developed between now and January 1986. The decision to construct an MRS facility and final site selection are reserved by Congress for itself. The Director's judgment is based on the results of a rigorous site screening and evaluation process described in this report. The three sites were selected from among eleven sites evaluated in detail. The Clinch River Breeder Reactor site, owned by the Tennessee Valley Authority, was identified as the preferred site. It has several particularly desirable features including: (1) federal ownership and control by the Department of Energy; (2) particularly good transportation access (five miles to the nearest interstate highway and direct rail access); (3) site characteristics and current data base judged by the NRC in 1983 as sufficient for granting a limited work authorization for the now cancelled breeder reactor; and (4) a technical community in the vicinity of site which can provide experienced nuclear facility support functions. 6 figs., 2 tabs

  8. 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

  9. Transcriptional regulation of HIV-1 host factor COMMD1 by the Sp family.

    Science.gov (United States)

    Kudo, Eriko; Taura, Manabu; Suico, Mary Ann; Goto, Hiroki; Kai, Hirofumi; Okada, Seiji

    2018-04-01

    Copper metabolism Murr1 domain containing 1 (COMMD1) has multiple functions in the regulation of protein stability at the plasma membrane and in the cytoplasm. However, the regulation of COMMD1 transcriptional has remained to be elucidated. In the present study, the 5'‑flanking region (‑1,192/+83 bp) of the human COMMD1 gene was cloned. It was observed that the COMMD1 promoter region contains GC‑rich region that has 7 putative Sp1‑binding sites via in silico analysis. The proximal promoter region at ‑289/+83 bp was required for COMMD1 basal promoter activity by deletion constructs of COMMD1 promoter. Moreover, Sp1 inhibitor, mithramycin A, suppressed basal COMMD1 promoter activity. The Sp1‑binding site (‑11/‑1 bp) in the proximal promoter region was a critical site for COMMD1 gene regulation by Sp1 and Sp3. Sp1 upregulated COMMD1 promoter activity, whereas Sp3 suppressed it. Endogenous Sp1 and Sp3 bound to the proximal promoter region of COMMD1. Taken together, Sp1 constitutively regulates the basal expression of the COMMD1 gene in human epithelial cell lines.

  10. SP2Bench: A SPARQL Performance Benchmark

    Science.gov (United States)

    Schmidt, Michael; Hornung, Thomas; Meier, Michael; Pinkel, Christoph; Lausen, Georg

    A meaningful analysis and comparison of both existing storage schemes for RDF data and evaluation approaches for SPARQL queries necessitates a comprehensive and universal benchmark platform. We present SP2Bench, a publicly available, language-specific performance benchmark for the SPARQL query language. SP2Bench is settled in the DBLP scenario and comprises a data generator for creating arbitrarily large DBLP-like documents and a set of carefully designed benchmark queries. The generated documents mirror vital key characteristics and social-world distributions encountered in the original DBLP data set, while the queries implement meaningful requests on top of this data, covering a variety of SPARQL operator constellations and RDF access patterns. In this chapter, we discuss requirements and desiderata for SPARQL benchmarks and present the SP2Bench framework, including its data generator, benchmark queries and performance metrics.

  11. Corrective Action Plan for Corrective Action Unit 135: Area 25 Underground Storage Tanks, Nevada Test Site, Nevada

    International Nuclear Information System (INIS)

    Cox, D. H.

    2000-01-01

    The Area 25 Underground Storage Tanks site Corrective Action Unit (CAU) 135 will be closed by unrestricted release decontamination and verification survey, in accordance with the Federal Facility Agreement and Consert Order (FFACO, 1996). The CAU includes one Corrective Action Site (CAS). The Area 25 Underground Storage Tanks, (CAS 25-02-01), referred to as the Engine-Maintenance Assembly and Disassembly (E-MAD) Waste Holdup Tanks and Vault, were used to receive liquid waste from all of the radioactive drains at the E-MAD Facility. Based on the results of the Corrective Action Investigation conducted in June 1999 discussed in the Corrective Action Investigation Plan for Corrective Action Unit 135: Area 25 Underground Storage Tanks, Nevada Test Site, Nevada (DOE/NV,1999a), one sample from the radiological survey of the concrete vault interior exceeded radionuclide preliminary action levels. The analytes from the sediment samples that exceeded the preliminary action levels are polychlorinated biphenyls, Resource Conservation and Recovery Act metals, total petroleum hydrocarbons as diesel-range organics, and radionuclides. Unrestricted release decontamination and verification involves removal of concrete and the cement-lined pump sump from the vault. After verification that the contamination has been removed, the vault will be repaired with concrete, as necessary. The radiological- and chemical-contaminated pump sump and concrete removed from the vault would be disposed of at the Area 5 Radioactive Waste Management Site. The vault interior will be field surveyed following removal of contaminated material to verify that unrestricted release criteria have been achieved

  12. Corrective Action Plan for Corrective Action Unit 135: Area 25 Underground Storage Tanks, Nevada Test Site, Nevada

    Energy Technology Data Exchange (ETDEWEB)

    D. H. Cox

    2000-07-01

    The Area 25 Underground Storage Tanks site Corrective Action Unit (CAU) 135 will be closed by unrestricted release decontamination and verification survey, in accordance with the Federal Facility Agreement and Consert Order (FFACO, 1996). The CAU includes one Corrective Action Site (CAS). The Area 25 Underground Storage Tanks, (CAS 25-02-01), referred to as the Engine-Maintenance Assembly and Disassembly (E-MAD) Waste Holdup Tanks and Vault, were used to receive liquid waste from all of the radioactive drains at the E-MAD Facility. Based on the results of the Corrective Action Investigation conducted in June 1999 discussed in the Corrective Action Investigation Plan for Corrective Action Unit 135: Area 25 Underground Storage Tanks, Nevada Test Site, Nevada (DOE/NV,1999a), one sample from the radiological survey of the concrete vault interior exceeded radionuclide preliminary action levels. The analytes from the sediment samples that exceeded the preliminary action levels are polychlorinated biphenyls, Resource Conservation and Recovery Act metals, total petroleum hydrocarbons as diesel-range organics, and radionuclides. Unrestricted release decontamination and verification involves removal of concrete and the cement-lined pump sump from the vault. After verification that the contamination has been removed, the vault will be repaired with concrete, as necessary. The radiological- and chemical-contaminated pump sump and concrete removed from the vault would be disposed of at the Area 5 Radioactive Waste Management Site. The vault interior will be field surveyed following removal of contaminated material to verify that unrestricted release criteria have been achieved.

  13. On-site storage of spent nuclear fuel assemblies in German nuclear power plants

    International Nuclear Information System (INIS)

    Banck, J.

    1999-01-01

    The selection of back-end strategies for spent fuel assemblies is influenced by a number of different factors depending on the given situation in any specific country. In Germany, the back-end strategy implemented in the past was almost exclusively reprocessing. This strategy was required by the German Atomic Energy Act. Since 1994, when the Atomic Energy Act was amended, the option of direct final disposal has been granted the equivalent status by law to that afforded to reprocessing (and reuse of valuable materials). As a result, German utilities may now choose between these two alternatives. Another important condition for optimizing the back-end policy is the fact that fuel cycle costs in Germany are directly dependent on spent fuel volumes (in contrast to the US, for example, such costs are related to the amount of power generated). Another boundary condition for German utilities with respect to spent fuel management is posed by the problems with militant opponents of nuclear energy during transportation of spent fuel to interim storage sites. These facts have given rise to a reconsideration of the fuel cycle back-end, which has resulted in a change in strategy by most German utilities in favour of the following: Preference for long-term storage and maximized use of on-site storage capacity; Reduction in the amount of spent fuel by increasing burnup as much as possible. These decisions have also been driven by the deregulation of energy markets in Europe, where utilities are now permitted to sell electric power to consumers beyond their original supply network and must therefore offer electric power on a very cost competitive basis. (author)

  14. Initial ORNL site assessment report on the storage of 233U

    International Nuclear Information System (INIS)

    Bereolos, P.J.; Yong, L.K.; Sadlowe, A.R.; Ramey, D.W.; Krichinsky, A.M.

    1998-03-01

    The 233 U storage facility at ORNL is Building 3019. The inventory stored in Building 3019 consists of 426.5 kg of 233 U contained in 1,387.1 kg of total uranium. The inventory is primarily in the form of uranium oxides; however, uranium metal and other compounds are also stored. Over 99% of the inventory is contained in 1,007 packages stored in tube vaults within the facility. A tank of thorium nitrate solution, the P-24 Tank, contains 0.13 kg of 233 U in ∼ 4,000 gal. of solution. The facility is receiving additional 233 U for storage from the remediation of the Molten Salt Reactor Experiment (MSRE) at ORNL. Consolidation of material from sites with small holdings is also adding to the 233 U inventory. Additionally, small quantities ( 233 U are in other research facilities at ORNL. A risk assessment process was chosen to evaluate the stored material and packages based on available package records. The risk scenario was considered the failure of a package (or a group of similar packages) in the Building 3019 inventory. The probability of such a failure depends on packaging factors such as the age and material of construction of the containers. The consequence of such a failure depends on the amount and form of the material within the packages. One thousand seven packages were categorized with this methodology resulting in 859 low-risk packages, 147 medium-risk packages, and 1 high-risk package. This initial assessment also documents the status of the evaluation of the Building 3019 and its systems for safe storage of 233 U. The final assessment report for ORNL storage of 233 U is scheduled for June 1999. The report will document the facility assessments, the specific package inspection plan, and the results of initial package inspections

  15. Use of artificial barriers in a site for surface storage of radioactive waste

    International Nuclear Information System (INIS)

    Gros, J.C.; Madoz-Escande, C.; Metivier, J.M.; Grimaud, P.

    1990-01-01

    The objective is the on site study of the influence of an injection screen on the flow in a water table of a porous medium, in order to improve the safety of a surface radioactive waste storage site. A hydrodispersive study has provided information for the definition of the role of the screen: the transfer times of the pollutant in the water table are increased by a factor of 2 and, in comparison, the concentration are clearly reduced by a factor of 10. The implantation of an injection screen in the ground should result in an improvement in the restrictive quality of the barrier and the contamination of an aquifer should be slower without interruption to the flow

  16. Environmental impact assessment of decommissioning treatment about radioactive model plant waste ore storage site

    International Nuclear Information System (INIS)

    Bei Xinyu

    2012-01-01

    Aiming at decommissioning treatment project of radioactive model plant waste ore storage site, based on the detailed investigations of source terms and project description, systematic environmental impacts have been identified. The environmental impacts both during decommissioning treatment, radioactive waste transportation and after treatment are assessed. Some specific environmental protection measures are proposed so as to minimize the adverse environmental impacts. (author)

  17. Niagara Falls Storage Site environmental report for calendar year 1989, Lewiston, New York

    International Nuclear Information System (INIS)

    1990-05-01

    The environmental monitoring program, which began in 1981, was continued during 1989 at the Niagara Falls Storage Site (NFSS), a United States Department of Energy (DOE) surplus facility located in Niagara County, New York, that is currently used for interim storage of radioactive residues, contaminated soils, and rubble. The monitoring program is being conducted by Bechtel National, Inc. The monitoring program at NFSS measures radon concentrations in air; external gamma radiation levels; and uranium and radium concentrations in surface water, groundwater, and sediment. Additionally, several nonradiological parameters are measured in groundwater. To verify that the site is in compliance with the DOE radiation protection standard and to assess its potential effect on public health, the radiation dose was calculated for a hypothetical maximally exposed individual. Based on the conservative scenario described in this report, this hypothetical individual receives an annual external exposure equivalent to approximately 2 percent of the DOE radiation protection standard of 100 mrem/yr. This exposure is less than a person receives during a one-way flight from New York to Los Angeles (because of the greater amounts of cosmic radiation at higher altitudes). The cumulative dose to the population within an 80-km (50-mi) radius of NFSS that results from radioactive materials present at the site is indistinguishable from the dose that the same population receives from naturally occurring radioactive sources. Results of the 1989 monitoring show that NFSS is in compliance with applicable DOE radiation protection standards. 18 refs., 26 figs., 18 tabs

  18. Site-specific issues related to structural/seismic design of an underground independent spent fuel storage installation (ISFSI)

    International Nuclear Information System (INIS)

    Tripathi, B.P.

    2005-01-01

    Utilities owning and operating commercial nuclear power plants (NPP) in USA may choose to build an underground Independent Spent Fuel Storage Installation (ISFSI) to store the spent nuclear fuels. The regulatory requirements and other guidance are based on 10 CFR Part 72, Regulatory Guide RG 3.73, Standard Review Plans NUREG-1536 and NUREG-1567, and Interim staff Guidance (ISG) documents as applicable. Structures, Systems, and Components (SSCs) classified as important to safety are designed to withstand the effects of site-specific environmental conditions and natural phenomena such as earthquake, tornado, flood, etc. An underground ISFSI for storage of spent nuclear fuel, presents some unique analysis and design challenges. This paper will briefly address some of these challenges and discuss site-specific loads, including seismic for the ISFSI design. (authors)

  19. 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

  20. Draft genome sequences of six neonatal meningitis-causing escherichia coli isolates (SP-4, SP-5, SP-13, SP-16, SP-46, and SP-65)

    Science.gov (United States)

    Neonatal meningitis Escherichia coli isolates (SP-4, SP-5, SP-13, SP-16, SP-46, and SP-65) were recovered from infants in the Netherlands from 1989 to 1997. Here, we report the draft genome sequences for these six E. coli isolates, which are currently being used to validate food safety processing te...

  1. The Niagara Falls Storage Site Remedial Action Project. Status update and summary of special features

    International Nuclear Information System (INIS)

    Campbell, L.F.; Coxon, G.D.

    1986-01-01

    The U.S. Department of Energy (DOE) and its Project Management Contractor, Bechtel National, Inc., are conducting remedial action at the Niagara Falls Storage Site (NFSS) near Lewiston, New York to stabilize low-level radioactive wastes stored at the site and to decontaminate over two dozen contaminated vicinity properties. Over the past 4 years a 10-acre interim waste containment facility has been developed at the site to hold the approximately 250,000 yd/sup 3/ of contaminated soil and rubble from the cleanup operations. Several existing buildings were demolished or modified for burial inside the containment area. In addition, residues inside a 165-ft-high concrete tower were transferred to one of the buildings inside the containment area using hydraulic mining techniques. The residues were dewatered and covered with clay to minimize radom emanation; the tower was demolished and the rubble disposed of in the containment area. Environmental monitoring will continue throughout the interim storage period. In addition, the surface and subsurface condition of the containment structure will be monitored to ensure that undesirable trends are detected in time for corrective action to be taken. The DOE Record of Decision on the long-term disposition of the NFSS is expected to be made by the end of April, 1986

  2. The search for a storage site for low-level and long-life wastes. December 2008 report

    International Nuclear Information System (INIS)

    2008-01-01

    After having recalled the methodology and approach implemented for the search and selection of radioactive waste storage sites, this report proposes a brief synthesis of contacts taken during the call for candidates. It comments the results of this call, describes the project technical constraints (waste inventory, studied solutions, graphite and radiferous wastes, programmed investigations on preselected sites), gives the results of the geological analysis (methodology, geological context, site ranking), of the environmental analysis (context and principles, collected information), and of the socio-economic analysis of the candidate sites. The last chapter discusses the identification of possible preselected sites. Some more detailed information are available in appendix: candidate list, geological sheets and maps, environmental and socio-economic analysis of candidate towns or districts

  3. Dry spent fuel storage licensing

    International Nuclear Information System (INIS)

    Sturz, F.C.

    1995-01-01

    In the US, at-reactor-site dry spent fuel storage in independent spent fuel storage installations (ISFSI) has become the principal option for utilities needing storage capacity outside of the reactor spent fuel pools. Delays in the geologic repository operational date at or beyond 2010, and the increasing uncertainty of the US Department of Energy's (DOE) being able to site and license a Monitored Retrievable Storage (MRS) facility by 1998 make at-reactor-site dry storage of spent nuclear fuel increasingly desirable to utilities and DOE to meet the need for additional spent fuel storage capacity until disposal, in a repository, is available. The past year has been another busy year for dry spent fuel storage licensing. The licensing staff has been reviewing 7 applications and 12 amendment requests, as well as participating in inspection-related activities. The authors have licensed, on a site-specific basis, a variety of dry technologies (cask, module, and vault). By using certified designs, site-specific licensing is no longer required. Another new cask has been certified. They have received one new application for cask certification and two amendments to a certified cask design. As they stand on the brink of receiving multiple applications from DOE for the MPC, they are preparing to meet the needs of this national program. With the range of technical and licensing options available to utilities, the authors believe that utilities can meet their need for additional spent fuel storage capacity for essentially all reactor sites through the next decade

  4. Effects of CO2 gas as leaks from geological storage sites on agro-ecosystems

    DEFF Research Database (Denmark)

    Patil, Ravi; Colls, Jeremy J; Steven, Michael D

    2010-01-01

    Carbon capture and storage in geological formations has potential risks in the long-term safety because of the possibility of CO2 leakage. Effects of leaking gas, therefore, on vegetation, soil, and soil-inhabiting organisms are critical to understand. An artificial soil gassing and response...... detection field facility developed at the University of Nottingham was used to inject CO2 gas at a controlled flow rate (1 l min-1) into soil to simulate build-up of soil CO2 concentrations and surface fluxes from two land use types: pasture grassland, and fallow followed by winter bean. Mean soil CO2....... This study showed adverse effects of CO2 gas on agro-ecosystem in case of leakage from storage sites to surface....

  5. An economic analysis of a monitored retrievable storage site for Tennessee. Final report and appendices

    Energy Technology Data Exchange (ETDEWEB)

    Fox, W.F.; Mayo, J.W.; Hansen, L.T.; Quindry, K.E.

    1985-12-17

    The United States Department of Energy is charged with the task of identifying potential sites for a Monitored Retrievable Storage (MRS) Facility and reporting the results of its analysis to Congress by January 1986. DOE chose three finalist sites from 11 sites DOE analysts evaluated earlier. All three are in Tennessee, including two in Oak Ridge and one in Trousdale/Smith Counties. This paper is a summary of research undertaken on the economic effects of establishing the MRS facility in Tennessee. All three locations were considered in the analysis, but on some occasions attention is focused on the site preferred by DOE. The research was undertaken by the Center for Business and Economic Research (CBER), College of Business Administration, the University of Tennessee, Knoxville, under contract with the Tennessee Department of Economic and Community Development.

  6. Isolation and characterization of a chromium-resistant bacterium Serratia sp. Cr-10 from a chromate-contaminated site.

    Science.gov (United States)

    Zhang, Kundi; Li, Fuli

    2011-05-01

    A novel bacterium, Cr-10, was isolated from a chromium-contaminated site and capable of removing toxic chromium species from solution by reducing hexavalent chromium to an insoluble precipitate. Sequence analysis of 16S rRNA gene of strain Cr-10 showed that it was most closely related to Serratia rubidaea JCM 1240(T) (97.68%). Physiological and chemotaxonomic data also supported that strain Cr-10 was identified as Serratia sp., a genus which was never specially reported chromate-resistant before. Serratia sp., Cr-10 was tolerant to a concentration of 1,500 mg Cr(VI) L(-1), which was the highest level reported until now. The optimum pH and temperature for reduction of Cr(VI) by Serratia sp. Cr-10 were found to be 7.0 and 37 °C, respectively. The Cr(VI) reduction was significantly influenced by additional carbon sources, and among them fructose and lactose offered maximum reduction, with a rate of 0.28 and 0.25 mg Cr(VI) L(-1) h(-1), respectively. The cell-free extracts and filtrate of the culture were able to reduce Cr(VI) while concentration of total chromium remained stable in the process, indicating that the enzyme-catalyzed mechanism was applied in Cr(VI) reduction by the isolate. Additionally, it was found that there was hardly any chromium on the cell surface of the strain, further supporting that reduction, rather than bioadsorption, plays a major role in the Cr(VI) removal.

  7. Isolation and characterization of a chromium-resistant bacterium Serratia sp. Cr-10 from a chromate-contaminated site

    Energy Technology Data Exchange (ETDEWEB)

    Zhang, Kundi; Li, Fuli [Chinese Academy of Sciences, Qingdao (China). Qingdao Inst. of Bioenergy and Bioprocess Technology

    2011-05-15

    A novel bacterium, Cr-10, was isolated from a chromium-contaminated site and capable of removing toxic chromium species from solution by reducing hexavalent chromium to an insoluble precipitate. Sequence analysis of 16S rRNA gene of strain Cr-10 showed that it was most closely related to Serratia rubidaea JCM 1240{sup T} (97.68%). Physiological and chemotaxonomic data also supported that strain Cr-10 was identified as Serratia sp., a genus which was never specially reported chromate-resistant before. Serratia sp., Cr-10 was tolerant to a concentration of 1,500 mg Cr(VI) L{sup -1}, which was the highest level reported until now. The optimum pH and temperature for reduction of Cr(VI) by Serratia sp. Cr-10 were found to be 7.0 and 37 C, respectively. The Cr(VI) reduction was significantly influenced by additional carbon sources, and among them fructose and lactose offered maximum reduction, with a rate of 0.28 and 0.25 mg Cr(VI) L{sup -1} h{sup -1}, respectively. The cell-free extracts and filtrate of the culture were able to reduce Cr(VI) while concentration of total chromium remained stable in the process, indicating that the enzyme-catalyzed mechanism was applied in Cr(VI) reduction by the isolate. Additionally, it was found that there was hardly any chromium on the cell surface of the strain, further supporting that reduction, rather than bioadsorption, plays a major role in the Cr(VI) removal. (orig.)

  8. Efficient biotransformation of herbicide diuron by bacterial strain Micrococcus sp. PS-1.

    Science.gov (United States)

    Sharma, Priyanka; Chopra, Adity; Cameotra, Swaranjit Singh; Suri, C Raman

    2010-11-01

    A Gram-positive, Micrococcus sp. strain PS-1 capable of utilizing phenylurea herbicide diuron as a sole carbon source at a high concentration (up to 250 ppm) was isolated from diuron storage site by selective enrichment study. The taxonomic characterization with 16S rRNA gene sequencing (1,477 bp) identified PS-1 as a member of Micrococcus sp. It was studied for the degradation of diuron and a range of its analogues (monuron, linuron, monolinuron, chlortoluron and fenuron). The shake flasks experiments demonstrated fast degradation of diuron (up to 96% at 250 ppm within 30 h incubation) with the addition of small quantity (0.01%) of non-ionic detergent. The relative degradation profile by the isolate was in the order of fenuron > monuron > diuron > linuron > monolinuron > chlortoluron. Further, the biochemical characterization of catabolic pathway by spectroscopic and chromatographic techniques demonstrated that the degradation proceeded via formation of dealkylated metabolites to form 3,4-dichloroaniline (3,4-DCA). It was the major metabolite formed, associated with profound increase in degradation kinetics in presence of appropriate additive.

  9. Closure Report for Corrective Action Unit 124, Storage Tanks, Nevada Test Site, Nevada with Errata Sheet, Revision 0

    Energy Technology Data Exchange (ETDEWEB)

    Alfred Wickline

    2008-01-01

    This Closure Report (CR) presents information supporting closure of Corrective Action Unit (CAU) 124, Storage Tanks, Nevada Test Site (NTS), Nevada. This report complies with the requirements of the Federal Facility Agreement and Consent Order (FFACO) that was agreed to by the State of Nevada; U.S. Department of Energy (DOE), Environmental Management; U.S. Department of Defense; and DOE, Legacy Management (FFACO, 1996; as amended January 2007). This CR provides documentation and justification for the closure of CAU 124 without further corrective action. This justification is based on process knowledge and the results of the investigative activities conducted in accordance with the Streamlined Approach for Environmental Restoration (SAFER) Plan for Corrective Action Unit 124: Storage Tanks, Nevada Test Site, Nevada (NNSA/NSO, 2007). The SAFER Plan provides information relating to site history as well as the scope and planning of the investigation. Therefore, this information will not be repeated in this CR.

  10. 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)

  11. Compressed air energy storage: preliminary design and site development program in an aquifer. Final draft, Task 2: Volume 2 of 3. Characterize and explore potential sites and prepare research and development plan

    Energy Technology Data Exchange (ETDEWEB)

    None

    1980-12-01

    The characteristics of sites in Indiana and Illinois which are being investigated as potential sites for compressed air energy storage power plants are documented. These characteristics include geological considerations, economic factors, and environmental considerations. Extensive data are presented for 14 specific sites and a relative rating on the desirability of each site is derived. (LCL)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2013-07-01

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

  13. Structure of a highly acidic β-lactamase from the moderate halophile Chromohalobacter sp. 560 and the discovery of a Cs+-selective binding site

    International Nuclear Information System (INIS)

    Arai, Shigeki; Yonezawa, Yasushi; Okazaki, Nobuo; Matsumoto, Fumiko; Shibazaki, Chie; Shimizu, Rumi; Yamada, Mitsugu; Adachi, Motoyasu; Tamada, Taro; Kawamoto, Masahide; Tokunaga, Hiroko; Ishibashi, Matsujiro; Blaber, Michael; Tokunaga, Masao; Kuroki, Ryota

    2015-01-01

    The tertiary structure of a β-lactamase derived from the halobacterium Chromohalobacter sp. 560 (HaBLA) was determined by X-ray crystallography. Three unique Sr 2+ -binding sites and one Cs + -binding site were discovered in the HaBLA molecule. Environmentally friendly absorbents are needed for Sr 2+ and Cs + , as the removal of the radioactive Sr 2+ and Cs + that has leaked from the Fukushima Nuclear Power Plant is one of the most important problems in Japan. Halophilic proteins are known to have many acidic residues on their surface that can provide specific binding sites for metal ions such as Cs + or Sr 2+ . The crystal structure of a halophilic β-lactamase from Chromohalobacter sp. 560 (HaBLA) was determined to resolutions of between 1.8 and 2.9 Å in space group P3 1 using X-ray crystallography. Moreover, the locations of bound Sr 2+ and Cs + ions were identified by anomalous X-ray diffraction. The location of one Cs + -specific binding site was identified in HaBLA even in the presence of a ninefold molar excess of Na + (90 mM Na + /10 mM Cs + ). From an activity assay using isothermal titration calorimetry, the bound Sr 2+ and Cs + ions do not significantly affect the enzymatic function of HaBLA. The observation of a selective and high-affinity Cs + -binding site provides important information that is useful for the design of artificial Cs + -binding sites that may be useful in the bioremediation of radioactive isotopes

  14. Nuclear materials management storage study

    International Nuclear Information System (INIS)

    Becker, G.W. Jr.

    1994-02-01

    The Office of Weapons and Materials Planning (DP-27) requested the Planning Support Group (PSG) at the Savannah River Site to help coordinate a Departmental complex-wide nuclear materials storage study. This study will support the development of management strategies and plans until Defense Programs' Complex 21 is operational by DOE organizations that have direct interest/concerns about or responsibilities for nuclear material storage. They include the Materials Planning Division (DP-273) of DP-27, the Office of the Deputy Assistant Secretary for Facilities (DP-60), the Office of Weapons Complex Reconfiguration (DP-40), and other program areas, including Environmental Restoration and Waste Management (EM). To facilitate data collection, a questionnaire was developed and issued to nuclear materials custodian sites soliciting information on nuclear materials characteristics, storage plans, issues, etc. Sites were asked to functionally group materials identified in DOE Order 5660.1A (Management of Nuclear Materials) based on common physical and chemical characteristics and common material management strategies and to relate these groupings to Nuclear Materials Management Safeguards and Security (NMMSS) records. A database was constructed using 843 storage records from 70 responding sites. The database and an initial report summarizing storage issues were issued to participating Field Offices and DP-27 for comment. This report presents the background for the Storage Study and an initial, unclassified summary of storage issues and concerns identified by the sites

  15. The effect of various concentration of tilapia (Oreochromis sp.) surimi for edible coating on the shelf-life of Pangasius sp. fillets

    Science.gov (United States)

    Purnama, M. A. P.; Agustono; Sahidu, A. M.

    2018-04-01

    Pangasius sp. fillets prone to deterioration the quality that will affect the appearance and the shelf life of fillets. The effort to extend the shelf life of fish fillet that is by using an edible coating. Surimi can be used as a protein-based edible coating because they have superior inhibitory and mechanical properties compared to the polysaccharides based material. Surimi can be made from freshwater tilapia (Oreochromis sp.) fish. The experimental design used was Completely Randomized Design (CRD) with five treatments of surimi (0 gr, 2 gr, 4 gr, 6 gr, 8 gr) with four replications. The results showed that Pangasius sp. fillets with an edible coating 8 gr surimi have the highest value in the organoleptic test. The pH testing on Pangasius sp. fillets with edible coating 2 gr, 4 gr, 6 gr, and 8 gr surimi from the 0th hour to 18th hour have increased but slower than Pangasius sp. fillets without edible coating surimi. The best value of Total Plate Count (TPC) test is in edible coating 6 gr and 8 gr surimi as it is in accordance with SNI 2696:2013 at room temperature storage until the 18th hours.

  16. Hanford site transuranic waste sampling plan

    International Nuclear Information System (INIS)

    GREAGER, T.M.

    1999-01-01

    This sampling plan (SP) describes the selection of containers for sampling of homogeneous solids and soil/gravel and for visual examination of transuranic and mixed transuranic (collectively referred to as TRU) waste generated at the U.S. Department of Energy (DOE) Hanford Site. The activities described in this SP will be conducted under the Hanford Site TRU Waste Certification Program. This SP is designed to meet the requirements of the Transuranic Waste Characterization Quality Assurance Program Plan (CAO-94-1010) (DOE 1996a) (QAPP), site-specific implementation of which is described in the Hanford Site Transuranic Waste Characterization Program Quality Assurance Project Plan (HNF-2599) (Hanford 1998b) (QAPP). The QAPP defines the quality assurance (QA) requirements and protocols for TRU waste characterization activities at the Hanford Site. In addition, the QAPP identifies responsible organizations, describes required program activities, outlines sampling and analysis strategies, and identifies procedures for characterization activities. The QAPP identifies specific requirements for TRU waste sampling plans. Table 1-1 presents these requirements and indicates sections in this SP where these requirements are addressed

  17. Effectiveness of interim remedial actions at the Niagara Falls Storage Site

    International Nuclear Information System (INIS)

    Devgun, J.S.; Beskid, N.J.; Seay, W.M.; McNamee, E.

    1990-01-01

    There are 190,000 m 3 of contaminated soils, wastes, and residues stored at the Niagara Falls Storage Site (NFSS). The residues have a volume of 18,000 m 3 and contain about 1,930 Ci of 226 Ra, which accounts for most of the radioactivity. Since 1980, actions have been taken to minimize potential radiological risks and prevent radionuclide migration. Interim actions included capping vents, sealing pipes, relocating the perimeter fence (to limit radon risk), transferring and consolidating wastes, upgrading storage buildings, constructing a clay cutoff wall (to limit potential ground-water transport of contaminants), treating and releasing contaminated water, using a synthetic liner, and using an interim clay cap. An interim waste containment facility was completed in 1986. Environmental monitoring showed a decrease in radon concentrations and in external gamma radiation from 1982 to 1986; levels have been stable since 1986. Uranium and radium concentrations in surface water have decreased; very low concentrations have been detected in stream sediments, and concentrations in ground water have remained stable. Recent monitoring showed that NFSS is in compliance with the U.S. Department of Energy's (DOE's) radiation protection standards

  18. SP-A-enriched surfactant for treatment of rat lung transplants with SP-A deficiency after storage and reperfusion

    NARCIS (Netherlands)

    Erasmus, ME; Hofstede, GJH; Petersen, AH; Batenburg, JJ; Haagsman, HP; Oetomo, SB; Prop, J

    2002-01-01

    Background. The function of pulmonary surfactant is affected by lung transplantation, contributing to impaired lung transplant function. A decreased amount of surfactant protein-A (SP-A) after reperfusion is believed to contribute to the impaired surfactant function. Surfactant treatment has been

  19. Wayne Interim Storage Site annual environmental report for calendar year 1991, Wayne, New Jersey

    International Nuclear Information System (INIS)

    1992-09-01

    This document describes the envirormental monitoring program at the Wayne Interim Storage Site (WISS) and surrounding area, implementation of the program, and monitoring results for 1991. Environmental monitoring of WISS and surrounding area began in 1984 when Congress added the site to the US Department of Energy's (DOE) Formerly Utilized Sites Remedial Action Program (FUSRAP). FUSRAP is a DOE program to decontaminate or otherwise control sites where residual radioactive materials remain from the early years of the nation's atomic energy program or from commercial operations causing conditions that Congress has authorized DOE to remedy. WISS is a National Priorities List site. The environmental monitoring program at WISS includes sampling networks for radon and thoron concentrations in air; external gamma radiation exposure; and radium-226, radium-228, thorium-232, and total uranium concentrations in surface water, sediment, and groundwater. Several nonradiological parameters are also measured in groundwater. Monitoring results are compared with applicable Environmental Protection Agency standards, DOE derived concentration guides, dose limits, and other requirements in DOE orders. Environmental standards are established to protect public health and the environment

  20. Feasibility assessment grants in support of volunteer siting of a monitored retrievables storage facility

    International Nuclear Information System (INIS)

    Benson, A.; Weisman, N.M.; Morgan, W.

    1993-01-01

    The Monitored Retrievable Storage facility (MRS) is an integral component of the planned Federal radioactive waste management system. The MRS will temporarily store spent fuel from commercial nuclear power plants prior to shipment to a geologic repository for permanent disposal. To facilitate voluntary siting of an MRS facility, Congress, in 1987, authorized the award of feasibility assessment grants by the Department of Energy to assist potentially interested jurisdictions to consider the possibility of hosting an MRS. This paper addresses the experience with MRS feasibility assessment grants to date, reviewing the current status of grant applications and presenting observations on the grant program and the voluntary siting approach, which it supports. The authors note that although the voluntary siting process has yet to identify an MRS host, the feasibility assessment grants have been successful in generating interest and active consideration and debate regarding MRS siting among States, Indian Tribes, and affected units of local government. Continued information efforts about the grant process and more proactive DOE support for and participation in the voluntary siting process are among the recommendations offered

  1. An optimization of the ALICE XRootD storage cluster at the Tier-2 site in Czech Republic

    International Nuclear Information System (INIS)

    Adamova, D; Horky, J

    2012-01-01

    ALICE, as well as the other experiments at the CERN LHC, has been building a distributed data management infrastructure since 2002. Experience gained during years of operations with different types of storage managers deployed over this infrastructure has shown, that the most adequate storage solution for ALICE is the native XRootD manager developed within a CERN - SLAC collaboration. The XRootD storage clusters exhibit higher stability and availability in comparison with other storage solutions and demonstrate a number of other advantages, like support of high speed WAN data access or no need for maintaining complex databases. Two of the operational characteristics of XRootD data servers are a relatively high number of open sockets and a high Unix load. In this article, we would like to describe our experience with the tuning/optimization of machines hosting the XRootD servers, which are part of the ALICE storage cluster at the Tier-2 WLCG site in Prague, Czech Republic. The optimization procedure, in addition to boosting the read/write performance of the servers, also resulted in a reduction of the Unix load.

  2. Underground Storage Tanks in Iowa

    Data.gov (United States)

    Iowa State University GIS Support and Research Facility — Underground storage tank (UST) sites which store petroleum in Iowa. Includes sites which have been reported to DNR, and have active or removed underground storage...

  3. Streamlined approach for environmental restoration closure report for Corrective Action Unit 454: Historical underground storage tank release sites, Nevada Test Site, Nevada

    International Nuclear Information System (INIS)

    1998-04-01

    This report addresses the characterization of three historical underground storage tank (UST) petroleum hydrocarbon release sites identified as 12-B-1, 12-B-3, and 12-COMM-1. The sites are located within the Nevada Test Site in Area 12 at B Tunnel and a former Communications/Power Maintenance Shop. Release Site 12-B-1 was not able to be clean-closed as proposed in the SAFER Plan. However, hydrocarbon impacted soils were excavated down to bedrock. Release Site 12-B-3 was evaluated to verify that the identified release was not associated with the UST removed from the site. Analytical results support the assumption that wood or possibly a roof sealant used as part of the bunker construction could have been the source of hydrocarbons detected. Release Site 12-COMM-1 was not clean closed as proposed in the SAFER Plan. The vertical extent of impacted soils was determined not to extend below a depth of 2.7 m (9 ft) below ground surface (bgs). The lateral extent could not be defined due to the presence of a discontinuous lens of hydrocarbon-impacted soil

  4. Streamlined approach for environmental restoration closure report for Corrective Action Unit 454: Historical underground storage tank release sites, Nevada Test Site, Nevada

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-04-01

    This report addresses the characterization of three historical underground storage tank (UST) petroleum hydrocarbon release sites identified as 12-B-1, 12-B-3, and 12-COMM-1. The sites are located within the Nevada Test Site in Area 12 at B Tunnel and a former Communications/Power Maintenance Shop. Release Site 12-B-1 was not able to be clean-closed as proposed in the SAFER Plan. However, hydrocarbon impacted soils were excavated down to bedrock. Release Site 12-B-3 was evaluated to verify that the identified release was not associated with the UST removed from the site. Analytical results support the assumption that wood or possibly a roof sealant used as part of the bunker construction could have been the source of hydrocarbons detected. Release Site 12-COMM-1 was not clean closed as proposed in the SAFER Plan. The vertical extent of impacted soils was determined not to extend below a depth of 2.7 m (9 ft) below ground surface (bgs). The lateral extent could not be defined due to the presence of a discontinuous lens of hydrocarbon-impacted soil.

  5. Plutonium storage criteria

    Energy Technology Data Exchange (ETDEWEB)

    Chung, D. [Scientech, Inc., Germantown, MD (United States); Ascanio, X. [Dept. of Energy, Germantown, MD (United States)

    1996-05-01

    The Department of Energy has issued a technical standard for long-term (>50 years) storage and will soon issue a criteria document for interim (<20 years) storage of plutonium materials. The long-term technical standard, {open_quotes}Criteria for Safe Storage of Plutonium Metals and Oxides,{close_quotes} addresses the requirements for storing metals and oxides with greater than 50 wt % plutonium. It calls for a standardized package that meets both off-site transportation requirements, as well as remote handling requirements from future storage facilities. The interim criteria document, {open_quotes}Criteria for Interim Safe Storage of Plutonium-Bearing Solid Materials{close_quotes}, addresses requirements for storing materials with less than 50 wt% plutonium. The interim criteria document assumes the materials will be stored on existing sites, and existing facilities and equipment will be used for repackaging to improve the margin of safety.

  6. Corrective Action Investigation Plan for Corrective Action Unit 166: Storage Yards and Contaminated Materials, Nevada Test Site, Nevada

    International Nuclear Information System (INIS)

    David Strand

    2006-01-01

    Corrective Action Unit 166 is located in Areas 2, 3, 5, and 18 of the Nevada Test Site, which is 65 miles northwest of Las Vegas, Nevada. Corrective Action Unit (CAU) 166 is comprised of the seven Corrective Action Sites (CASs) listed below: (1) 02-42-01, Cond. Release Storage Yd - North; (2) 02-42-02, Cond. Release Storage Yd - South; (3) 02-99-10, D-38 Storage Area; (4) 03-42-01, Conditional Release Storage Yard; (5) 05-19-02, Contaminated Soil and Drum; (6) 18-01-01, Aboveground Storage Tank; and (7) 18-99-03, Wax Piles/Oil Stain. These sites are being investigated because existing information on the nature and extent of potential contamination is insufficient to evaluate and recommend corrective action alternatives. Additional information will be obtained by conducting a corrective action investigation (CAI) before evaluating corrective action alternatives and selecting the appropriate corrective action for each CAS. The results of the field investigation will support a defensible evaluation of viable corrective action alternatives that will be presented in the Corrective Action Decision Document. The sites will be investigated based on the data quality objectives (DQOs) developed on February 28, 2006, by representatives of the Nevada Division of Environmental Protection; U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office; Stoller-Navarro Joint Venture; and Bechtel Nevada. The DQO process was used to identify and define the type, amount, and quality of data needed to develop and evaluate appropriate corrective actions for CAU 166. Appendix A provides a detailed discussion of the DQO methodology and the DQOs specific to each CAS. The scope of the CAI for CAU 166 includes the following activities: (1) Move surface debris and/or materials, as needed, to facilitate sampling. (2) Conduct radiological surveys. (3) Perform field screening. (4) Collect and submit environmental samples for laboratory analysis to determine if

  7. Cr(VI) reduction from contaminated soils by Aspergillus sp. N2 and Penicillium sp. N3 isolated from chromium deposits.

    Science.gov (United States)

    Fukuda, Tsubasa; Ishino, Yasuhiro; Ogawa, Akane; Tsutsumi, Kadzuyo; Morita, Hiroshi

    2008-10-01

    Aspergillus sp. N2 and Penicillium sp. N3 are chromate-resistant filamentous fungi that were isolated from Cr(VI) contaminated soil based on their ability to decrease hexavalent chromium levels in the growth medium. After 120 h of growth in a medium containing 50 ppm Cr(VI) at near neutral pH, Aspergillus sp. N2 reduced the Cr(VI) concentration by about 75%. Penicillium sp. N3 was able to reduce the Cr(VI) concentration by only 35%. However, Penicillium sp. N3 reduced the Cr(VI) concentration in the medium by 93% under acidic conditions. Interestingly, the presence of Cu(II) enhanced the Cr(VI) reducing ability of Aspergillus sp. N2 and Penicillium sp. N3 at near neutral pH. Aspergillus sp. N2 and Penicillium sp. N3 reduced the Cr(VI) concentration in the growth medium to a virtually undetectable level within 120 h. For both Aspergillus sp. N2 and Penicillium sp. N3, mycelial seed cultures were more efficient at Cr(VI) reduction than conidium seed cultures. The mechanisms of Cr(VI) reduction in Aspergillus sp. N2 and Penicillium sp. N3 were enzymatic reduction and sorption to mycelia. Enzymatic activity contributed significantly to Cr(VI) reduction. Aspergillus sp. N2 and Penicillium sp. N3 reduced the levels of Cr(VI) in polluted soil samples, suggesting that these strains might be useful for cleaning up chromium-contaminated sites.

  8. Annotated bibliography for biologic overview for the Nevada Nuclear Waste Storage Investigations, Nevada Test Site, Nye County, Nevada

    International Nuclear Information System (INIS)

    Collins, E.; O'Farrell, T.P.; Rhoads, W.A.

    1981-12-01

    This annotated bibliography was compiled to accompany the Biologic Overview for the Nevada Nuclear Waste Storage Investigations, Nevada Test Site, Nye County, Nevada, EG and G, Santa Barbara Operations Report No. EGG 1183-2443, which documents and synthesizes important biotic information related to Nevada Nuclear Waste Storage Investigations (NNWSI). As such, it is an important part of the NNWSI screening process that was designed to include a systematic, traceable, defensible, and documented basis for a decision to proceed or not with site-specific phases on NTS. Included are all published, and available but unpublished, baseline information on life histories, habitat requirements, distributions, and ecological relationships of the flora and fauna of the region. Special effort was made to include information on endangered, threatened, or sensitive species. 131 references

  9. Lama Penyimpanan, Karakterisasi Fisiologi, dan Viabilitas Bakteri Endofit Bacillus sp. dalam Formula Tepung

    Directory of Open Access Journals (Sweden)

    Diana putri

    2016-03-01

    Full Text Available Endophytic bacteria can be formulated to retain its ability as disease control agents. Three of endophytic bacteria which had the capability to suppress infection of Meloidogyne sp, and to enhance pepper growth were gained from the previous study. This research was aimed to evaluate the influence of storage time on the viability of endophytic bacteria, Bacillus sp. AA2, Bacillus sp. MER and MSJ, and to study its physiological charaterization during storage. The formulation evaluated in this study was : formulation 1 (50 g talc, 1 g pepton, 0.5 g CMC, and brown sugar 1.5 g, formulation 2 (50 g talc, 1 g pepton, 0.5 g CMC, and 1.5 g white sugar, formulation 3 (50 g talc, 1 g pepton, 0.5 g CMC, 1 g yeast extract, and 1.5 gwhite sugar and formulation 4 (50 g talc, 1 g pepton, 0.5 g CMC, 1 g yeast extract, 3 mL molasses, 1 gbentonite, 0.75 g calcium carbonate, and 1 g dextrose. The results of the bacterial characterization showed that Bacillus sp AA2 and Bacillus sp MER belongs to Gram positive, produced lipase and protease enzyme, as well as  IAA hormone. N2 fixation is only existed in Bacillussp. AA2 and MSJ isolate. The highest viability was shown on MSJ isolate with 2.5×106 cfu mL-1. in the fourth formulation, whereas Bacillus sp. AA2 and Bacillus sp. MER viability was 1.9×106 cfu mL-1. and 1.2×106 cfu mL-1. , respectively. 

  10. Transcriptional Regulation of Frizzled-1 in Human Osteoblasts by Sp1.

    Directory of Open Access Journals (Sweden)

    Shibing Yu

    Full Text Available The wingless pathway has a powerful influence on bone metabolism and is a therapeutic target in skeletal disorders. Wingless signaling is mediated in part through the Frizzled (FZD receptor family. FZD transcriptional regulation is poorly understood. Herein we tested the hypothesis that Sp1 plays an important role in the transcriptional regulation of FZD1 expression in osteoblasts and osteoblast mineralization. To test this hypothesis, we conducted FZD1 promoter assays in Saos2 cells with and without Sp1 overexpression. We found that Sp1 significantly up-regulates FZD1 promoter activity in Saos2 cells. Chromatin immunoprecipitation (ChIP and electrophoretic mobility shift (EMSA assays identified a novel and functional Sp1 binding site at -44 to -40 from the translation start site in the FZD1 promoter. The Sp1-dependent activation of the FZD1 promoter was abolished by mithramycin A (MMA, an antibiotic affecting both Sp1 binding and Sp1 protein levels in Saos2 cells. Similarly, down-regulation of Sp1 in hFOB cells resulted in less FZD1 expression and lower alkaline phosphatase activity. Moreover, over-expression of Sp1 increased FZD1 expression and Saos2 cell mineralization while MMA decreased Sp1 and FZD1 expression and Saos2 cell mineralization. Knockdown of FZD1 prior to Sp1 overexpression partially abolished Sp1 stimulation of osteoblast differentiation markers. Taken together, our results suggest that Sp1 plays a role in human osteoblast differentiation and mineralization, which is at least partially mediated by Sp1-dependent transactivation of FZD1.

  11. Ecological characterisation of the Colombian entomopathogenic nematode Heterorhabditis sp. SL0708.

    Science.gov (United States)

    Mejia-Torres, M C; Sáenz, A

    2013-05-01

    The entomopathogenic nematode Heterorhabditis sp. SL0708 (Rhabditida: Heterorhabditidae) isolated from soil in Alcalá, Valle del Cauca (Colombia) was characterised ecologically using Galleria mellonella larvae (L) (Pyralidae: Galleriinae) as hosts. The effect of temperature on the viability, infectivity and reproduction, and of moisture on infectivity and storage in liquid were evaluated in infective juveniles (IJs). Significant differences were found in the viability, infectivity and reproduction of the IJs at different temperatures. No nematodes were recovered at 5 °C and 10 °C, and at 35 °C no infectivity was observed. Average daily nematode recovery was best at 25 °C, and survival of the IJs was low in substrates presenting 13% moisture. The optimal storage temperature for Heterorhabditis sp. SL0708 was between 20 °C and 30 °C, keeping its infectivity for up to 8 weeks.

  12. Carbon storage as affected by different site preparation techniques two years after mixed forest stand installation

    Energy Technology Data Exchange (ETDEWEB)

    Fonseca, F.; Figueiredo, T. de; Martins, A.

    2014-06-01

    Aim of study: This study aims at evaluating the impact of site preparation techniques prior to plantation on carbon storage and distribution in a young mixed stand of Pseudotsuga menziesii (PM) and Castanea sativa (CS). Area of study: The experimental field was established near Macedo de Cavaleiros, Northern Portugal, at 700 m elevation, mean annual temperature 12 degree centigrade and mean annual rainfall 678 mm. Material and methods: The experimental layout includes three replicates, where the different treatments corresponding to different tillage intensities were randomly distributed (high, moderate and slight intensity), in plots with an area of 375 m{sup 2} each. Twenty six months after forest stand installation, samples of herbaceous vegetation (0.49 m{sup 2} quadrat), forest species (8 PM and 8 CS) and mineral soil (at 0-5, 5-15, 15-30 and 30-60 cm depth) were collected in 15 randomly selected points in each treatment, processed in laboratory and analyzed for carbon by elemental carbon analyzer. Main results: The results obtained showed that: (i) more than 90% of the total carbon stored in the system is located in the soil, increasing in depth with tillage intensity; (ii) the contribution of herbaceous vegetation and related roots to the carbon storage is very low; (iii) the amount of carbon per tree is higher in CS than in PM; (iv) the global carbon storage was affected by soil tillage generally decreasing with the increase of tillage intensity. Accordingly, carbon storage capacity as affected by the application of different site preparation techniques should be a decision support tool in afforestation schemes. (Author)

  13. Guidelines for interim storage of low level waste

    International Nuclear Information System (INIS)

    Hornibrook, C.; Castagnacci, A.; Clymer, G.; Kelly, J.; Naughton, M.; Saunders, P.; Stoner, P.; Walker, N.; Cazzolli, R.; Dettenmeier, R.; Loucks, L.; Rigsby, M.; Spall, M.; Strum, M.

    1992-12-01

    This report presents an overview of on-site storage of Low Level Waste while providing guidelines for using the complete Interim On-Site Storage of Low Level Waste report series. Overall, this report provides a methodology for planning and implementing on-site storage

  14. Dry storage of Magnox fuel

    International Nuclear Information System (INIS)

    1986-09-01

    This work, commissioned by the CEGB, studies the feasibility of a combination of short-term pond storage and long-term dry storage of Magnox spent fuel as a cheaper alternative to reprocessing. Storage would be either at the reactor site or a central site. Two designs are considered, based on existing design work done by GEC-ESL and NNC; the capsule design developed by NNC and with storage in passive vaults for up to 100 yrs and the GEC-ESL tube design developed at Wylfa for the interim storage of LWR. For the long-term storage of Magnox spent fuel the GEC-ESL tubed vault all-dry storage method is recommended and specifications for this method are given. (U.K.)

  15. The Cigeo project: an industrial storage site for radioactive wastes in deep underground

    International Nuclear Information System (INIS)

    Krieguer, Jean-Marie

    2017-01-01

    In 2006, France has decided to store its high-level and long-lived radioactive wastes, mostly issued from the nuclear industry, in a deep geological underground disposal site. This document presents the Cigeo project, a deep underground disposal site (located in the East of France) for such radioactive wastes, which construction is to be started in 2021 (subject to authorization in 2018). After a brief historical review of the project, started 20 years ago, the document presents the radioactive waste disposal context, the ethical choice of underground storage (in France and elsewhere) for these types of radioactive wastes, the disposal site safety and financing aspects, the progressive development of the underground facilities and, of most importance, its reversibility. In a second part, the various works around the site are presented (transport, buildings, water and power supply, etc.) together with a description of the various radioactive wastes (high and intermediate level and long-lived wastes and their packaging) that will be disposed in the site. The different steps of the project are then reviewed (the initial design and initial construction phases, the pilot industrial phase (expected in 2030), the operating phase, and the ultimate phases that will consist in the definitive closure of the site and its monitoring), followed by an extensive description of the various installations of surface and underground facilities, their architecture and their equipment

  16. Comparison of Dry Gas Seasonal Storage with CO2 Storage and Re-Use Potential

    OpenAIRE

    Killerud, Marie

    2013-01-01

    To make large-scale CO2 storage economic, many groups have proposed using CO2in EOR projects to create value for CO2 storage. However, CO2 EOR projectsgenerally require a large and variable supply of CO2 and consequently may requiretemporary storage of CO2 in geological formations. In order to store CO2 atoffshore sites as a source for CO2 EOR projects, the CO2 needs to be extractedfrom a storage site to a certain extent. Alternatively, CO2 EOR projects maybe developed alongside saline aquife...

  17. Streamlined Approach for Environmental Restoration Plan for Corrective Action Unit 121: Storage Tanks and Miscellaneous Sites, Nevada Test Site, Nevada

    International Nuclear Information System (INIS)

    NSTec Environmental Restoration

    2007-01-01

    This Streamlined Approach for Environmental Restoration (SAFER) Plan identifies the activities required for the closure of Corrective Action Unit (CAU) 121, Storage Tanks and Miscellaneous Sites. CAU 121 is currently listed in Appendix III of the ''Federal Facility Agreement and Consent Order'' (FFACO, 1996) and consists of three Corrective Action Sites (CASs) located in Area 12 of the Nevada Test Site (NTS): CAS 12-01-01, Aboveground Storage Tank; CAS 12-01-02, Aboveground Storage Tank; and CAS 12-22-26, Drums; 2 AST's. CASs 12-01-01 and 12-01-02 are located to the west of the Area 12 Camp, and CAS 12-22-26 is located near the U-12g Tunnel, also known as G-tunnel, in Area 12 (Figure 1). The aboveground storage tanks (ASTs) present at CASs 12-01-01 and 12-01-02 will be removed and disposed of at an appropriate facility. Soil below the ASTs will be sampled to identify whether it has been impacted with chemicals or radioactivity above action levels. If impacted soil above action levels is present, the soil will be excavated and disposed of at an appropriate facility. The CAS 12-22-26 site is composed of two overlapping areas, one where drums had formerly been stored, and the other where an AST was used to dispense diesel for locomotives used at G-tunnel. This area is located above an underground radioactive materials area (URMA), and within an area that may have elevated background radioactivity because of containment breaches during nuclear tests and associated tunnel reentry operations. CAS 12-22-26 does not include the URMA or the elevated background radioactivity. An AST that had previously been used to store liquid magnesium chloride (MgCl) was properly disposed of several years ago, and releases from this tank are not an environmental concern. The diesel AST will be removed and disposed of at an appropriate facility. Soil at the former drum area and the diesel AST area will be sampled to identify whether it has been impacted by releases, from the drums or the

  18. Environmental surveillance results for 1995 for the Hazelwood Interim Storage Site

    International Nuclear Information System (INIS)

    McCague, J.C.

    1996-01-01

    This memorandum presents and interprets analytical results and measurements obtained as part of the 1995 environmental surveillance program for the Hazelwood Interim Storage Site (HISS) under the Formerly Utilized Sites Remedial Action Program (FUSRAP). The discussion provides a comparative analysis of average historical background conditions and applicable regulatory criteria to the 1995 results reported for external gamma radiation and for samples from the media investigated (air, surface water, sediment, groundwater, and stormwater). Results from the 1995 environmental surveillance program at HISS indicate that, with the exception of thorium-230 in streambed sediment, applicable US Department of Energy (DOE) guidelines were not exceeded for any measured parameter or for any dose calculated for potentially exposed members of the general public. In the absence of sediment guidelines, DOE soil guidelines serve as a standard of comparison for data obtained from stream bed sediment; two samples from downstream locations contained concentrations of thorium-230 that exceeded DOE soil guidelines. All stormwater sample results were in compliance with permit-specified limits. Other radioactive materials include radium 226 and natural uranium

  19. Hazelwood Interim Storage Site annual environmental report for calendar year 1991, Hazelwood, Missouri

    International Nuclear Information System (INIS)

    1992-09-01

    This document describes the environmental monitoring program at the Hazelwood Interim Storage Site (HISS) and surrounding area, implementation of the program, and monitoring results for 1991. Environmental monitoring of HISS began in 1984 when the site was assigned to the US Department of Energy (DOE) as part of the decontamination research and development project authorized by Congress under the 1984 Energy and Water Development Appropriations Act. DOE placed responsibility for HISS under the Formerly Utilized Sites Remedial Action Program (FUSRAP), a DOE program to decontaminate or otherwise control sites where residual radioactive materials remain from the early years of the nation's atomic energy program or from commercial operations causing conditions that Congress has authorized DOE to remedy. The environmental monitoring program at HISS includes sampling networks for radon concentrations in air; external gamma radiation exposure; and radium-226, thorium-230, and total uranium concentrations in surface water, sediment, and groundwater. Additionally, several nonradiological parameters are measured in groundwater. Monitoring results are compared with applicable Environmental Protection Agency standards, DOE derived concentration guides (DCGs), dose limits, and other requirements in DOE orders. Environmental standards and DCGs are established to protect public health and the environment

  20. DSND report on radio-ecological monitoring of INBS and management of radioactive waste old storage sites

    International Nuclear Information System (INIS)

    2010-01-01

    In its first part, this report describes the radiological monitoring of secret base nuclear installations (INBS): applicable arrangements and actors in terms of transparency and information on nuclear safety, regulatory arrangements related to surveillance of underground and surface water quality, assessment of the application of regulatory arrangements, arrangements in terms of public information, and actions of the ASND. The second part describes the management of nuclear waste old storage sites: INBS coming under the ministry of defence (air force sites, military harbors), INBS coming under the minister in charge of energy

  1. Overexpression of transcription factor Sp1 leads to gene expression perturbations and cell cycle inhibition.

    Directory of Open Access Journals (Sweden)

    Emmanuelle Deniaud

    Full Text Available BACKGROUND: The ubiquitous transcription factor Sp1 regulates the expression of a vast number of genes involved in many cellular functions ranging from differentiation to proliferation and apoptosis. Sp1 expression levels show a dramatic increase during transformation and this could play a critical role for tumour development or maintenance. Although Sp1 deregulation might be beneficial for tumour cells, its overexpression induces apoptosis of untransformed cells. Here we further characterised the functional and transcriptional responses of untransformed cells following Sp1 overexpression. METHODOLOGY AND PRINCIPAL FINDINGS: We made use of wild-type and DNA-binding-deficient Sp1 to demonstrate that the induction of apoptosis by Sp1 is dependent on its capacity to bind DNA. Genome-wide expression profiling identified genes involved in cancer, cell death and cell cycle as being enriched among differentially expressed genes following Sp1 overexpression. In silico search to determine the presence of Sp1 binding sites in the promoter region of modulated genes was conducted. Genes that contained Sp1 binding sites in their promoters were enriched among down-regulated genes. The endogenous sp1 gene is one of the most down-regulated suggesting a negative feedback loop induced by overexpressed Sp1. In contrast, genes containing Sp1 binding sites in their promoters were not enriched among up-regulated genes. These results suggest that the transcriptional response involves both direct Sp1-driven transcription and indirect mechanisms. Finally, we show that Sp1 overexpression led to a modified expression of G1/S transition regulatory genes such as the down-regulation of cyclin D2 and the up-regulation of cyclin G2 and cdkn2c/p18 expression. The biological significance of these modifications was confirmed by showing that the cells accumulated in the G1 phase of the cell cycle before the onset of apoptosis. CONCLUSION: This study shows that the binding to DNA

  2. Structural Analysis of Planar sp3 and sp2 Films: Diamond-Like Carbon and Graphene Overlayers

    KAUST Repository

    Mansour, Ahmed

    2011-07-07

    The special electronic configuration of carbon enables the existence of wide ranging allotropes taking all possible dimensionalities. The allotropes of carbon are characterized by the type of hybridized bonding forming its structure, ranging from pure sp2 as in graphene, carbon nanotubes and fullerenes, to pure sp3 as in diamond. Amorphous and diamond-like carbon consists of a mixture of both hybridizations. This variation in hybridization in carbon materials enables a wide spectrum of properties, ranging from high bulk mechanical hardness, tribological properties and chemical inertness made possible by moving towards pure sp3 bonding to the extraordinary electrical conductivity, optical properties and in-plane mechanical strength resulting from pure sp2 bonding. Two allotropes at the extremes of this spectrum, diamond like carbon (DLC) and graphene, are investigated in this thesis; the former is investigated as a protective coating in hard drive applications, while the latter is investigated in the context of chemically derived graphene as material for transparent conducting electrode applications. DLC thin films are a main component in computer hard drives, acting as a protective coating against corrosion and mechanical wear of the magnetic layer and read-write head. The thickness of DLC films greatly affects the storage density in such devices, as larger separation between the read/write head and the magnetic layer decreases the storage density. A targeted DLC thickness of 2 nm would increase the storage density towards 1 Tbits/inch2. However, difficulty achieving continuous films at such thicknesses by commonly used sputtering methods challenges the industry to investigate alternative methods. Filtered cathodic vacuum arc (FCVA) has been proposed as an efficient technique to provide continuous, smooth and ultra-thin DLC films. We investigate the influence of deposition angle, deposition time, and substrate biasing to define the optimum process window to obtain

  3. Control of Branchionus sp. and Amoeba sp. in cultures of Arthrospira sp. Control de Branchionus sp. y Amoeba sp. en cultivos de Arthrospira sp.

    Directory of Open Access Journals (Sweden)

    Carlos Méndez

    2012-09-01

    Full Text Available Cultivation of cyanobacterium Arthrospira sp. has been developed in many countries for the production of proteins, pigments and other compounds. Outdoor mass cultures are often affected by biological contamination, drastically reducing productivity as far as bringing death. This study evaluates the control of Branchionus sp. and Amoeba sp. with two chemical compounds: urea (U and ammonium bicarbonate (AB, in laboratory conditions and outdoor mass culture of Arthrospira sp. The lethal concentration 100 (LC100 at 24 h for Branchionus sp. and Amoeba sp. determined was of 60-80 mg L-1 (U and 100-150 mg L-1 (AB. The average effective inhibition concentration for 50% of the population (IC50 in Arthrospira sp., after 72 h, was 80 mg L-1 (U and 150 mg L-1 (AB. The application of doses of 60 mg L-1 (U or 100 mg L-1 (AB in the outdoor mass culture of this contaminated microalga, completely inhibited grazing and did not affect the growth of Arthrospira sp. but rather promoted rapid recovery of algal density at levels prior to infestation. These compounds provided an economical and effective control of predators in cultures of Arthrospira sp.El cultivo de la cianobacteria Arthrospira sp. ha sido desarrollado en muchos países para la obtención de proteínas, pigmentos y otros compuestos. Cultivo que a nivel industrial se ve afectado frecuentemente por contaminación biológica, reduciendo drásticamente la productividad hasta causar la muerte. Este estudio evalúa el control de Branchionus sp. y de Amoeba sp. con dos compuestos químicos, la urea (U y bicarbonato de amonio (AB en cultivos de Arthrospira sp. La concentración letal 100 (LC100 determinada a las 24 h para Branchionus sp. y Amoeba sp. fue de 60-80 mg L-1 (U y 100-150 mg L-1 (AB. La concentración media de inhibición efectiva, después de 72 h, para el 50% de la población (IC50 en Arthrospira fue de 80 mg L-1 (U y 150 mg L-1 (AB. La aplicación de dosis de 60 mg L-1 (U ó 100 mg L-1 (AB en

  4. Site characterization data for Solid Waste Storage Area 6

    International Nuclear Information System (INIS)

    Boegly, W.J. Jr.

    1984-12-01

    Currently, the only operating shallow land burial site for low-level radioactive waste at the Oak Ridge National Laboratory (ORNL) is Solid Waste Storage Area No. 6 (SWSA-6). In 1984, the US Department of Energy (DOE) issued Order 5820.2, Radioactive Waste Management, which establishes policies and guidelines by which DOE manages its radioactive waste, waste by-products, and radioactively contaminated surplus facilities. The ORNL Operations Division has given high priority to characterization of SWSA-6 because of the need for continued operation under DOE 5820.2. The purpose of this report is to compile existing information on the geologic and hydrologic conditions in SWSA-6 for use in further studies related to assessing compliance with 5820.2. Burial operations in SWSA-6 began in 1969 on a limited scale, and full operation was initiated in 1973. Since that time, ca. 29,100 m 3 of low-level waste containing ca. 251,000 Ci of activity has been buried in SWSA-6. No transuranic waste has been disposed of in SWSA-6; rather this waste is retrievably stored in SWSA-5. Estimates of the remaining usable space in SWSA-6 vary; however, in 1982 sufficient useful land was reported for about 10 more years of operation. Analysis of the information available on SWSA-6 indicates that more information is required to evaluate the surface water hydrology, the geology at depths below the burial trenches, and the nature and extent of soils within the site. Also, a monitoring network will be required to allow detection of potential contaminant movement in groundwater. Although these are the most obvious needs, a number of specific measurements must be made to evaluate the spatial heterogeneity of the site and to provide background information for geohydrological modeling. Some indication of the nature of these measurements is included

  5. Storage pool water condition of multipurpose compact 60Co irradiator of IPEN-CNEN/SP

    International Nuclear Information System (INIS)

    Kodama, Yasko; Rela, Paulo R.

    2008-01-01

    A new type compact gamma irradiator was developed and installed at IPEN-CNEN/SP, it is classified as category IV irradiator according to International Atomic Energy Agency-IAEA. The originality of its design remains on the rotating concrete door, which integrates the shielding system with the product handling system, permitting the input and output of the products in a continuous way, without the necessity to lower the sources and open the irradiator chamber to change the batch. The licensed capacity of this irradiator is 37 P Bq (1 MCi) and the water pool liner, manufactured in stainless steel, has 7.0 m deep and 2.7 m diameter. A sealed radiation source may be defined as a quantity of radioactive material sealed within non-radioactive material, which the confining barrier is intended to prevent leakage or escape of the radioactive material under normal handling conditions and also under foreseeable mishaps. The use of cobalt-60 radiation sources in a wet storage environment requires care in the control of that environment to avoid the potential for deterioration of the stainless steel. In the literature, the tests performed demonstrated that stainless steel had excellent performance under controlled environment conditions. The inspection includes assessing the condition of storage pool water and measuring the pool water conductivity. The demineralized water normally used in storage pools is usually an effective and secure medium in which to store stainless steel. However, there are certain constituents and contaminants in the water which can affect this behaviour. For instance, the pH has a small but definite effect on the tendency for pitting corrosion. Nevertheless, there is also evidence that both strongly alkaline and strongly acid environments can encourage pitting corrosion. In general, an around neutral pH is recommended. The conductivity is used as a measure of the extent to which ionic species are present in the pool water. International recommendations

  6. Model environmental assessment for a property-cleanup/interim-storage remedial action at a formerly utilized site

    International Nuclear Information System (INIS)

    Merry-Libby, P.

    1982-07-01

    This document has been prepared as a model for the preparation of an Environmental Assessment (EA) for a property-cleanup/interim-storage type of remedial action under the Formerly Utilized Sites Remedial Action Program (FUSRAP) of the US Department of Energy (DOE). For major federal actions significantly affecting the quality of the human environment, an Environmental Impact Statement (EIS) must be prepared to aid DOE in making its decision. However, when it is not clear that an action is major and the impacts are significant, an EA may be prepared to determine whether to prepare an EIS or a finding of no significant impact (FONSI). If it is likely that an action may be major and the impacts significant, it is usually more cost-effective and timely to directly prepare an EIS. If it is likely that a FONSI can be reached after some environmental assessment, as DOE believes may be the case for most property-cleanup/interim-storage remedial actions, preparation of site-specific EAs is an effective means of compliance with NEPA

  7. Niagara Falls Storage Site annual environmental report for calendar year 1991, Lewiston, New York

    International Nuclear Information System (INIS)

    1992-09-01

    This document describes the environmental monitoring program at the Niagara Falls Storage Site (NFSS) and surrounding area, implementation of the program, and monitoring results for 1991. Environmental monitoring at NFSS began in 1981. The site is owned by the US Department of Energy (DOE) and is assigned to the DOE Formerly Utilized Sites Remedial Action Program (FUSRAP). FUSRAP is a program to decontaminate or otherwise control sites where residual radioactive materials remain from the early years of the nation's atomic energy program or from commercial operations causing conditions that Congress has authorized DOE to remedy. The environmental monitoring program at NFSS includes sampling networks for radon concentrations in air; external gamma radiation exposure; and total uranium and radium-226 concentrations in surface water, sediments, and groundwater. Additionally, several nonradiological parameters including seven metals are routinely measured in groundwater. Monitoring results are compared with applicable Environmental Protection Agency (EPA) standards, DOE derived concentration guides (DCGs), dose limits, and other requirements in DOE orders. Environmental standards are established to protect public health and the environment

  8. Public storage for the Open Science Grid

    International Nuclear Information System (INIS)

    Levshina, T; Guru, A

    2014-01-01

    The Open Science Grid infrastructure doesn't provide efficient means to manage public storage offered by participating sites. A Virtual Organization that relies on opportunistic storage has difficulties finding appropriate storage, verifying its availability, and monitoring its utilization. The involvement of the production manager, site administrators and VO support personnel is required to allocate or rescind storage space. One of the main requirements for Public Storage implementation is that it should use SRM or GridFTP protocols to access the Storage Elements provided by the OSG Sites and not put any additional burden on sites. By policy, no new services related to Public Storage can be installed and run on OSG sites. Opportunistic users also have difficulties in accessing the OSG Storage Elements during the execution of jobs. A typical users' data management workflow includes pre-staging common data on sites before a job's execution, then storing for a subsequent download to a local institution the output data produced by a job on a worker node. When the amount of data is significant, the only means to temporarily store the data is to upload it to one of the Storage Elements. In order to do that, a user's job should be aware of the storage location, availability, and free space. After a successful data upload, users must somehow keep track of the data's location for future access. In this presentation we propose solutions for storage management and data handling issues in the OSG. We are investigating the feasibility of using the integrated Rule-Oriented Data System developed at RENCI as a front-end service to the OSG SEs. The current architecture, state of deployment and performance test results will be discussed. We will also provide examples of current usage of the system by beta-users.

  9. Public storage for the Open Science Grid

    Science.gov (United States)

    Levshina, T.; Guru, A.

    2014-06-01

    The Open Science Grid infrastructure doesn't provide efficient means to manage public storage offered by participating sites. A Virtual Organization that relies on opportunistic storage has difficulties finding appropriate storage, verifying its availability, and monitoring its utilization. The involvement of the production manager, site administrators and VO support personnel is required to allocate or rescind storage space. One of the main requirements for Public Storage implementation is that it should use SRM or GridFTP protocols to access the Storage Elements provided by the OSG Sites and not put any additional burden on sites. By policy, no new services related to Public Storage can be installed and run on OSG sites. Opportunistic users also have difficulties in accessing the OSG Storage Elements during the execution of jobs. A typical users' data management workflow includes pre-staging common data on sites before a job's execution, then storing for a subsequent download to a local institution the output data produced by a job on a worker node. When the amount of data is significant, the only means to temporarily store the data is to upload it to one of the Storage Elements. In order to do that, a user's job should be aware of the storage location, availability, and free space. After a successful data upload, users must somehow keep track of the data's location for future access. In this presentation we propose solutions for storage management and data handling issues in the OSG. We are investigating the feasibility of using the integrated Rule-Oriented Data System developed at RENCI as a front-end service to the OSG SEs. The current architecture, state of deployment and performance test results will be discussed. We will also provide examples of current usage of the system by beta-users.

  10. Ground deformation monitoring using RADARSAT-2 DInSAR-MSBAS at the Aquistore CO2 storage site in Saskatchewan (Canada)

    OpenAIRE

    Czarnogorska, M.; Samsonov, S.; White, D.

    2014-01-01

    The research objectives of the Aquistore CO2 storage project are to design, adapt, and test non-seismic monitoring methods for measurement, and verification of CO2 storage, and to integrate data to determine subsurface fluid distributions, pressure changes and associated surface deformation. Aquistore site is located near Estevan in Southern Saskatchewan on the South flank of the Souris River and west of the Boundary Dam Power Station and the historical part of Estevan coal mine in s...

  11. Spent fuel handling system for a geologic storage test at the Nevada Test Site

    International Nuclear Information System (INIS)

    Duncan, J.E.; House, P.A.; Wright, G.W.

    1980-01-01

    The Lawrence Livermore Laboratory is conducting a test of the geologic storage of encapsulated spent commercial reactor fuel assemblies in a granitic rock at the Nevada Test Site. The test, known as the Spent Fuel Test-Climax (SFT-C), is sponsored by the US Department of Energy, Nevada Operations Office. Eleven pressurized-water-reactor spent fuel assemblies are stored retrievably for three to five years in a linear array in the Climax stock at a depth of 420 m

  12. Safety Assessment Document for the Spent Reactor Fuel Geologic Storage Test in the Climax Granite Stock at the Nevada Test site

    International Nuclear Information System (INIS)

    1980-01-01

    The objective of the Spent Fuel Geologic Storage Test in the Climax Granite Stock is to evaluate the response of a granitic rock mass to the underground storage of encapsulated spent reactor fuel in a geometry that simulates a module of a large-scale geologic repository. This document reports an assessment of the safety of conducting this test. Descriptions are provided of the geography, meteorology, hydrology, geology, and seismology of the Climax Site; the effects of postulated natural phenomena and other activities at the nevada Test Site on the safety of the test; and the design and operation of the test facility and associated equipment. Evaluations are made of both the radiological and nonradiological impacts of normal operations, abnormal operations, and postulated accidents. It is concluded that conduct of the spent fuel test at the Climax Site will not result in any undue risk to the public, property, environment, or site employees

  13. Polyvalent intermediate storage: first step in the cleaning of the Cogema Marcoule site

    Energy Technology Data Exchange (ETDEWEB)

    Cabe, J.M. [Cogema, 30 - Marcoule (France); Seurat, Ph. [Societe Generale pour les Techniques Nouvelles, SGN, 30 - Bagnols sur Ceze (France)

    1998-07-01

    Cleaning operations of Marcoule site consist, beside the permanent stop and the dismantling of the Cogema 's nuclear fuel reprocessing plant U.P.1., in assuring waste retaking and conditioning not dispatched to C.S.M., for the moment stored on production or pretreatment facilities, under a stabilized form. The Polyvalent Intermediate Storage (E.I.P.) receives preconditioned waste before treatment and reconditioning, receives storing over about 50 years conditioned waste before a permanent repository. Its main function is to wait for the construction of long term repository. (N.C.)

  14. Polyvalent intermediate storage: first step in the cleaning of the Cogema Marcoule site

    International Nuclear Information System (INIS)

    Cabe, J.M.; Seurat, Ph.

    1998-01-01

    Cleaning operations of Marcoule site consist, beside the permanent stop and the dismantling of the Cogema 's nuclear fuel reprocessing plant U.P.1., in assuring waste retaking and conditioning not dispatched to C.S.M., for the moment stored on production or pretreatment facilities, under a stabilized form. The Polyvalent Intermediate Storage (E.I.P.) receives preconditioned waste before treatment and reconditioning, receives storing over about 50 years conditioned waste before a permanent repository. Its main function is to wait for the construction of long term repository. (N.C.)

  15. Niagara falls storage site: Annual site environmental report, Lewiston, New York, Calendar Year 1988: Surplus Facilities Management Program (SFMP)

    International Nuclear Information System (INIS)

    1989-04-01

    The monitoring program at the Niagara Falls Storage Site (NFSS) measures radon concentrations in air; external gamma radiation levels; and uranium and radium concentrations in surface water, groundwater, and sediment. To verify that the site is in compliance with the DOE radiation protection standard and to assess its potential effect on public health, the radiation dose was calculated for a hypothetical maximally exposed individual. Based on the conservative scenario described in this report, this hypothetical individual receives an annual external exposure approximately equivalent to 6 percent of the DOE radiation protection standard of 100 mrem/yr. This exposure is less than a person receives during two round-trip flights from New York to Los Angeles (because of the greater amounts of cosmic radiation at higher altitudes). The cumulative dose to the population within an 80-km (50-mi) radius of the NFSS that results from radioactive materials present at the site is indistinguishable from the dose that the same population receives from naturally occurring radioactive sources. Results of the 1988 monitoring show that the NFSS is in compliance with applicable DOE radiation protection standards. 17 refs., 31 figs., 20 tabs

  16. Geochemical information for sites contaminated with low-level radioactive wastes: II. St. Louis Airport Storage Site

    International Nuclear Information System (INIS)

    Seeley, F.G.; Kelmers, A.D.

    1985-01-01

    The St. Louis Airport Storage Site (SLASS) became radioactively contaminated as a result of wastes that were being stored from operations to recover uranium from pitchblende ores in the 1940s and 1950s. The US Department of Energy is considering various remedial action options for the SLASS under the Formerly Utilized Site Remedial Action Program (FUSRAP). This report describes the results of geochemical investigations, carried out to support the FUSRAP activities and to aid in quantifying various remedial action options. Soil and groundwater samples from the site were characterized, and sorption ratios for uranium and radium and apparent concentration limit values for uranium were measured in soil/groundwater systems by batch contact methodology. The uranium and radium concentrations in soil samples were significantly above background near the old contaminated surface horizon (now at the 0.3 - to 0.9 - m depth); the maximum values were 1566 μg/g and 101 pCi/g, respectively. Below about the 6 - m depth, the concentrations appeared to be typical of those naturally present in soils of this area (3.8 +- 1.2 μg/g and 3.1 +- 0.6 pCi/g). Uranium sorption ratios showed stratigraphic trends but were generally moderate to high (100 to 1000 L/kg). The sorption isotherm suggested an apparent uranium concentration limit of about 200 mg/L. This relatively high solubility can probably be correlated with the carbonate content of the soil/groundwater systems. The lower sorption ratio values obtained from the sorption isotherm may have resulted from changes in the experimental procedure or the groundwater used. The SLASS appears to exhibit generally favorable behavior for the retardation of uranium solubilized from waste in the site. Parametric tests were conducted to estimate the sensitivity of uranium sorption and solubility to the pH and carbonate content of the system

  17. Enkapsulasi B. bassiana menggunakan maizena dan daya infeksinya terhadap larva Aedes aegypti, Anopheles sp., Culex sp.

    Directory of Open Access Journals (Sweden)

    Mutiara Widawati

    2015-12-01

    Full Text Available Abstract. Encapsulation formulae of mycoinsecticide have to be able to maintain fungus viability and pathogenicity. This mycoinsecticide was developed as an alternative way to control mosquito borne disease. The aim of this study was to encapsulate Beauveria bassiana as viable storage and have the capability to kill larvae of Aedes aegypti, Anopheles sp. and Culex sp. Mosquito larvae obtained from laboratory reared at health research laboratory; Loka Litbang P2B2 Ciamis. The treatments made in this study were the formu-lation of cornstarch and controls for comparison. This study showed potential formulation of cornstarch encapsulation as a biolarvacidal. Cornstarch formulations proven to be succeed in maintaining fungus viability, however, the pathogenicity of the microcapsule still not effective to kill Aedes, Culex and Anopheles larvae. Keywords: encapsulation, Beauveria bassiana, Ae.aegypti, Anopheles sp., Culex sp. Abstrak. Pembuatan formula bioinsektisida yang optimal sebagai salah satu alternatif untuk pengen-dalian nyamuk vektor perlu di kembangkan. Sediaan mikoinsektisida yang dibuat harus dapat memper-tahankan viabilitas jamur B. bassiana sehingga masih efektif pada saat penggunaannya. Salah satu cara yang digunakan untuk menjaga kestabilan sediaan mikoinsektisida yang berdampak langsung pada via-bilitas jamur adalah dengan menerapkan metode enkapsulasi. Penelitian ini bertujuan untuk meng-hasilkan sediaan mikokapsul dari Beauvaria bassiana melalui proses enkapsulasi menggunakan maizena yang memiliki kapabilitas tinggi sebagai penyimpan B. bassiana dan efektif dalam membunuh larva dan telur Aedes aegypti, Anopheles sp. dan Culex sp. Semua larva uji berasal dari insektarium laboratorium penelitian kesehatan Loka litbang P2B2 Ciamis. Pembuatan enkapsulasi dimulai dengan kultur dan pema-nenan B. bassiana, uji viabilitas, proses enkapsulasi serta uji larvasida di laboratorium. Uji dilakukan dengan satu perlakuan dan satu kontrol untuk

  18. Signal peptide discrimination and cleavage site identification using SVM and NN.

    Science.gov (United States)

    Kazemian, H B; Yusuf, S A; White, K

    2014-02-01

    About 15% of all proteins in a genome contain a signal peptide (SP) sequence, at the N-terminus, that targets the protein to intracellular secretory pathways. Once the protein is targeted correctly in the cell, the SP is cleaved, releasing the mature protein. Accurate prediction of the presence of these short amino-acid SP chains is crucial for modelling the topology of membrane proteins, since SP sequences can be confused with transmembrane domains due to similar composition of hydrophobic amino acids. This paper presents a cascaded Support Vector Machine (SVM)-Neural Network (NN) classification methodology for SP discrimination and cleavage site identification. The proposed method utilises a dual phase classification approach using SVM as a primary classifier to discriminate SP sequences from Non-SP. The methodology further employs NNs to predict the most suitable cleavage site candidates. In phase one, a SVM classification utilises hydrophobic propensities as a primary feature vector extraction using symmetric sliding window amino-acid sequence analysis for discrimination of SP and Non-SP. In phase two, a NN classification uses asymmetric sliding window sequence analysis for prediction of cleavage site identification. The proposed SVM-NN method was tested using Uni-Prot non-redundant datasets of eukaryotic and prokaryotic proteins with SP and Non-SP N-termini. Computer simulation results demonstrate an overall accuracy of 0.90 for SP and Non-SP discrimination based on Matthews Correlation Coefficient (MCC) tests using SVM. For SP cleavage site prediction, the overall accuracy is 91.5% based on cross-validation tests using the novel SVM-NN model. © 2013 Published by Elsevier Ltd.

  19. Final environmental assessment for the U.S. Department of Energy, Oak Ridge Operations receipt and storage of uranium materials from the Fernald Environmental Management Project site

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-06-01

    Through a series of material transfers and sales agreements over the past 6 to 8 years, the Fernald Environmental Management Project (FEMP) has reduced its nuclear material inventory from 14,500 to approximately 6,800 metric tons of uranium (MTU). This effort is part of the US Department of energy`s (DOE`s) decision to change the mission of the FEMP site; it is currently shut down and the site is being remediated. This EA focuses on the receipt and storage of uranium materials at various DOE-ORO sites. The packaging and transportation of FEMP uranium material has been evaluated in previous NEPA and other environmental evaluations. A summary of these evaluation efforts is included as Appendix A. The material would be packaged in US Department of Transportation-approved shipping containers and removed from the FEMP site and transported to another site for storage. The Ohio Field Office will assume responsibility for environmental analyses and documentation for packaging and transport of the material as part of the remediation of the site, and ORO is preparing this EA for receipt and storage at one or more sites.

  20. Final environmental assessment for the U.S. Department of Energy, Oak Ridge Operations receipt and storage of uranium materials from the Fernald Environmental Management Project site

    International Nuclear Information System (INIS)

    1999-01-01

    Through a series of material transfers and sales agreements over the past 6 to 8 years, the Fernald Environmental Management Project (FEMP) has reduced its nuclear material inventory from 14,500 to approximately 6,800 metric tons of uranium (MTU). This effort is part of the US Department of energy's (DOE's) decision to change the mission of the FEMP site; it is currently shut down and the site is being remediated. This EA focuses on the receipt and storage of uranium materials at various DOE-ORO sites. The packaging and transportation of FEMP uranium material has been evaluated in previous NEPA and other environmental evaluations. A summary of these evaluation efforts is included as Appendix A. The material would be packaged in US Department of Transportation-approved shipping containers and removed from the FEMP site and transported to another site for storage. The Ohio Field Office will assume responsibility for environmental analyses and documentation for packaging and transport of the material as part of the remediation of the site, and ORO is preparing this EA for receipt and storage at one or more sites

  1. Data Centre Infrastructure & Data Storage @ Facebook

    CERN Multimedia

    CERN. Geneva; Garson, Matt; Kauffman, Mike

    2018-01-01

    Several speakers from the Facebook company will present their take on the infrastructure of their Data Center and Storage facilities, as follows: 10:00 - Facebook Data Center Infrastructure, by Delfina Eberly, Mike Kauffman and Veerendra Mulay Insight into how Facebook thinks about data center design, including electrical and cooling systems, and the technology and tooling used to manage data centers. 11:00 - Storage at Facebook, by Matt Garson An overview of Facebook infrastructure, focusing on different storage systems, in particular photo/video storage and storage for data analytics. About the speakers Mike Kauffman, Director, Data Center Site Engineering Delfina Eberly, Infrastructure, Site Services Matt Garson, Storage at Facebook Veerendra Mulay, Infrastructure

  2. On-site storage of high level nuclear waste: Attitudes and perceptions of local residents

    International Nuclear Information System (INIS)

    Bassett, G.W. Jr.; Jenkins-Smith, H.C.; Silva, C.

    1996-01-01

    No public policy issue has been as difficult as high-level nuclear waste. Debates continue regarding Yucca Mountain as a disposal site, and - more generally - the appropriateness of geologic disposal and the need to act quickly. Previous research has focused on possible social, political, and economic consequences of a facility in Nevada. Impacts have been predicted to be potentially large and to emanate mainly from stigmatization of the region due to increased perceptions of risk. Analogous impacts from leaving waste at power plants have been either ignored or assumed to be negligible. This paper presents survey results on attitudes of residents in three countries where nuclear waste is currently stored. Topics include perceived risk, knowledge of nuclear waste and radiation, and impacts on jobs, tourism, and housing values from leaving waste on site. Results are similar to what has been reported for Nevada; the public is concerned about possible adverse effects from on-site storage of waste. 24 refs., 7 figs., 5 tabs

  3. On-site storage of high level nuclear waste: attitudes and perceptions of local residents.

    Science.gov (United States)

    Bassett, G W; Jenkins-Smith, H C; Silva, C

    1996-06-01

    No public policy issue has been as difficult as high-level nuclear waste. Debates continue regarding Yucca Mountain as a disposal site, and-more generally-the appropriateness of geologic disposal and the need to act quickly. Previous research has focused on possible social, political, and economic consequences of a facility in Nevada. Impacts have been predicted to be potentially large and to emanate mainly from stigmatization of the region due to increased perceptions of risk. Analogous impacts from leaving waste at power plants have been either ignored or assumed to be negligible. This paper presents survey results on attitudes of residents in three counties where nuclear waste is currently stored. Topics include perceived risk, knowledge of nuclear waste and radiation, and impacts on jobs, tourism, and housing values from leaving waste on site. Results are similar to what has been reported for Nevada; the public is concerned about possible adverse effects from on-site storage of waste.

  4. Managing the process for storage and disposal of immobilized high- and low-level tank waste at the Hanford Site

    International Nuclear Information System (INIS)

    Murkowski, R.J.

    1998-01-01

    Lockheed Martin Hanford Corporation (LMHC) is one of six subcontractors under Fluor Daniel Hanford, Inc., the Management and Integration contractor for the Project Hanford Management Contract working for the US Department of Energy. One of LMHC's responsibilities is to prepare storage and disposal facilities to receive immobilized high and low-level tank waste by June of 2002. The immobilized materials are to be produced by one or more vendors working under a privatization contract. The immobilized low-activity waste is to be permanently disposed of at the Hanford Site while the immobilized high-level waste is to be stored at the Hanford Site while awaiting shipment to the offsite repository. Figure 1 is an overview of the entire cleanup mission with the disposal portion of the mission. Figure 2 is a representation of major activities required to complete the storage and disposal mission. The challenge for the LNIHC team is to understand and plan for accepting materials that are described in the Request for Proposal. Private companies will submit bids based on the Request for Proposal and other Department of Energy requirements. LMHC, however, must maintain sufficient flexibility to accept modifications that may occur during the privatization bid/award process that is expected to be completed by May 1998. Fundamental to this planning is to minimize the risks of stand-by costs if storage and disposal facilities are not available to receive the immobilized waste. LMHC has followed a rigorous process for the identification of the functions and requirements of the storage/disposal facilities. A set of alternatives to meet these functions and requirements were identified and evaluated. The alternatives selected were (1) to modify four vaults for disposal of immobilized low-activity waste, and (2) to retrofit a portion of the Canister Storage Building for storage of immobilized high-level waste

  5. Structure of a highly acidic β-lactamase from the moderate halophile Chromohalobacter sp. 560 and the discovery of a Cs{sup +}-selective binding site

    Energy Technology Data Exchange (ETDEWEB)

    Arai, Shigeki; Yonezawa, Yasushi; Okazaki, Nobuo; Matsumoto, Fumiko; Shibazaki, Chie; Shimizu, Rumi; Yamada, Mitsugu; Adachi, Motoyasu; Tamada, Taro [Japan Atomic Energy Agency, 2-4 Shirakata-shirane, Tokai, Ibaraki 319-1195 (Japan); Kawamoto, Masahide [Kyushu Synchrotron Light Research Center, 8-7 Yayoigaoka, Tosu, Saga 841-0005 (Japan); Tokunaga, Hiroko; Ishibashi, Matsujiro [Faculty of Agriculture, Kagoshima University, 1-21-24 Korimoto, Kagoshima 890-0065 (Japan); Blaber, Michael [Japan Atomic Energy Agency, 2-4 Shirakata-shirane, Tokai, Ibaraki 319-1195 (Japan); Florida State University, 1115 West Call Street, Tallahassee, FL 32306-4300 (United States); Tokunaga, Masao [Faculty of Agriculture, Kagoshima University, 1-21-24 Korimoto, Kagoshima 890-0065 (Japan); Kuroki, Ryota, E-mail: kuroki.ryota@jaea.go.jp [Japan Atomic Energy Agency, 2-4 Shirakata-shirane, Tokai, Ibaraki 319-1195 (Japan)

    2015-03-01

    The tertiary structure of a β-lactamase derived from the halobacterium Chromohalobacter sp. 560 (HaBLA) was determined by X-ray crystallography. Three unique Sr{sup 2+}-binding sites and one Cs{sup +}-binding site were discovered in the HaBLA molecule. Environmentally friendly absorbents are needed for Sr{sup 2+} and Cs{sup +}, as the removal of the radioactive Sr{sup 2+} and Cs{sup +} that has leaked from the Fukushima Nuclear Power Plant is one of the most important problems in Japan. Halophilic proteins are known to have many acidic residues on their surface that can provide specific binding sites for metal ions such as Cs{sup +} or Sr{sup 2+}. The crystal structure of a halophilic β-lactamase from Chromohalobacter sp. 560 (HaBLA) was determined to resolutions of between 1.8 and 2.9 Å in space group P3{sub 1} using X-ray crystallography. Moreover, the locations of bound Sr{sup 2+} and Cs{sup +} ions were identified by anomalous X-ray diffraction. The location of one Cs{sup +}-specific binding site was identified in HaBLA even in the presence of a ninefold molar excess of Na{sup +} (90 mM Na{sup +}/10 mM Cs{sup +}). From an activity assay using isothermal titration calorimetry, the bound Sr{sup 2+} and Cs{sup +} ions do not significantly affect the enzymatic function of HaBLA. The observation of a selective and high-affinity Cs{sup +}-binding site provides important information that is useful for the design of artificial Cs{sup +}-binding sites that may be useful in the bioremediation of radioactive isotopes.

  6. Revised corrective action plan for underground storage tank 2331-U at the Building 9201-1 Site

    International Nuclear Information System (INIS)

    Bohrman, D.E.; Ingram, E.M.

    1993-09-01

    This document represents the Corrective Action Plan for underground storage tank (UST) 2331-U, previously located at Building 9201-1, Oak Ridge Y-12 Plant, Oak Ridge, Tennessee. Tank 2331-U, a 560-gallon UST, was removed on December 14, 1988. This document presents a comprehensive summary of all environmental assessment investigations conducted at the Building 9201-1 Site and the corrective action measures proposed for remediation of subsurface petroleum product contamination identified at the site. This document is written in accordance with the regulatory requirements of the Tennessee Department of Environment and Conservation (TDEC) Rule 1200-1-15-.06(7)

  7. Pengendalian Hayati Penyakit Layu Fusarium Pisang (Fusarium oxysporum f.sp. cubense dengan Trichoderma sp.

    Directory of Open Access Journals (Sweden)

    Albertus Sudirman

    2011-07-01

    Full Text Available The aim of this research was to study the inhibiting ability of Trichoderma sp. to control fusarium wilt of banana in greenhouse condition. The experiments consisted of the antagonism test between Trichoderma sp. and Fusarium oxysporum f.sp. cubense (Foc in vitro using dual culture method and glass house experiment which was arranged in 3×3 Factorial Complete Randomized Design. First factor of the latter experiment was the dose of Trichoderma sp. culture (0, 25, and 50 g per polybag, second factor was time of Trichoderma culture application (2 weeks before Foc inoculation, at same time with Foc inoculation and 2 weeks after Foc inoculation. Trichoderma sp. was cultured in mixed rice brand and chaff medium. The disease intensity was observed with scoring system of wilting leaves (0–4. The results showed that Trichoderma sp. was antagonistic against Foc in vitro and inhibited 86% of Foc colony development. Mechanism of antagonism between Trichoderma sp. and Foc was hyperparasitism. Trichoderma hyphae coiled around Foc hyphae. Lysis of Foc hyphae was occurred at the attached site of Trichoderma hyphae on Foc hyphae. Added banana seedling with Trichoderma sp. Culture reduced disease intensity of Fusarium wilt. Suggested dose of Trichoderma culture application in glass house was 25 g/polybag, given at the same time with Foc inoculation. Penelitian ini bertujuan untuk mengetahui kemampuan Trichoderma sp. untuk pengendalian penyakit layu fusarium pisang di rumah kaca. Penelitian meliputi pengujian daya hambat Fusarium oxysporum f.sp. cubense (Foc in vitro dan kemampuan menekan intensitas penyakit di rumah kaca. Penelitian in vitro meliputi uji antagonisme dan mekanismenya yang dilakukan secara dual culture. Uji pengaruh Trichoderma sp. terhadap penyakit layu Fusarium dilakukan di rumah kaca dengan Rancangan Acak Lengkap Faktorial. Faktor pertama adalah dosis biakan Trichoderma sp., dengan tiga aras (0, 25, 50 g/per bibit dalam polibag. Faktor kedua

  8. Cloning single wall carbon nanotubes for hydrogen storage

    Energy Technology Data Exchange (ETDEWEB)

    Tour, James M [Rice Univ., Houston, TX (United States); Kittrell, Carter [Rice Univ., Houston, TX (United States)

    2012-08-30

    The purpose of this research is to development the technology required for producing 3-D nano-engineered frameworks for hydrogen storage based on sp2 carbon media, which will have high gravimetric and especially high volumetric uptake of hydrogen, and in an aligned fibrous array that will take advantage of the exceptionally high thermal conductivity of sp2 carbon materials to speed up the fueling process while minimizing or eliminating the need for internal cooling systems. A limitation for nearly all storage media using physisorption of the hydrogen molecule is the large amount of surface area (SA) occupied by each H2 molecule due to its large zero-point vibrational energy. This creates a conundrum that in order to maximize SA, the physisorption media is made more tenuous and the density is decreased, usually well below 1 kg/L, so that there comes a tradeoff between volumetric and gravimetric uptake. Our major goal was to develop a new type of media with high density H2 uptake, which favors volumetric storage and which, in turn, has the capability to meet the ultimate DoE H2 goals.

  9. Seroprevalencia de Leptospira sp., Rickettsia sp. Ehrlichia sp. en trabajadores rurales del departamento de Sucre, Colombia Seroprevalence of Leptospira sp., Rickettsia sp. and Ehrlichia sp. in rural workers of Sucre, Colombia

    Directory of Open Access Journals (Sweden)

    Rodrigo Ríos

    2008-06-01

    Full Text Available Objective. Determinar la seroprevalencia de Leptospira sp., Rickettsia sp. y Ehrlichia sp. en trabajadores de áreas rurales del departamento de Sucre. Material y métodos. Se realizó un estudio escriptivo, prospectivo, de corte transversal, que pretendió determinar la seroprevalencia e Leptospira sp., Rickettsia sp. y Ehrlichia sp. en 90 trabajadores de áreas rurales del departamento de Sucre. Se estableció la presencia de anticuerpos séricos anti-IgM específicos anti-Leptospira por la técnica de ELISA indirecta. Para la determinación de Rickettsia sp. y Ehrlichia sp. se uso la técnica de inmunofluorescencia indirecta. Resultados. La población evaluada estaba compuesta por 27 (30% ordeñadores, 21 (23% jornaleros, 18 (20% profesionales del campo y 24 (27% que realizaban otras actividades. Ventidós (24% muestras resultaron positivas en alguna de las pruebas. De éstas, 12 (13,3% fueron positivas para Leptospira sp., 7 (7,8% para Rickettsia sp. y 3 (3,3% ara Ehrlichia sp. Conclusión. Este fue el primer estudio que se llevó a cabo en el departamento de Sucre y permitió demostrar que existe una prevalencia importante de Leptospira p.,Rickettsia sp. y Ehrlichia sp.. Los factores de riesgo ocupacional fueron factores determinantes en la seropositividad.Objective. To determine the seroprevalence of Leptospira sp., Rickettsia sp. and Ehrlichia sp. in agricultural workers of Sucre. Methods. A descriptive prospective cross-sectional study was conducted in ninety rural workers of Sucre. Presence of serum antibodies anti-IgM specific anti-Leptospira by indirect ELISA was established. For the determination of Rickettsia and Ehrlichia indirect inmunoflorescence was used. Results.The population was composed by 27 (30% milkers, 21 (23% day workers, 18 farm professionals (20% and 24 (26% workers in others activities. A total of 22 (24% samples were positive to some test. Twelve (13.3% were positive to Leptospira sp., seven (7.8% to Rickettsia sp

  10. Biologic overview for the Nevada Nuclear Waste Storage Investigations, Nevada Test Site, Nye County, Nevada

    International Nuclear Information System (INIS)

    Collins, E.; O'Farrell, T.P.; Rhoads, W.A.

    1982-01-01

    The Nevada Nuclear Waste Storage Investigations project study area includes five major vegetation associations characteristic of the transition between the northern extent of the Mojave Desert and the southern extent of the Great Basin Desert. A total of 32 species of reptiles, 66 species of birds, and 46 species of mammals are known to occur within these associations elsewhere on the Nevada Test Site. Ten species of plants, and the mule deer, wild horse, feral burro, and desert tortoise were defined as possible sensitive species because they are protected by federal and state regulations, or are being considered for such protection. The major agricultural resources of southern Nye County included 737,000 acres of public grazing land managed by the Bureau of Land Management, and 9500 acres of irrigated crop land located in the Beatty/Oasis valleys, the Amargosa Valley, and Ash Meadows. Range lands are of poor quality. Alfalfa and cotton are the major crops along with small amounts of grains, Sudan grass, turf, fruits, and melons. The largest impacts to known ecosystems are expected to result from: extensive disturbances associated with construction of roads, seismic lines, drilling pads, and surface facilities; storage and leaching of mined spoils; disposal of water; off-road vehicle travel; and, over several hundred years, elevated soil temperatures. Significant impacts to off-site areas such as Ash Meadows are anticipated if new residential developments are built there to accommodate an increased work force. Several species of concern and their essential habitats are located at Ash Meadows. Available literature contained sufficient baseline information to assess potential impacts of the proposed project on an area-wide basis. It was inadequate to support analysis of potential impacts on specific locations selected for site characterization studies, mining an exploratory shaft, or the siting and operation of a repository

  11. Radioactive solid waste inventories at United States Department of Energy burial and storage sites

    International Nuclear Information System (INIS)

    Watanabe, T.

    1986-06-01

    Radioactive solid waste inventories are given for United States Department of Energy (DOE) burial and storage sites. These data are obtained from the Solid Waste Information Management System (SWIMS) and reflect the inventories as of the end of the calendar year 1985. This report differs from previous issues in that the data cutoff date is December 31, 1985, rather than the fiscal year end. Another difference from previous issues is that data for the TRU categories 1 and 6 have been omitted

  12. Reversible deep storage: reversibility options for storage in deep geological formations

    International Nuclear Information System (INIS)

    2009-01-01

    This report describes the definition approach to reversibility conditions, presents the main characteristics of high-activity and intermediate-activity long-lived wastes, describes the storage in deep geological formations (safety functions, general description of the storage centre), discusses the design options for the different types of wastes (container, storage module, handling processes, phenomenological analysis, monitoring arrangements) and the decision process in support reversibility (steering of the storage process, progressive development and step-by-step closing), and reports and discusses the researches concerning the memory of the storage site

  13. Environmental concern-based site screening of carbon dioxide geological storage in China.

    Science.gov (United States)

    Cai, Bofeng; Li, Qi; Liu, Guizhen; Liu, Lancui; Jin, Taotao; Shi, Hui

    2017-08-08

    Environmental impacts and risks related to carbon dioxide (CO 2 ) capture and storage (CCS) projects may have direct effects on the decision-making process during CCS site selection. This paper proposes a novel method of environmental optimization for CCS site selection using China's ecological red line approach. Moreover, this paper established a GIS based spatial analysis model of environmental optimization during CCS site selection by a large database. The comprehensive data coverage of environmental elements and fine 1 km spatial resolution were used in the database. The quartile method was used for value assignment for specific indicators including the prohibited index and restricted index. The screening results show that areas classified as having high environmental suitability (classes III and IV) in China account for 620,800 km 2 and 156,600 km 2 , respectively, and are mainly distributed in Inner Mongolia, Qinghai and Xinjiang. The environmental suitability class IV areas of Bayingol Mongolian Autonomous Prefecture, Hotan Prefecture, Aksu Prefecture, Hulunbuir, Xilingol League and other prefecture-level regions not only cover large land areas, but also form a continuous area in the three provincial-level administrative units. This study may benefit the national macro-strategic deployment and implementation of CCS spatial layout and environmental management in China.

  14. Evolution of sp2 networks with substrate temperature in amorphous carbon films: Experiment and theory

    International Nuclear Information System (INIS)

    Gago, R.; Vinnichenko, M.; Jaeger, H.U.; Maitz, M.F.; Belov, A.Yu.; Jimenez, I.; Huang, N.; Sun, H.

    2005-01-01

    The evolution of sp 2 hybrids in amorphous carbon (a-C) films deposited at different substrate temperatures was studied experimentally and theoretically. The bonding structure of a-C films prepared by filtered cathodic vacuum arc was assessed by the combination of visible Raman spectroscopy, x-ray absorption, and spectroscopic ellipsometry, while a-C structures were generated by molecular-dynamics deposition simulations with the Brenner interatomic potential to determine theoretical sp 2 site distributions. The experimental results show a transition from tetrahedral a-C (ta-C) to sp 2 -rich structures at ∼500 K. The sp 2 hybrids are mainly arranged in chains or pairs whereas graphitic structures are only promoted for sp 2 fractions above 80%. The theoretical analysis confirms the preferred pairing of isolated sp 2 sites in ta-C, the coalescence of sp 2 clusters for medium sp 2 fractions, and the pronounced formation of rings for sp 2 fractions >80%. However, the dominance of sixfold rings is not reproduced theoretically, probably related to the functional form of the interatomic potential used

  15. A comparative study of different storage methods on the shelf-life of ...

    African Journals Online (AJOL)

    A study was conducted to determine the storage method that will best preserve the quality and quantity of smoke-cured Clarias sp. using boxes made of cardboard and wood, as well as, airtight metal containers. The boxes made of cardboard material was found to be the best medium of storage as all infesting dermestid ...

  16. Cast iron transport, storage and disposal containers for use in UK nuclear licensed sites - 59412

    International Nuclear Information System (INIS)

    Viermann, Joerg; Messer, Matthias P.

    2012-01-01

    Document available in abstract form only. Full text of publication follows: Ductile Cast Iron Containers of the types GCVI (UK trademark -GNS YELLOW BOX R ) and MOSAIK R have been in use in Germany for transport, storage and disposal of intermediate level radioactive waste (ILW) for more than two decades. In 2009 a number of containers of these types were delivered to various Magnox sites as so called pathfinders to test their suitability for Magnox waste streams. The results were encouraging. Therefore the Letter of Compliance (LoC) procedure was started to prove the suitability of packages using these types of containers for the future UK Geological Disposal Facility (GDF) and a conceptual Letter of Compliance (cLoC) was obtained from RWMD in 2010. Waste stream specific applications for Interim Stage Letters of Compliance (ILoC) for a number of waste streams from different Magnox sites and from the UK's only pressurised water reactor, Sizewell B are currently being prepared and discussed with RWMD. In order to achieve a package suitable for interim storage and disposal the contents of a Ductile Cast Iron Container only has to be dried. Mobile drying facilities are readily available. Containers and drying facilities form a concerted system

  17. Housekeeping Closure Report for Corrective Action Unit 119: Storage Tanks, Nevada Test Site, Nevada

    International Nuclear Information System (INIS)

    2000-01-01

    The Federal Facility Agreement and Consent Order was entered into by the State of Nevada, US Department of Energy, and US Department of Defense to identify sites of potential historical contamination and implement corrective actions based on public health and environmental considerations. The facilities subject to this agreement include the Nevada Test Site (NTS), parts of the Tonopah Test Range, parts to the Nellis Air Force Range, the Central Nevada Test Area, and the Project Shoal Area. Corrective Action Sites (CASs) are areas potentially requiring corrective actions and may include solid waste management units, individual disposal, or release sites. Based on geography, technical similarity, agency responsibility, or other appropriate reasons, CASs are grouped together into Corrective Action Units (CAUs) for the purpose of determining appropriate corrective actions. This report contains the Closure Verification Forms for cleanup activities that were performed at 19 CASs with in CAU 119 on the NTS. The form for each CAS provides the location, directions to the site, general description, and photographs of the site before and after cleanup activities. Activities included verification of the prior removal of both aboveground and underground gas/oil storage tanks, gas sampling tanks, pressure fuel tanks, tank stands, trailers, debris, and other material. Based on these former activities, no further action is required at these CASs

  18. Decommissioning of the 105-F and 105-H fuel storage basin in the 100 Area at the Hanford Site

    International Nuclear Information System (INIS)

    Griffin, P.W.

    1991-09-01

    The US Department of Energy (DOE) owns the eight surplus production reactors at the Hanford Site north of Richland, Washington. The fuel storage basins at the 105-F and 105-H reactors were filled with equipment, associated with the operation of the basins and clean fill in 1970. This was done to stabilize the residual sediment and a few feet of water in the reactors' fuel storage basins. This project investigates the subject basins to locate and remove overlooked fuel elements left in the basins

  19. Streamlined approach for environmental restoration closure report for Corrective Action Unit No. 456: Underground storage tank release site 23-111-1, Nevada Test Site, Nevada

    International Nuclear Information System (INIS)

    1998-04-01

    The underground storage tank (UST) release site 23-111-1 is located in Mercury, Nevada. The site is in Area 23 of the Nevada Test Site, (NTS) located on the north side of Building 111. The tank associated with the release was closed in place using cement grout on September 6, 1990. The tank was not closed by removal due to numerous active underground utilities, a high-voltage transformer pad, and overhead power lines. Soil samples collected below the tank bottom at the time of tank closure activities exceeded the Nevada Administrative Code Action Level of 100 milligrams per kilogram (mg/kg) for petroleum hydrocarbons. Maximum concentrations detected were 119 mg/kg. Two passive venting wells were subsequently installed at the tank ends to monitor the progress of biodegradation at the site. Quarterly air sampling from the wells was completed for approximately one year, but was discontinued since data indicated that considerable biodegradation was not occurring at the site

  20. Social Site Characterisation for CO2 storage operations to inform public engagement in Poland and Scotland

    Energy Technology Data Exchange (ETDEWEB)

    Brunsting, S.; Pol, M.; Mastop, J. [Energy research Centre of the Netherlands ECN, Policy Studies, Petten (Netherlands); Kaiser, M.; Zimmer, R. [UfU - Independent Institute for Environmental Issues, Berlin (Germany); Shackley, S.; Mabon, L.; Howell, R. [The University of Edinburgh - School of Geosciences, Edinburgh, Scotland (United Kingdom); Hepplewhite, F.; Loveridge, R. [Scottish Government, Edinburgh, Scotland (United Kingdom); Mazurowski, M. [PGNiG - Polskie Gornictwo Naftowe i Gazownictwo SA, Warszawa (Poland); Rybicki, C. [AGH - University of Science and Technology, Krakow (Poland)

    2013-05-01

    Public support has proven crucial to the implementation of CO2 capture and storage (CCS) demonstration projects. Whereas no method exists to guarantee local 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 plan and evaluate an approach for actively engaging local stakeholders. Social site characterisation is the process of repeatedly investigating local public awareness and opinions of a specific CCS project, changes therein over time, and underlying factors shaping public opinion as a parallel activity to technical site characterization. This paper presents results from the EU FP7 SiteChar project in which social site characterisation (a.o. surveys) and public participation activities (focus conferences) were conducted by a multidisciplinary team at two prospective CCS sites in in Poland (onshore) and Scotland (offshore). Results demonstrate that social site characterization and focus conferences are powerful tools to raise public awareness about complex issues such as CCS and to initiate local discussion and planning processes with the appropriate type of information, through appropriate media, and involving all relevant stakeholders. Application and the duration of effects in real-life project settings will be discussed.

  1. Comprehensive Monitoring for Heterogeneous Geographically Distributed Storage

    Energy Technology Data Exchange (ETDEWEB)

    Ratnikova, N. [Fermilab; Karavakis, E. [CERN; Lammel, S. [Fermilab; Wildish, T. [Princeton U.

    2015-12-23

    Storage capacity at CMS Tier-1 and Tier-2 sites reached over 100 Petabytes in 2014, and will be substantially increased during Run 2 data taking. The allocation of storage for the individual users analysis data, which is not accounted as a centrally managed storage space, will be increased to up to 40%. For comprehensive tracking and monitoring of the storage utilization across all participating sites, CMS developed a space monitoring system, which provides a central view of the geographically dispersed heterogeneous storage systems. The first prototype was deployed at pilot sites in summer 2014, and has been substantially reworked since then. In this paper we discuss the functionality and our experience of system deployment and operation on the full CMS scale.

  2. Design report for the interim waste containment facility at the Niagara Falls Storage Site

    International Nuclear Information System (INIS)

    1986-05-01

    Low-level radioactive residues from pitchblende processing and thorium- and radium-contaminated sand, soil, and building rubble are presently stored at the Niagara Falls Storage Site (NFSS) in Lewiston, New York. These residues and wastes derive from past NFSS operations and from similar operations at other sites in the United States conducted during the 1940s by the Manhattan Engineer District (MED) and subsequently by the Atomic Energy Commission (AEC). The US Department of Energy (DOE), successor to MED/AEC, is conducting remedial action at the NFSS under two programs: on-site work under the Surplus Facilities Managemnt Program and off-site cleanup of vicinity properties under the Formerly Utilized Sites Remedial Action Program. On-site remedial action consists of consolidating the residues and wastes within a designated waste containment area and constructing a waste containment facility to prevent contaminant migration. The service life of the system is 25 to 50 years. Near-term remedial action construction activities will not jeopardize or preclude implementation of any other remedial action alternative at a later date. Should DOE decide to extend the service life of the system, the waste containment area would be upgraded to provide a minimum service life of 200 years. This report describes the design for the containment system. Pertinent information on site geology and hydrology and on regional seismicity and meteorology is also provided. Engineering calculations and validated computer modeling studies based on site-specific and conservative parameters confirm the adequacy of the design for its intended purposes of waste containment and environmental protection

  3. Development of in-structure design spectra for dome mounted equipment on underground waste storage tanks at the Hanford Site

    International Nuclear Information System (INIS)

    Julyk, L.J.

    1995-09-01

    In-structure response spectra for dome mounted equipment on underground waste storage tanks at the Hanford Site are developed on the basis of recent soil-structure-interaction analyses. Recommended design spectra are provided for various locations on the tank dome

  4. Geostatistical characterisation of geothermal parameters for a thermal aquifer storage site in Germany

    Science.gov (United States)

    Rodrigo-Ilarri, J.; Li, T.; Grathwohl, P.; Blum, P.; Bayer, P.

    2009-04-01

    The design of geothermal systems such as aquifer thermal energy storage systems (ATES) must account for a comprehensive characterisation of all relevant parameters considered for the numerical design model. Hydraulic and thermal conductivities are the most relevant parameters and its distribution determines not only the technical design but also the economic viability of such systems. Hence, the knowledge of the spatial distribution of these parameters is essential for a successful design and operation of such systems. This work shows the first results obtained when applying geostatistical techniques to the characterisation of the Esseling Site in Germany. In this site a long-term thermal tracer test (> 1 year) was performed. On this open system the spatial temperature distribution inside the aquifer was observed over time in order to obtain as much information as possible that yield to a detailed characterisation both of the hydraulic and thermal relevant parameters. This poster shows the preliminary results obtained for the Esseling Site. It has been observed that the common homogeneous approach is not sufficient to explain the observations obtained from the TRT and that parameter heterogeneity must be taken into account.

  5. The search for a storage site for low-level and long-life wastes. A national project and a development opportunity for your town. A dossier for local communities

    International Nuclear Information System (INIS)

    2008-01-01

    After a review of the program schedule, this document presents the project of a storage site for low-level and long life radioactive wastes as an opportunity for a district: it outlines the benefits of such a realisation for the dynamics of the local activity, specifies the main economical and financial characteristics associated with such a facility, and evokes the elements which are taken into account for the selection of the site. It describes the storage centre as a place of industrial activity, a monitored and controlled facility, an installation opened to the public. It describes the different stages of the life cycle of this future storage centre: pre-selection, on-site investigations, additional studies and administrative process for the selected site, building and starting, operation, shutting down, surveillance. The document indicates the legal frame related to this activity, specifies what are the different concerned wastes, and their present warehousing locations. It gives some details on the different safety principles for such a storage: environment and health protection, geological layer, public works engineering solutions, waste packages

  6. Cancer mortality and incidence survey around the Aube's low- and medium-activity radioactive waste storage site

    International Nuclear Information System (INIS)

    2010-01-01

    This report presents the main results of a survey performed in 2010 to describe the health status of the population around the Aube's low- and medium-activity radioactive waste storage site. The aim of this survey was to determine whether the frequencies of death and hospitalization on account of cancer are different for this population (15 km around the site) with respect to two reference populations (the population of the Champagne-Ardennes region and the French metropolitan population). Results of mortality, hospitalization, and lung cancer are presented under the form of maps and tables giving global data or data for males, females, adults, or children

  7. Characterization of Tifton 85 bermudagrass haylage with different layers of polyethylene film and storage time.

    Science.gov (United States)

    Nath, Caroline Daiane; Neres, Marcela Abbado; Scheidt, Kácia Carine; Bersot, Luciano Dos Santos; Sunahara, Samantha Mariana Monteiro; Sarto, Jaqueline Rocha Wobeto; Stangarlin, José Renato; Gomes, Simone Damasceno; Sereno, Mallu Jagnow; Perin, Ana Paula

    2018-03-02

    The objective was to characterize the fermentative and microbiological profile of Tifton 85 bermudagrass haylage with different layers of polyethylene film and storage time. The experimental design consisted of a randomized block design with four and six wrapping layers (100 and 150 microns in total. respectively) allocated in the main plots, through repeated measures analysis (30, 60, and 90 days of storage) with four replicates. The storage time and number of wrapping layers did not show changes in the population of Clostridium and lactic acid bacteria. A decrease was observed in the enterobacteria population with an increase in the storage period in the two wrapping layers studied. Upon opening of the haylage at 30 days, the population of Bacillus was lower in haylages made with six layers of wrapping (3.63 log colony forming units (CFU) g-1). No growth of Listeria sp. or Salmonella sp. was observed during the experimental period. The fungal genera with greater occurrence were Penicillium sp. and Fusarium sp. The following mycotoxins were not detected: ochratoxin A, fumonisins, and zearalenone. Relative to the organic butyric, propionic, and acetic acids, the haylages presented a low concentration of lactic acid; this may have prevented a drop in the pH, which was high when the silos were opened (5.4). The levels of ammoniacal nitrogen and soluble carbohydrates presented no variation among the number of wrapping layers, with an overall average of 35.55 and 38.04 g kg-1. Tifton 85 bermudagrass haylage wrapped with four and six layers presented adequate fermentation and microbiological characteristics in the evaluated periods.

  8. Screening of prospective sites for geological storage of CO{sub 2} in the Southern Baltic Sea

    Energy Technology Data Exchange (ETDEWEB)

    Vernon, R.; O' Neil, N.; Pasquali, R. [SLR Consulting, Dublin (Ireland); Nieminen, M.

    2013-05-15

    The BASTOR project focuses on identifying and characterising potential sites for CO{sub 2} storage in the southern Baltic Sea region. A compilation of available digital data from well logs, seismic line data interpretations, mapped structure outlines and published material from existing hydrocarbon fields and identified and mapped structures from Sweden, Poland, Latvia, Lithuania and Kaliningrad have been incorporated into a regional GIS for the Baltic Sea region. A detailed screening of regional sedimentary basins identified the Slupsk Border Zone as having suitable structures for storage of CO{sub 2} in depleted oil and gas fields or saline aquifers. Cambrian sandstone saline aquifers below 900 m have been identified as the principal regional potential storage target with the Dalders Monocline as the most promising area. Eight individual structures were identified as having greatest potential. Detailed 3D geological static models were developed for three of these structures located in offshore Latvia (E6 and E7) and one cross-border structure (Dalders Structure). A theoretical regional CO{sub 2} storage capacity calculation based on the GeoCapacity methodology was undertaken. A regional storage capacity for Cambrian sandstones below 900 m was estimated at a total of 16 Gt, with 2 Gt for the Dalders Monocline. Theoretical storage estimates for individual structures for the Baltic Sea regions includes 760 Mt for the Latvian structures and the Dalders Structure, 9.1 Mt for the structures located in Poland, 31 Mt in Lithuania and 170 Mt in Kaliningrad. These estimates are based on the best available data at the time of writing. However these estimates will be improved upon as new data becomes available from other sources. (orig.)

  9. Hazelwood Interim Storage Site environmental report for calendar year 1992, 9200 Latty Avenue, Hazelwood, Missouri

    International Nuclear Information System (INIS)

    1993-05-01

    This report describes the environmental surveillance program at the Hazelwood Interim storage Site (HISS) and surrounding area, provides the results for 1992, and discusses applicable environmental standards and requirements with which the results were compared. HISS is located in eastern Missouri in the City of Hazelwood (St. Louis County) and occupies approximately 2.2 ha (5.5 acres). Environmental monitoring of HISS began in 1984 when the site was assigned to the US Department of Energy (DOE) as part of the decontamination research and development project authorized by Congress under the 1984 Energy and Water Development Appropriations Act. DOE placed responsibility for HISS under the Formerly Utilized Sites Remedial Action Program (FUSRAP), which was established to identify and decontaminate or otherwise control sites where residual radioactive materials remain from the early years of the nation's atomic energy program or from commercial operations causing conditions that Congress has authorized DOE to remedy. In 1992 there were no environmental occurrences or unplanned contaminant releases as defined in DOE requirements and in the Superfund Amendment and Reauthorization Act (SARA) Title III of CERCLA

  10. Hazelwood Interim Storage Site environmental report for calendar year 1992, 9200 Latty Avenue, Hazelwood, Missouri

    Energy Technology Data Exchange (ETDEWEB)

    1993-05-01

    This report describes the environmental surveillance program at the Hazelwood Interim storage Site (HISS) and surrounding area, provides the results for 1992, and discusses applicable environmental standards and requirements with which the results were compared. HISS is located in eastern Missouri in the City of Hazelwood (St. Louis County) and occupies approximately 2.2 ha (5.5 acres). Environmental monitoring of HISS began in 1984 when the site was assigned to the US Department of Energy (DOE) as part of the decontamination research and development project authorized by Congress under the 1984 Energy and Water Development Appropriations Act. DOE placed responsibility for HISS under the Formerly Utilized Sites Remedial Action Program (FUSRAP), which was established to identify and decontaminate or otherwise control sites where residual radioactive materials remain from the early years of the nation`s atomic energy program or from commercial operations causing conditions that Congress has authorized DOE to remedy. In 1992 there were no environmental occurrences or unplanned contaminant releases as defined in DOE requirements and in the Superfund Amendment and Reauthorization Act (SARA) Title III of CERCLA.

  11. Colonie Interim Storage Site: Annual environmental report for calendar year 1990, Colonie, New York

    International Nuclear Information System (INIS)

    1991-09-01

    Environmental monitoring of the US Department of Energy's (DOE) Colonie Interim Storage Site (CISS) and surrounding area began in 1984. CISS is part of the Formerly Utilized Sites Remedial Action Program (FUSRAP), a DOE program to decontaminate or otherwise control sties where residual radioactive materials remain from the early years of the nation's atomic energy program or from commercial operations causing conditions that Congress has authorized DOE to remedy. The routine environmental monitoring program at CISS includes sampling networks for external gamma radiation exposures and for radium-226, throium-232, an total uranium concentrations in surface water, sediment, and groundwater. Additionally, the nonradiological parameters volatile and semivolatile organics, pesticides/polychlorinated biphenyls (PCBs), metals, total organic carbon (TOC), total organic halides (TOX), specific conductivity, and pH are measured in groundwater. 14 refs., 20 figs., 25 tabs

  12. Description of INR-Pitesti own strategy for on site radioactive solid waste storage concepts

    International Nuclear Information System (INIS)

    Tuturici, I.L.; Toma, V.; Bujoreanu, D.; Prava, M.

    1993-01-01

    The Post Irradiation Examination Laboratory (PIEL) produces and will produce the majority of institute's alpha-contaminated solid radioactive waste, generated by the process of examination of irradiated CANDU-600 type nuclear fuel. The wastes will be divided into three categories: low-level, medium-level, and high-level general process trash (LLGPT, MLGPT, and HLGPT). The paper describes the strategy adopted for immobilization, conditioning and on-site long-term storage of these wastes. The proposed strategy is based on the best experience acquired by other nuclear centers, confronted with same problems. (Author)

  13. Substance P and substance K receptor binding sites in the human gastrointestinal tract: localization by autoradiography

    International Nuclear Information System (INIS)

    Gates, T.S.; Zimmerman, R.P.; Mantyh, C.R.; Vigna, S.R.; Maggio, J.E.; Welton, M.L.; Passaro, E.P. Jr.; Mantyh, P.W.

    1988-01-01

    Quantitative receptor autoradiography was used to localize and quantify the distribution of binding sites for 125 I-radiolabeled substance P (SP), substance K (SK) and neuromedin K (NK) in the human GI tract using histologically normal tissue obtained from uninvolved margins of resections for carcinoma. The distribution of SP and SK binding sites is different for each gastrointestinal (GI) segment examined. Specific SP binding sites are expressed by arterioles and venules, myenteric plexus, external circular muscle, external longitudinal muscle, muscularis mucosa, epithelial cells of the mucosa, and the germinal centers of lymph nodules. SK binding sites are distributed in a pattern distinct from SP binding sites and are localized to the external circular muscle, external longitudinal muscle, and the muscularis mucosa. Binding sites for NK were not detected in any part of the human GI tract. These results demonstrate that: (1) surgical specimens from the human GI tract can be effectively processed for quantitative receptor autoradiography; (2) of the three mammalian tachykinins tested, SP and SK, but not NK binding sites are expressed in detectable levels in the human GI tract; (3) whereas SK receptor binding sites are expressed almost exclusively by smooth muscle, SP binding sites are expressed by smooth muscle cells, arterioles, venules, epithelial cells of the mucosa and cells associated with lymph nodules; and (4) both SP and SK binding sites expressed by smooth muscle are more stable than SP binding sites expressed by blood vessels, lymph nodules, and mucosal cells

  14. Integrative Gene Cloning and Expression System for Streptomyces sp. US 24 and Streptomyces sp. TN 58 Bioactive Molecule Producing Strains

    Directory of Open Access Journals (Sweden)

    Samiha Sioud

    2009-01-01

    Full Text Available Streptomyces sp. US 24 and Streptomyces sp. TN 58, two strains producing interesting bioactive molecules, were successfully transformed using E. coli ET12567 (pUZ8002, as a conjugal donor, carrying the integrative plasmid pSET152. For the Streptomyces sp. US 24 strain, two copies of this plasmid were tandemly integrated in the chromosome, whereas for Streptomyces sp. TN 58, the integration was in single copy at the attB site. Plasmid pSET152 was inherited every time for all analysed Streptomyces sp. US 24 and Streptomyces sp. TN 58 exconjugants under nonselective conditions. The growth, morphological differentiation, and active molecules production of all studied pSET152 integrated exconjugants were identical to those of wild type strains. Consequently, conjugal transfer using pSET152 integration system is a suitable means of genes transfer and expression for both studied strains. To validate the above gene transfer system, the glucose isomerase gene (xylA from Streptomyces sp. SK was expressed in strain Streptomyces sp. TN 58. Obtained results indicated that heterologous glucose isomerase could be expressed and folded effectively. Glucose isomerase activity of the constructed TN 58 recombinant strain is of about eighteenfold higher than that of the Streptomyces sp. SK strain. Such results are certainly of importance due to the potential use of improved strains in biotechnological process for the production of high-fructose syrup from starch.

  15. Spent fuel storage and isolation

    International Nuclear Information System (INIS)

    Bensky, M.S.; Kurzeka, W.J.; Bauer, A.A.; Carr, J.A.; Matthews, S.C.

    1979-02-01

    The principal spent fuel activities conducted within the commercial waste and spent fuel within the Commercial Waste and Spent Fuel Packaging Program are: simulated near-surface (drywell) storage demonstrations at Hanford and the Nevada Test Site; surface (sealed storage cask) and drywell demonstrations at the Nevada Test Site; and spent fuel receiving and packaging facility conceptual design. These investigations are described

  16. Off-Site Storage and Special Collections: A Study in Use and Impact in ARL Libraries in the United States

    Science.gov (United States)

    Priddle, Charlotte; McCann, Laura

    2015-01-01

    Special collections libraries collect and preserve materials of intellectual and cultural heritage, providing access to unique research resources. As their holdings continue to expand, special collections in research libraries confront increased space pressures. Off-site storage facilities, used frequently by research libraries for general…

  17. Rock cavern storage of spent fuel

    Energy Technology Data Exchange (ETDEWEB)

    Cho, Won Jin; Kim, Kyung Soo [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of); Kwon, Sang Ki [Inha University, Incheon (Korea, Republic of)

    2015-12-15

    The rock cavern storage for spent fuel has been assessed to apply in Korea with reviewing the state of the art of the technologies for surface storage and rock cavern storage of spent fuel. The technical feasibility and economic aspects of the rock cavern storage of spent fuel were also analyzed. A considerable area of flat land isolated from the exterior are needed to meet the requirement for the site of the surface storage facilities. It may, however, not be easy to secure such areas in the mountainous region of Korea. Instead, the spent fuel storage facilities constructed in the rock cavern moderate their demands for the suitable site. As a result, the rock cavern storage is a promising alternative for the storage of spent fuel in the aspect of natural and social environments. The rock cavern storage of spent fuel has several advantages compared with the surface storage, and there is no significant difference on the viewpoint of economy between the two alternatives. In addition, no great technical difficulties are present to apply the rock cavern storage technologies to the storage of domestic spent fuel.

  18. Standardized, utility-DOE compatible, spent fuel storage-transport systems

    International Nuclear Information System (INIS)

    Smith, M.L.

    1991-01-01

    Virginia Power has developed and licensed a facility for dry storage of spent nuclear fuel in metal spent fuel storage casks. The modifications to the design of these casks necessary for licensing for both storage and transport of spent fuel are discussed along with the operational advantages of dual purpose storage-transport casks. Dual purpose casks can be used for storage at utility and DOE sites (MRS or repository) and for shipment between these sites with minimal spent fuel handling. The cost for a standardized system of casks that are compatible for use at both DOE and utility sites is discussed along with possible arrangements for sharing both the cost and benefits of dual purpose storage-transport casks

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

    International Nuclear Information System (INIS)

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

    1978-01-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1978-02-15

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

  1. Streamlined Approach for Environmental Restoration Closure Report for Corrective Action Unit 120: Areas 5 and 6 Aboveground Storage Tanks, Nevada Test Site, Nevada

    Energy Technology Data Exchange (ETDEWEB)

    Allison Urban

    1999-06-01

    This Closure Report provides documentation for the closure of Corrective Action Unit 120. CAU 120 consists of two Corrective Action Sites located in Areas 5 and 6 of the Nevada Test Site. CAS 05-01-01 is located in Area 5 and consists of three 45,800-liter aboveground storage tanks, piping, and debris associated with Well RNM-1. CAS 06-01-01 in Area 6 consists of two aboveground storage tanks and two tanker trailers All the CAU 120 items have been used to convey or contain radiologically contaminated fluid from post-nuclear event activities at the NTS> Closure of this CAU was completed by collecting samples to identify the appropriate method of disposal for tanks, piping, debris, and tankers in each CAS. Placing low-level radioactive waste into the appropriate containers and disposing of waste in the Area 5 Radioactive Waste Management Site, the Area 9 10C Landfill, and the Area 3 Radioactive Waste Management Site.

  2. Streamlined Approach for Environmental Restoration Closure Report for Corrective Action Unit 120: Areas 5 and 6 Aboveground Storage Tanks, Nevada Test Site, Nevada

    International Nuclear Information System (INIS)

    Allison Urban

    1999-01-01

    This Closure Report provides documentation for the closure of Corrective Action Unit 120. CAU 120 consists of two Corrective Action Sites located in Areas 5 and 6 of the Nevada Test Site. CAS 05-01-01 is located in Area 5 and consists of three 45,800-liter aboveground storage tanks, piping, and debris associated with Well RNM-1. CAS 06-01-01 in Area 6 consists of two aboveground storage tanks and two tanker trailers All the CAU 120 items have been used to convey or contain radiologically contaminated fluid from post-nuclear event activities at the NTS> Closure of this CAU was completed by collecting samples to identify the appropriate method of disposal for tanks, piping, debris, and tankers in each CAS. Placing low-level radioactive waste into the appropriate containers and disposing of waste in the Area 5 Radioactive Waste Management Site, the Area 9 10C Landfill, and the Area 3 Radioactive Waste Management Site

  3. Verification of criticality safety in on-site spent fuel storage systems

    International Nuclear Information System (INIS)

    Rasmussen, R.W.

    1989-01-01

    On February 15, 1984, Duke Power Company received approval for a two-region, burnup credit, spent fuel storage rack design at both Units 1 and 2 of the McGuire Nuclear Station. Duke also hopes to obtain approval by January of 1990 for a dry spent fuel storage system at the Oconee Nuclear Station, which will incorporate the use of burnup credit in the criticality analysis governing the design of the individual storage units. While experiences in burnup verification for criticality safety for their dry storage system at Oconee are in the future, the methods proposed for burnup verification will be similar to those currently used at the McGuire Nuclear Station in the two-region storage racks installed in both pools. In conclusion, the primary benefit of the McGuire rerack effort has obviously been the amount of storage expansion it provided. A total increase of about 2,000 storage cells was realized, 1,000 of which were the result of pursuing the two-region rather than the conventional poison rack design. Less impacting, but equally as important, however, has been the experience gained during the planning, installation, and operation of these storage racks. This experience should prove useful for future rerack efforts likely to occur at Duke's Catawba Nuclear Station as well as for the current dry storage effort underway for the Oconee Nuclear Station

  4. Interim and final storage casks

    International Nuclear Information System (INIS)

    Stumpfrock, L.; Kockelmann, H.

    2012-01-01

    The disposal of radioactive waste is a huge social challenge in Germany and all over the world. As is well known the search for a site for a final repository for high-level waste in Germany is not complete. Therefore, interim storage facilities for radioactive waste were built at plant sites in Germany. The waste is stored in these storage facilities in appropriate storage and transport casks until the transport in a final repository can be carried out. Licensing of the storage and transport casks aimed for use in the public space is done according to the traffic laws and for handling in the storage facility according to nuclear law. Taking into account the activity of the waste to be stored, different containers are in use, so that experience is available from the licensing and operation in interim storage facilities. The large volume of radioactive waste to be disposed of after the shut-down of power generation in nuclear power stations makes it necessary for large quantities of licensed storage and transport casks to be provided soon.

  5. VM-based infrastructure for simulating different cluster and storage solutions used on ATLAS Tier-3 sites

    International Nuclear Information System (INIS)

    Belov, S; Kadochnikov, I; Korenkov, V; Kutouski, M; Oleynik, D; Petrosyan, A

    2012-01-01

    The current ATLAS Tier-3 infrastructure consists of a variety of sites of different sizes and with a mix of local resource management systems (LRMS) and mass storage system (MSS) implementations. The Tier-3 monitoring suite, having been developed in order to satisfy the needs of Tier-3 site administrators and to aggregate Tier-3 monitoring information on the global VO level, needs to be validated for various combinations of LRMS and MSS solutions along with the corresponding Ganglia plugins. For this purpose the testbed infrastructure, which allows simulation of various computational cluster and storage solutions, had been set up at JINR (Dubna, Russia). This infrastructure provides the ability to run testbeds with various LRMS and MSS implementations, and with the capability to quickly redeploy particular testbeds or their components. Performance of specific components is not a critical issue for development and validation, whereas easy management and deployment are crucial. Therefore virtual machines were chosen for implementation of the validation infrastructure which, though initially developed for Tier-3 monitoring project, can be exploited for other purposes. Load generators for simulation of the computing activities at the farm were developed as a part of this task. The paper will cover concrete implementation, including deployment scenarios, hypervisor details and load simulators.

  6. The Donald C. Cook Nuclear Plant's experience with on-site storage

    International Nuclear Information System (INIS)

    MacRae, W.T.

    1993-01-01

    The Donald C. Cook nuclear plant is located in Bridgman, Michigan. As such, no low-level radioactive waste from the facility has been sent to burial since November 1990. The only option is storage. The plant is well prepared for storage. A new facility was built, so the plant now has >2265 M3 (80 000 ft 3 ) of storage capacity. There are a number of issues that have had to be addressed during the period of storage. These items include storage capacity and waste generation rates, the waste form and the packages used, and the regulatory issues

  7. Investigation of Pumped Storage Hydropower Power-Off Transient Process Using 3D Numerical Simulation Based on SP-VOF Hybrid Model

    Directory of Open Access Journals (Sweden)

    Daqing Zhou

    2018-04-01

    Full Text Available The transient characteristic of the power-off process is investigated due to its close relation to hydraulic facilities’ safety in a pumped storage hydropower (PSH. In this paper, power-off transient characteristics of a PSH station in pump mode was studied using a three-dimensional (3D unsteady numerical method based on a single-phase and volume of fluid (SP-VOF coupled model. The computational domain covered the entire flow system, including reservoirs, diversion tunnel, surge tank, pump-turbine unit, and tailrace tunnel. The fast changing flow fields and dynamic characteristic parameters, such as unit flow rate, runner rotate speed, pumping lift, and static pressure at measuring points were simulated, and agreed well with experimental results. During the power-off transient process, the PSH station underwent pump mode, braking mode, and turbine mode, with the dynamic characteristics and inner flow configurations changing significantly. Intense pressure fluctuation occurred in the region between the runner and guide vanes, and its frequency and amplitude were closely related to the runner’s rotation speed and pressure gradient, respectively. While the reversed flow rate of the PSH unit reached maximum, some parameters, such as static pressure, torque, and pumping lift would suddenly jump significantly, due to the water hammer effect. The moment these marked jumps occurred was commonly considered as the most dangerous moment during the power-off transient process, due to the blade passages being clogged by vortexes, and chaos pressure distribution on the blade surfaces. The results of this study confirm that 3D SP-VOF hybrid simulation is an effective method to reveal the hydraulic mechanism of the PSH transient process.

  8. A mutation in a functional Sp1 binding site of the telomerase RNA gene (hTERC promoter in a patient with Paroxysmal Nocturnal Haemoglobinuria

    Directory of Open Access Journals (Sweden)

    Mason Philip J

    2004-06-01

    Full Text Available Abstract Background Mutations in the gene coding for the RNA component of telomerase, hTERC, have been found in autosomal dominant dyskeratosis congenita (DC and aplastic anemia. Paroxysmal nocturnal hemoglobinuria (PNH is a clonal blood disorder associated with aplastic anemia and characterized by the presence of one or more clones of blood cells lacking glycosylphosphatidylinositol (GPI anchored proteins due to a somatic mutation in the PIGA gene. Methods We searched for mutations in DNA extracted from PNH patients by amplification of the hTERC gene and denaturing high performance liquid chromatography (dHPLC. After a mutation was found in a potential transcription factor binding site in one patient electrophoretic mobility shift assays were used to detect binding of transcription factors to that site. The effect of the mutation on the function of the promoter was tested by transient transfection constructs in which the promoter is used to drive a reporter gene. Results Here we report the finding of a novel promoter mutation (-99C->G in the hTERC gene in a patient with PNH. The mutation disrupts an Sp1 binding site and destroys its ability to bind Sp1. Transient transfection assays show that mutations in this hTERC site including C-99G cause either up- or down-regulation of promoter activity and suggest that the site regulates core promoter activity in a context dependent manner in cancer cells. Conclusions These data are the first report of an hTERC promoter mutation from a patient sample which can modulate core promoter activity in vitro, raising the possibility that the mutation may affect the transcription of the gene in hematopoietic stem cells in vivo, and that dysregulation of telomerase may play a role in the development of bone marrow failure and the evolution of PNH clones.

  9. Evolution of spent fuel dry storage

    Energy Technology Data Exchange (ETDEWEB)

    Standring, Paul Nicholas [International Atomic Energy Agency, Vienna (Austria). Div. of Nuclear Fuel Cycle and Waste Technology; Takats, Ferenc [TS ENERCON KFT, Budapest (Hungary)

    2016-11-15

    Around 10,000 tHM of spent fuel is discharged per year from the nuclear power plants in operation. Whilst the bulk of spent fuel is still held in at reactor pools, 24 countries have developed storage facilities; either on the reactor site or away from the reactor site. Of the 146 operational AFR storage facilities about 80 % employ dry storage; the majority being deployed over the last 20 years. This reflects both the development of dry storage technology as well as changes in politics and trading relationships that have affected spent fuel management policies. The paper describes the various approaches to the back-end of the nuclear fuel cycle for power reactor fuels and provides data on deployed storage technologies.

  10. Corrective Action Investigation Plan for Corrective Action Unit 166: Storage Yards and Contaminated Materials, Nevada Test Site, Nevada, Rev. No.: 0

    Energy Technology Data Exchange (ETDEWEB)

    David Strand

    2006-06-01

    Corrective Action Unit 166 is located in Areas 2, 3, 5, and 18 of the Nevada Test Site, which is 65 miles northwest of Las Vegas, Nevada. Corrective Action Unit (CAU) 166 is comprised of the seven Corrective Action Sites (CASs) listed below: (1) 02-42-01, Cond. Release Storage Yd - North; (2) 02-42-02, Cond. Release Storage Yd - South; (3) 02-99-10, D-38 Storage Area; (4) 03-42-01, Conditional Release Storage Yard; (5) 05-19-02, Contaminated Soil and Drum; (6) 18-01-01, Aboveground Storage Tank; and (7) 18-99-03, Wax Piles/Oil Stain. These sites are being investigated because existing information on the nature and extent of potential contamination is insufficient to evaluate and recommend corrective action alternatives. Additional information will be obtained by conducting a corrective action investigation (CAI) before evaluating corrective action alternatives and selecting the appropriate corrective action for each CAS. The results of the field investigation will support a defensible evaluation of viable corrective action alternatives that will be presented in the Corrective Action Decision Document. The sites will be investigated based on the data quality objectives (DQOs) developed on February 28, 2006, by representatives of the Nevada Division of Environmental Protection; U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office; Stoller-Navarro Joint Venture; and Bechtel Nevada. The DQO process was used to identify and define the type, amount, and quality of data needed to develop and evaluate appropriate corrective actions for CAU 166. Appendix A provides a detailed discussion of the DQO methodology and the DQOs specific to each CAS. The scope of the CAI for CAU 166 includes the following activities: (1) Move surface debris and/or materials, as needed, to facilitate sampling. (2) Conduct radiological surveys. (3) Perform field screening. (4) Collect and submit environmental samples for laboratory analysis to determine if

  11. CPP-603 Underwater Fuel Storage Facility Site Integrated Stabilization Management Plan (SISMP), Volume I

    International Nuclear Information System (INIS)

    Denney, R.D.

    1995-10-01

    The CPP-603 Underwater Fuel Storage Facility (UFSF) Site Integrated Stabilization Management Plan (SISMP) has been constructed to describe the activities required for the relocation of spent nuclear fuel (SNF) from the CPP-603 facility. These activities are the only Idaho National Engineering Laboratory (INEL) actions identified in the Implementation Plan developed to meet the requirements of the Defense Nuclear Facilities Safety Board (DNFSB) Recommendation 94-1 to the Secretary of Energy regarding an improved schedule for remediation in the Defense Nuclear Facilities Complex. As described in the DNFSB Recommendation 94-1 Implementation Plan, issued February 28, 1995, an INEL Spent Nuclear Fuel Management Plan is currently under development to direct the placement of SNF currently in existing INEL facilities into interim storage, and to address the coordination of intrasite SNF movements with new receipts and intersite transfers that were identified in the DOE SNF Programmatic and INEL Environmental Restoration and Waste Management Environmental Impact Statement Record, of Decision. This SISMP will be a subset of the INEL Spent Nuclear Fuel Management Plan and the activities described are being coordinated with other INEL SNF management activities. The CPP-603 relocation activities have been assigned a high priority so that established milestones will be meet, but there will be some cases where other activities will take precedence in utilization of available resources. The Draft INEL Site Integrated Stabilization Management Plan (SISMP), INEL-94/0279, Draft Rev. 2, dated March 10, 1995, is being superseded by the INEL Spent Nuclear Fuel Management Plan and this CPP-603 specific SISMP

  12. 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

  13. Analysis of superconducting magnetic energy storage applications at a proposed wind farm site near Browning, Montana

    Science.gov (United States)

    Gaustad, K. L.; Desteese, J. G.

    1993-07-01

    A computer program was developed to analyze the viability of integrating superconducting magnetic energy storage (SMES) with proposed wind farm scenarios at a site near Browning, Montana. The program simulated an hour-by-hour account of the charge/discharge history of a SMES unit for a representative wind-speed year. Effects of power output, storage capacity, and power conditioning capability on SMES performance characteristics were analyzed on a seasonal, diurnal, and hourly basis. The SMES unit was assumed to be charged during periods when power output of the wind resource exceeded its average value. Energy was discharged from the SMES unit into the grid during periods of low wind speed to compensate for below-average output of the wind resource. The option of using SMES to provide power continuity for a wind farm supplemented by combustion turbines was also investigated. Levelizing the annual output of large wind energy systems operating in the Blackfeet area of Montana was found to require a storage capacity too large to be economically viable. However, it appears that intermediate-sized SMES economically levelize the wind energy output on a seasonal basis.

  14. Yield and cold storage of Trichoderma conidia is influenced by substrate pH and storage temperature.

    Science.gov (United States)

    Steyaert, Johanna M; Chomic, Anastasia; Nieto-Jacobo, Maria; Mendoza-Mendoza, Artemio; Hay, Amanda J; Braithwaite, Mark; Stewart, Alison

    2017-05-01

    In this study we examined the influence of the ambient pH during morphogenesis on conidial yield of Trichoderma sp. "atroviride B" LU132 and T. hamatum LU593 and storage at low temperatures. The ambient pH of the growth media had a dramatic influence on the level of Trichoderma conidiation and this was dependent on the strain and growth media. On malt-extract agar, LU593 yield decreased with increasing pH (3-6), whereas yield increased with increasing pH for LU132. During solid substrate production the reverse was true for LU132 whereby yield decreased with increasing pH. The germination potential of the conidia decreased significantly over time in cold storage and the rate of decline was a factor of the strain, pH during morphogenesis, growth media, and storage temperature. © 2017 WILEY-VCH Verlag GmbH & Co. KGaA, Weinheim.

  15. Characterization and reclamation assessment for the Central Shops Diesel Storage Facility, Savannah River Site, Aiken, South Carolina

    Energy Technology Data Exchange (ETDEWEB)

    Fliermans, C.B.; Hazen, T.C.; Bledsoe, H.

    1993-10-01

    The contamination of subsurface terrestrial environments by organic contaminants is a global phenomenon. The remediation of such environments requires innovative assessment techniques and strategies for successful clean-ups. Central Shops Diesel Storage Facility at Savannah River Site was characterized to determine the extent of subsurface diesel fuel contamination using innovative approaches and effective bioremediation techniques for clean-up of the contaminant plume have been established.

  16. Sll0528, a Site-2-Protease, Is Critically Involved in Cold, Salt and Hyperosmotic Stress Acclimation of Cyanobacterium Synechocystis sp. PCC 6803

    Directory of Open Access Journals (Sweden)

    Haijin Lei

    2014-12-01

    Full Text Available Site-2-proteases (S2Ps mediated proteolysis of transmembrane transcriptional regulators is a conserved mechanism to regulate transmembrane signaling. The universal presence of S2P homologs in different cyanobacterial genomes suggest conserved and fundamental functions, though limited data has been available. Here we provide the first evidence that Sll0528, a site-2-protease in Synechocystis sp. PCC 6803 is crucial for salt, cold and hyperosmotic stress acclimation. Remarkable induction of sll0528 gene expression was observed under salt, cold and hyperosmotic stress, much higher than induction of the other three S2Ps. Knock-out of sll0528 gene in wild type Synechocystis sp. PCC 6803 increased their sensitivity to salt, cold and hyperosmotic stress, as revealed by retarded growth, reduced pigments and disrupted photosystems. The sll0528 gene was induced to a much smaller extent by high light and mixotrophic growth with glucose. Similar growth responses of the sll0528 knockout mutant and wild type under high light and mixotrophic growth indicated that sll0528 was dispensable for these conditions. Recombinant Sll0528 protein could cleave beta-casein into smaller fragments. These results together suggest that the Sll0528 metalloprotease plays a role in the stress response and lays the foundation for further investigation of its mechanism, as well as providing hints for the functional analysis of other S2Ps in cyanobacteria.

  17. Operation Iraqi Freedom: DOD Should Apply Lessons Learned Concerning the Need for Security over Conventional Munitions Storage Sites to Future Operations Planning

    National Research Council Canada - National Science Library

    D'Agostino, Davi M

    2007-01-01

    The Government Accountability Office (GAO) is releasing a report today on lessons learned concerning the need for security over conventional munitions storage sites that provides the basis for this testimony...

  18. Spent fuel storage options: a critical appraisal

    International Nuclear Information System (INIS)

    Singh, K.P.; Bale, M.G.

    1990-01-01

    The delayed decisions on nuclear fuel reprocessing strategies in the USA and other countries have forced the development of new long-term irradiated fuel storage techniques, to allow a larger volume of fuel to be held on the nuclear station site after removal from the reactor. The nuclear power industry has responded to the challenge by developing several viable options for long-term onsite storage, which can be employed individually or in tandem. They are: densification of storage in the existing spent fuel pool; building another fuel pool facility at the plant site; onsite cask park, and on site vault clusters. Desirable attributes of a storage option are: Safety: minimise the number of fuel handling steps; Economy: minimise total installed, and O and M cost; Security: protection from anti-nuclear protesters; Site adaptability: available site space, earthquake characteristics of the region and so on; Non-intrusiveness: minimise required modifications to existing plant systems; Modularisation: afford the option to adapt a modular approach for staged capital outlays; and Maturity: extent of industry experience with the technology. A critical appraisal is made of each of the four aforementioned storage options in the light of these criteria. (2 figures, 1 table, 4 references) (Author)

  19. Management of Hanford Site non-defense production reactor spent nuclear fuel, Hanford Site, Richland, Washington

    International Nuclear Information System (INIS)

    1997-03-01

    The US Department of Energy (DOE) needs to provide radiologically, and industrially safe and cost-effective management of the non-defense production reactor spent nuclear fuel (SNF) at the Hanford Site. The proposed action would place the Hanford Site's non-defense production reactor SNF in a radiologically- and industrially-safe, and passive storage condition pending final disposition. The proposed action would also reduce operational costs associated with storage of the non-defense production reactor SNF through consolidation of the SNF and through use of passive rather than active storage systems. Environmental, safety and health vulnerabilities associated with existing non-defense production reactor SNF storage facilities have been identified. DOE has determined that additional activities are required to consolidate non-defense production reactor SNF management activities at the Hanford Site, including cost-effective and safe interim storage, prior to final disposition, to enable deactivation of facilities where the SNF is now stored. Cost-effectiveness would be realized: through reduced operational costs associated with passive rather than active storage systems; removal of SNF from areas undergoing deactivation as part of the Hanford Site remediation effort; and eliminating the need to duplicate future transloading facilities at the 200 and 400 Areas. Radiologically- and industrially-safe storage would be enhanced through: (1) removal from aging facilities requiring substantial upgrades to continue safe storage; (2) utilization of passive rather than active storage systems for SNF; and (3) removal of SNF from some storage containers which have a limited remaining design life. No substantial increase in Hanford Site environmental impacts would be expected from the proposed action. Environmental impacts from postulated accident scenarios also were evaluated, and indicated that the risks associated with the proposed action would be small

  20. Report on technical feasibility of underground pumped hydroelectric storage in a marble quarry site in the Northeast United States

    Energy Technology Data Exchange (ETDEWEB)

    Chas. T. Main, Inc.

    1982-03-01

    The technical and economic aspects of constructing a very high head underground hydroelectric pumped storage were examined at a prefeasibility level. Excavation of existing caverns in the West Rutland Vermont marble quarry would be used to construct the underground space. A plant capacity of 1200 MW and 12 h of continuous capacity were chosen as plant operating conditions. The site geology, plant design, and electrical and mechanical equipment required were considered. The study concluded that the cost of the 1200 MW underground pumped storage hydro electric project at this site even with the proposed savings from marketable material amounts to between $581 and $595 per kilowatt of installed capacity on a January 1982 pricing level. System studies performed by the planning group of the New England Power System indicate that the system could economically justify up to about $442 per kilowatt on an energy basis with no credit for capacity. To accommodate the plant with the least expensive pumping energy, a coal and nuclear generation mix of approximately 65% would have to be available before the project becomes feasible. It is not expected that this condition can be met before the year 2000 or beyond. It is therefore concluded that the West Rutland underground pumped storage facility is uneconomic at this time. Several variables however could have marked influence on future planning and should be examined on periodic basis.

  1. Corrective Action Investigation Plan for Corrective Action Unit 145: Wells and Storage Holes, Nevada Test Site, Nevada, Rev. No.: 0

    Energy Technology Data Exchange (ETDEWEB)

    David A. Strand

    2004-09-01

    This Corrective Action Investigation Plan (CAIP) contains project-specific information for conducting site investigation activities at Corrective Action Unit (CAU) 145: Wells and Storage Holes. Information presented in this CAIP includes facility descriptions, environmental sample collection objectives, and criteria for the selection and evaluation of environmental samples. Corrective Action Unit 145 is located in Area 3 of the Nevada Test Site, which is 65 miles northwest of Las Vegas, Nevada. Corrective Action Unit 145 is comprised of the six Corrective Action Sites (CASs) listed below: (1) 03-20-01, Core Storage Holes; (2) 03-20-02, Decon Pad and Sump; (3) 03-20-04, Injection Wells; (4) 03-20-08, Injection Well; (5) 03-25-01, Oil Spills; and (6) 03-99-13, Drain and Injection Well. These sites are being investigated because existing information on the nature and extent of potential contamination is insufficient to evaluate and recommend corrective action alternatives. Additional information will be obtained by conducting a corrective action investigation (CAI) prior to evaluating corrective action alternatives and selecting the appropriate corrective action for each CAS. The results of the field investigation will support a defensible evaluation of viable corrective action alternatives that will be presented in the Corrective Action Decision Document. One conceptual site model with three release scenario components was developed for the six CASs to address all releases associated with the site. The sites will be investigated based on data quality objectives (DQOs) developed on June 24, 2004, by representatives of the Nevada Division of Environmental Protection; U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office; Stoller-Navarro Joint Venture; and Bechtel Nevada. The DQOs process was used to identify and define the type, amount, and quality of data needed to develop and evaluate appropriate corrective actions for CAU 145.

  2. Procedures for the site location of an storage centre of medium and low level radioactive wastes

    International Nuclear Information System (INIS)

    Pena G, P.; Garcia B, M.

    2001-01-01

    In order to establish the procedures for the location of a new and definitive storage center for medium and low level radioactive wastes which will be the place where confining, controlling and keeping those waste products of radioactive materials which were used in the hospitable centers, clinics and institutions (research and techniques development) as well as those obtained from industry. The site studies for nuclear facilities, require the participation of a several professionals with different specialities to be able to make use of competence in different disciplines. The result is the exclusion of unacceptable zones followed them by a pre-selection, a selection and a systematic comparison of those sites which are in the remaining zones considered as acceptable. (Author)

  3. Sp1/3 and NF-1 mediate basal transcription of the human P2X1 gene in megakaryoblastic MEG-01 cells

    Directory of Open Access Journals (Sweden)

    Ennion Steven J

    2006-03-01

    Full Text Available Abstract Background P2X1 receptors play an important role in platelet function as they can induce shape change, granule centralization and are also involved in thrombus formation. As platelets have no nuclei, the level of P2X1 expression depends on transcriptional regulation in megakaryocytes, the platelet precursor cell. Since nothing is known about the molecular mechanisms regulating megakaryocytic P2X1 expression, this study aimed to identify and functionally characterize the P2X1 core promoter utilized in the human megakaryoblastic cell line MEG-01. Results In order to identify cis-acting elements involved in the transcriptional regulation of P2X1 expression, the ability of 4.7 kb P2X1 upstream sequence to drive luciferase reporter gene expression was tested. Low promoter activity was detected in proliferating MEG-01 cells. This activity increased 20-fold after phorbol-12-myristate-13-acetate (PMA induced differentiation. A transcription start site was detected 365 bp upstream of the start codon by primer extension. Deletion analysis of reporter constructs indicated a core promoter located within the region -68 to +149 bp that contained two Sp1 sites (named Sp1a and Sp1b and an NF-1 site. Individual mutations of Sp1b or NF-1 binding sites severely reduced promoter activity whereas triple mutation of Sp1a, Sp1b and NF-1 sites completely abolished promoter activity in both untreated and PMA treated cells. Sp1/3 and NF-1 proteins were shown to bind their respective sites by EMSA and interaction of Sp1/3, NF-1 and TFIIB with the endogenous P2X1 core promoter in MEG-01 cells was demonstrated by chromatin immunoprecipitation. Alignment of P2X1 genes from human, chimp, rat, mouse and dog revealed consensus Sp1a, Sp1b and NF-1 binding sites in equivalent positions thereby demonstrating evolutionary conservation of these functionally important sites. Conclusion This study has identified and characterized the P2X1 promoter utilized in MEG-01 cells and

  4. Low-Level Radioactive Waste temporary storage issues

    International Nuclear Information System (INIS)

    1992-04-01

    The Low-Level Radioactive Waste Policy Act of 1980 gave responsibility for the disposal of commercially generated low-level radioactive waste to the States. The Low-Level Radioactive Waste Policy Amendments Act of 1985 attached additional requirements for specific State milestones. Compact regions were formed and host States selected to establish disposal facilities for the waste generated within their borders. As a result of the Low-Level Radioactive Waste Policy Amendments Act of 1985, the existing low-level radioactive waste disposal sites will close at the end of 1992; the only exception is the Richland, Washington, site, which will remain open to the Northwest Compact region only. All host States are required to provide for disposal of low-level radioactive waste by January 1, 1996. States also have the option of taking title to the waste after January 1, 1993, or taking title by default on January 1, 1996. Low-level radioactive waste disposal will not be available to most States on January 1, 1993. The most viable option between that date and the time disposal is available is storage. Several options for storage can be considered. In some cases, a finite storage time will be permitted by the Nuclear Regulatory Commission at the generator site, not to exceed five years. If disposal is not available within that time frame, other options must be considered. There are several options that include some form of extension for storage at the generator site, moving the waste to an existing storage site, or establishing a new storage facility. Each of these options will include differing issues specific to the type of storage sought

  5. Temporary storage area characterization report

    International Nuclear Information System (INIS)

    1990-01-01

    The preferred alternative identified in the Remedial Investigation/Feasibility Study (RI/FS) for the Weldon Spring Quarry Bulk Wastes is to remove the wastes from the quarry and transport them by truck to temporary storage facility at the chemical plant site. To support the RI/FS, this report provides data to characterize the temporary storage area (TSA) site and to ensure the suitability of the proposed location. 31 refs., 14 figs., 7 tabs

  6. Radioactive waste interim storage in Germany

    International Nuclear Information System (INIS)

    2015-12-01

    The short summary on the radioactive waste interim storage in Germany covers the following issues: importance of interim storage in the frame of radioactive waste management, responsibilities and regulations, waste forms, storage containers, transport of vitrified high-level radioactive wastes from the reprocessing plants, central interim storage facilities (Gorleben, Ahaus, Nord/Lubmin), local interim storage facilities at nuclear power plant sites, federal state collecting facilities, safety, radiation exposure in Germany.

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

    International Nuclear Information System (INIS)

    Stoffle, R.W.; Traugott, M.J.; Stone, J.V.; McIntyre, P.D.; Davidson, C.C.; Jensen, F.V.; Coover, G.E.

    1990-01-01

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

  8. The gamma ray spectrometer GA.SP

    Energy Technology Data Exchange (ETDEWEB)

    Bazzacco, D [Instituto Nazionale di Fisica Nucleare, Sezione di Padova, Padova (Italy)

    1992-08-01

    GA.SP is a general purpose 4{pi} detector array for advanced {gamma}-spectroscopy and, in the same time, a suitable system for reaction mechanism studies. The detector is sited at the LNL Tandem+Linac accelerator and has been built as a joint project of INFN Padova, LNL, Milano and Firenze. The array consists of 40 Compton suppressed HPGe detectors and of a 4{pi} calorimeter composed of 80 BGO crystals. The detector houses a reaction chamber of 34 cm diameter where a charged particles multiplicity filter composed of 40 Si detectors is going to be installed. Evaporation residues produced in the centre of GA.SP can be injected into the recoil mass spectrometer (RMS, named CAMEL) in use at LNL, without the need to remove any of the gamma detectors. The coupled operation of GA.SP, RMS and Si ball will give a unique instrument for identification and study of weak reaction channels. (author). 6 figs.

  9. The gamma ray spectrometer GA.SP

    International Nuclear Information System (INIS)

    Bazzacco, D.

    1992-01-01

    GA.SP is a general purpose 4π detector array for advanced γ-spectroscopy and, in the same time, a suitable system for reaction mechanism studies. The detector is sited at the LNL Tandem+Linac accelerator and has been built as a joint project of INFN Padova, LNL, Milano and Firenze. The array consists of 40 Compton suppressed HPGe detectors and of a 4π calorimeter composed of 80 BGO crystals. The detector houses a reaction chamber of 34 cm diameter where a charged particles multiplicity filter composed of 40 Si detectors is going to be installed. Evaporation residues produced in the centre of GA.SP can be injected into the recoil mass spectrometer (RMS, named CAMEL) in use at LNL, without the need to remove any of the gamma detectors. The coupled operation of GA.SP, RMS and Si ball will give a unique instrument for identification and study of weak reaction channels. (author). 6 figs

  10. Spent fuel storage requirements: the need for away-from-reactor storage

    International Nuclear Information System (INIS)

    1980-01-01

    The analyses of on-site storage capabilities of domestic utilities and estimates of timing and magnitude of away-from-reactor (AFR) storage requirements were presented in the report DOE/ET-0075 entitled Spent Fuel Storage Requirements: The Need For Away-From-Reactor Storage published in February 1979 by the US Department of Energy. Since utility plans and requirements continue to change with time, a need exists to update the AFR requirements estimates as appropriate. This short report updates the results presented in DOE/ET-0075 to reflect recent data on reactor operations and spent fuel storage. In addition to the updates of cases representing the range of AFR requirements in DOE/ET-0075, new cases of interest reflecting utility and regulatory trends are presented

  11. Final Report, 2011-2014. Forecasting Carbon Storage as Eastern Forests Age. Joining Experimental and Modeling Approaches at the UMBS AmeriFlux Site

    Energy Technology Data Exchange (ETDEWEB)

    Curtis, Peter [The Ohio State Univ., Columbus, OH (United States); Bohrer, Gil [The Ohio State Univ., Columbus, OH (United States); Gough, Christopher [Virginia Commonwealth Univ., Richmond, VA (United States); Nadelhoffer, Knute [Univ. of Michigan, Ann Arbor, MI (United States)

    2015-03-12

    At the University of Michigan Biological Station (UMBS) AmeriFlux sites (US-UMB and US-UMd), long-term C cycling measurements and a novel ecosystem-scale experiment are revealing physical, biological, and ecological mechanisms driving long-term trajectories of C cycling, providing new data for improving modeling forecasts of C storage in eastern forests. Our findings provide support for previously untested hypotheses that stand-level structural and biological properties constrain long-term trajectories of C storage, and that remotely sensed canopy structural parameters can substantially improve model forecasts of forest C storage. Through the Forest Accelerated Succession ExperimenT (FASET), we are directly testing the hypothesis that forest C storage will increase due to increasing structural and biological complexity of the emerging tree communities. Support from this project, 2011-2014, enabled us to incorporate novel physical and ecological mechanisms into ecological, meteorological, and hydrological models to improve forecasts of future forest C storage in response to disturbance, succession, and current and long-term climate variation

  12. Colonie Interim Storage Site environmental report for calendar year 1992, 1130 Central Avenue, Colonie, New York. Formerly Utilized Sites Remedial Action Program (FUSRAP)

    Energy Technology Data Exchange (ETDEWEB)

    1993-05-01

    This report describes the environmental surveillance program at the Colonie Interim Storage Site (CISS) and provides the results for 1992. The site is located in eastern New York State, approximately 6.4 km (4.0 mi) northwest of downtown Albany. From 1958 to 1984, National Lead (NL) Industries used the facility to manufacture various components from depleted and enriched uranium natural thorium. Environmental monitoring of CISS began in 1984 when Congress added, the site to the US Department of Energy`s (DOE) Formerly Utilized Sites Remedial Action Program (FUSRAP). FUSRAP is a program established to identify and decontaminate or otherwise control sites where residual radioactive materials remain from the early years of the nation`s atomic energy program or from commercial operations causing conditions that Congress has authorized DOE to remedy. The environmental surveillance program at CISS includes sampling networks for external gamma radiation exposure and for thorium-232 and total uranium concentrations in surface water, sediment, and groundwater. Several chemical parameters are also measured in groundwater, including total metals, volatile organics, and water quality parameters. This surveillance program assists in fulfilling the DOE policy of measuring and monitoring effluents from DOE activities and calculating hypothetical doses. Results are compared with applicable Environmental Protection Agency (EPA) and New York State Department of Environmental Conservation (NYSDEC) standards, DOE derived concentration guides (DCGs), dose limits, and other DOE requirements.

  13. Summary of treatment, storage, and disposal facility usage data collected from U.S. Department of Energy sites

    International Nuclear Information System (INIS)

    Jacobs, A.; Oswald, K.; Trump, C.

    1995-04-01

    This report presents an analysis for the US Department of Energy (DOE) to determine the level and extent of treatment, storage, and disposal facility (TSDF) assessment duplication. Commercial TSDFs are used as an integral part of the hazardous waste management process for those DOE sites that generate hazardous waste. Data regarding the DOE sites' usage have been extracted from three sets of data and analyzed in this report. The data are presented both qualitatively and quantitatively, as appropriate. This information provides the basis for further analysis of assessment duplication to be documented in issue papers as appropriate. Once the issues have been identified and adequately defined, corrective measures will be proposed and subsequently implemented

  14. Geological characterization of CO{sub 2} storage sites: lessons from Sleipner, Northern North Sea

    Energy Technology Data Exchange (ETDEWEB)

    R.A. Chadwick; P. Zweigel; U. Gregersen; G.A. Kirby; S. Holloway; P.N. Johannessen [British Geological Survey, Keyworth (United Kingdom). Kingsley Dunham Centre

    2003-07-01

    The paper aims to draw some generic conclusions on reservoir characterization based on the Sleipner operation in the North Sea where CO{sub 2} is being injected into the Utsira Sand, a saline aquifer. Regional mapping and petrophysical characterization of the reservoir, based on 2D seismic and well data, enable gross storage potential to be evaluated. Site specific injection studies, however, require precision depth mapping based on 3D seismic data and detailed knowledge of reservoir stratigraphy. Stratigraphical and structural permeability barriers, difficult to detect prior to CO{sub 2} injection, can radically affect CO{sub 2} migration within the aquifer. 5 refs., 5 figs.

  15. Soil structure interaction analysis for the Hanford Site 241-SY-101 double-shell waste storage tanks

    International Nuclear Information System (INIS)

    Giller, R.A.; Weiner, E.O.

    1991-09-01

    The 241-SY-101 tank is a double-shell waste storage tank buried in the 241-SY tank farm in the 200 West Area of the Hanford Site. This analysis addresses the effects of seismic soil-structure interaction on the tank structure and includes a parametric soil-structure interaction study addressing three configurations: two-dimensional soil structure, a two-dimensional structure-soil-structure, and a three-dimensional soil-structure interaction. This study was designed to determine an optimal method for addressing seismic-soil effects on underground storage tanks. The computer programs calculate seismic-soil pressures on the double-shell tank walls and and seismic acceleration response spectra in the tank. The results of this soil-structure interaction parametric study as produced by the computer programs are given in terms of seismic soil pressures and response spectra. The conclusions of this soil-structure interaction evaluation are that dynamically calculated soil pressures in the 241-SY-101 tank are significantly reduce from those using standard hand calculation methods and that seismic evaluation of underground double-shell waste storage tanks must consider soil-structure interaction effects in order to predict conservative structural response. Appendixes supporting this study are available in Volume 2 of this report

  16. Effect of moisture content and storage conditions on the storability of ...

    African Journals Online (AJOL)

    STORAGESEVER

    2008-12-17

    Dec 17, 2008 ... Rhizopus sp. were more abundant with increasing moisture content. Air-tight .... jute bag. The aim of this study is to evaluate the role of moisture and storage .... be due to contamination as a result of local method of processing.

  17. Report by the committee assessing fuel storage

    International Nuclear Information System (INIS)

    Morgan, W.W.

    1977-11-01

    Various concepts for interim storage of spent nuclear fuel have been considered. Preliminary design studies and cost estimates have been prepared for the following concepts: two with water cooling - prolonged pool storage at a generating station and pool storage at a central site - , three with air cooling at a central site - ''canister'', ''convection vault'', and ''conduction vault'' - and one underground storage scheme in rock salt. Costs (1972 dollars) were estimated including transportation and a perpetual care fund for maintenance and periodical renewal of the storage facility. Part 2 provides details of the concepts and costing methods. All concepts gave moderate costs providing a contribution of about 0.1 m$/kWh to the total unit energy cost. Advantages and disadvantages of the respective schemes are compared. (author)

  18. A General Catalyst for Site-Selective C(sp(3))-H Bond Amination of Activated Secondary over Tertiary Alkyl C(sp(3))-H Bonds.

    Science.gov (United States)

    Scamp, Ryan J; Jirak, James G; Dolan, Nicholas S; Guzei, Ilia A; Schomaker, Jennifer M

    2016-06-17

    The discovery of transition metal complexes capable of promoting general, catalyst-controlled and selective carbon-hydrogen (C-H) bond amination of activated secondary C-H bonds over tertiary alkyl C(sp(3))-H bonds is challenging, as substrate control often dominates when reactive nitrene intermediates are involved. In this letter, we report the design of a new silver complex, [(Py5Me2)AgOTf]2, that displays general and good-to-excellent selectivity for nitrene insertion into propargylic, benzylic, and allylic C-H bonds over tertiary alkyl C(sp(3))-H bonds.

  19. Monitored Retrievable Storage System Requirements Document

    International Nuclear Information System (INIS)

    1994-03-01

    This Monitored Retrievable Storage System Requirements Document (MRS-SRD) describes the functions to be performed and technical requirements for a Monitored Retrievable Storage (MRS) facility subelement and the On-Site Transfer and Storage (OSTS) subelement. The MRS facility subelement provides for temporary storage, at a Civilian Radioactive Waste Management System (CRWMS) operated site, of spent nuclear fuel (SNF) contained in an NRC-approved Multi-Purpose Canister (MPC) storage mode, or other NRC-approved storage modes. The OSTS subelement provides for transfer and storage, at Purchaser sites, of spent nuclear fuel (SNF) contained in MPCs. Both the MRS facility subelement and the OSTS subelement are in support of the CRWMS. The purpose of the MRS-SRD is to define the top-level requirements for the development of the MRS facility and the OSTS. These requirements include design, operation, and decommissioning requirements to the extent they impact on the physical development of the MRS facility and the OSTS. The document also presents an overall description of the MRS facility and the OSTS, their functions (derived by extending the functional analysis documented by the Physical System Requirements (PSR) Store Waste Document), their segments, and the requirements allocated to the segments. In addition, the top-level interface requirements of the MRS facility and the OSTS are included. As such, the MRS-SRD provides the technical baseline for the MRS Safety Analysis Report (SAR) design and the OSTS Safety Analysis Report design

  20. Rethinking the economics of centralized spent fuel storage

    International Nuclear Information System (INIS)

    Wood, T.W.; Short, S.M.; Dippold, D.G.; Rod, S.R.; Williams, J.W.

    1991-04-01

    The technology for extended storage of spent nuclear fuel (SNF), either at-reactor or in a centralized facility such as a monitored retrievable storage (MRS) facility, is well-developed and proven from an engineering and safety perspective. The question of whether spent fuel should await its final geologic disposal while at a reactor site or in an MRS facility is essentially an economic one. While intuition and previous results suggest that centralized storage will be more economical than at-reactor storage beyond some break-even quantity of SNF, the incremental costs of pool storage at-reactor are close to zero as long as pool capacity is generally available. Thus, if economics is the prime motivator, the quantity of spent fuel required to warrant centralized storage could be quite large. The economics of centralizing the storage of spent fuel at a single site, as opposed to continued storage at over 100 reactor sites, has been the subject of several recent analyses. Most of these analyses involved calculating the benefits of an MRS facility with a pre-defined MRS operating scenario. This paper reverses this approach to economic analysis of the MRS by seeking the optimal MRS operating scenario (in terms of the parameters listed above) implied by the economic incentives arising from the relative costs of at-reactor storage and centralized storage. This approach treats an MRS as a possible storage location that will be used according to its economic value in system operation. 5 refs., 5 figs

  1. Aktivitas minyak dan serbuk enam spesies tumbuhan terhadap peneluran dan Mortalitas Callosobruchus sp. (Coleoptera: Bruchidae

    Directory of Open Access Journals (Sweden)

    Dadang Dadang

    2017-02-01

    Full Text Available Storage pests remain one of the main problems in storage. The pest attacks occur not only in the field, but also in storage. Control should be done to maintain the quality of storedproducts. The environmentally friendly measures should be implemented to avoid negative impacts to the environment and human being. The objective of this research was to study the mortality and oviposition deterrence caused by powder and oil of six plant species against Callosobruchus sp. (Coleoptera: Bruchidae. Flowers of Eugenia aromatica, roots of Vetiveria zizanioides, leaves of Pogostemon cablin, seeds of Ricinus communis, seeds of Foeniculum vulgare, and stems of Cymbopogon citratus were air-dried and milled to yield powder. Oil of six plant species were purchased from local market. Oviposition deterrent bioassay was conducted by no-choice method for both powder and oil, while mortality bioassay was conducted by topical application and residual methods for plant oil only. Several plant species showed high biological activity to Callosobruchus sp. Powder of E. aromatica and oil of V. zizanioides caused high oviposition deterrence, while oil of V. zizanioides and E. aromatica caused high mortality.

  2. Ground testing of an SP-100 prototypic reactor

    International Nuclear Information System (INIS)

    Motwani, K.; Pflasterer, G.R.; Upton, H.; Lazarus, J.D.; Gluck, R.

    1988-01-01

    SP-100 is a space power system which is being developed by GE to meet future space electrical power requirements. The ground testing of an SP-100 prototypic reactor system will be conducted at the Westinghouse Hanford Company site located at Richland, Washington. The objective of this test is to demonstrate the performance of a full scale prototypic reactor system, including the reactor, control system and flight shield. The ground test system is designed to simulate the flight operating conditions while meeting all the necessary nuclear safety requirements in a gravity environment. The goal of the reactor ground test system is to establish confidence in the design maturity of the SP-100 space reactor power system and resolve the technical issues necessary for the development of a flight mission design

  3. Occupational radiation dose assessment for a non site specific spent fuel storage facility

    International Nuclear Information System (INIS)

    Hadley, J.; Eble, R.G. Jr.

    1997-01-01

    To expedite the licensing process of the non site specific Centralized Interim Storage Facility (CISF) the Department of Energy has completed a phase I CISF Topical Safety Analysis Report (TSAR). The TSAR will be used in licensing the phase I CISF if a site is designated. An occupational radiation does assessment of the facility operations is performed as part of the phase I CISF design. The first phase of the CISF has the capability to receive, transfer, and store SNF in dual-purpose cask/canister systems (DPC's). Currently there are five vendor technologies under consideration. The preliminary dose assessment is based on estimated occupational exposures using traditional power plant ISFSI and transport cask handling processes. The second step in the process is to recommend ALARA techniques to reduce potential exposures. A final dose assessment is completed implementing the ALARA techniques and a review is performed to ensure that the design is in compliance with regulatory criteria. The dose assessment and ALARA evaluation are determined using the following input information: Dose estimates from vendor SAR's; ISFSI experience with similar systems; Traditional methods of operations; Expected CISF cask receipt rates; and feasible ALARA techniques. 5 refs., 1 tab

  4. Hybrid model predictive control of a residential HVAC system with on-site thermal energy generation and storage

    International Nuclear Information System (INIS)

    Fiorentini, Massimo; Wall, Josh; Ma, Zhenjun; Braslavsky, Julio H.; Cooper, Paul

    2017-01-01

    Highlights: • A comprehensive approach to managing thermal energy in residential buildings. • Solar-assisted HVAC system with on-site energy generation and storage. • Mixed logic-dynamical building model identified using experimental data. • Design and implementation of a logic-dynamical model predictive control strategy. • MPC applied to the Net-Zero Energy house winner of the Solar Decathlon China 2013. - Abstract: This paper describes the development, implementation and experimental investigation of a Hybrid Model Predictive Control (HMPC) strategy to control solar-assisted heating, ventilation and air-conditioning (HVAC) systems with on-site thermal energy generation and storage. A comprehensive approach to the thermal energy management of a residential building is presented to optimise the scheduling of the available thermal energy resources to meet a comfort objective. The system has a hybrid nature with both continuous variables and discrete, logic-driven operating modes. The proposed control strategy is organized in two hierarchical levels. At the high-level, an HMPC controller with a 24-h prediction horizon and a 1-h control step is used to select the operating mode of the HVAC system. At the low-level, each operating mode is optimised using a 1-h rolling prediction horizon with a 5-min control step. The proposed control strategy has been practically implemented on the Building Management and Control System (BMCS) of a Net Zero-Energy Solar Decathlon house. This house features a sophisticated HVAC system comprising of an air-based photovoltaic thermal (PVT) collector and a phase change material (PCM) thermal storage integrated with the air-handling unit (AHU) of a ducted reverse-cycle heat pump system. The simulation and experimental results demonstrated the high performance achievable using an HMPC approach to optimising complex multimode HVAC systems in residential buildings, illustrating efficient selection of the appropriate operating modes

  5. Benefits and applications of modular hydroelectric pumped storage

    International Nuclear Information System (INIS)

    Koebbe, R.S.

    1991-01-01

    This paper reports on hydroelectric pumped storage which is the only proven and most efficient technology available for energy storage. It is used by utilities to provide peak and intermediate power and to optimize overall system performance. Because of increased environmental and regulatory constraints, few acceptable sites, long schedules, and huge financial commitments, large conventional pumped storage plants, are now virtually impossible to build. As an alternative, small modular pumped storage, with project sizes ranging from 25 MW to 200 MW, was created to overcome the difficulties of conventional projects. The modular approach involves standardizing the elements of a pumped storage plant by utilizing specialized siting techniques and optimizing design, equipment, and construction. Compared with conventional pumped storage, the modular design can reduce cost and expedite schedule; reduce environmental concerns and permitting obstacles; and expand applications of energy storage on a utility's system

  6. Second law characterization of stratified thermal storage tanks

    Energy Technology Data Exchange (ETDEWEB)

    Fraidenraich, N [Departamento de Energia Nuclear-UFPE (Brazil)

    2000-07-01

    It is well known that fluid stratification in thermal storage tanks improves the overall performance of solar thermal systems, when compared with systems operating with uniform fluid temperature. From the point of view of the first law of thermodynamics, no difference exists between storage tanks with the same mass and average temperature, even if they have different stratified thermal structures. Nevertheless, the useful thermal energy that can be obtained from them might differ significantly. In this work, we derive an expression able to characterize the stratified configuration of thermal fluid. Using results obtained by thermodynamics of irreversible processes, the procedure adopted consists in calculating the maximum work available from the tank's thermal layer is able to develop. We arrive, then, at a dimensionless expression, the stratification parameter (SP), which depends on the mass fraction and absolute temperature of each thermal layer as well as the thermal fluid average temperature. Numerical examples for different types of tank stratification are given and it is verified that the expression obtained is sensitive to small differences in the reservoir thermal configuration. For example a thermal storage with temperatures equal to 74 Celsius degrees, 64 Celsius degrees and 54 Celsius degrees, with its mass equally distributed along the tank yields, for the parameter SP, a figure equal to 0.000294. On the other hand a storage tank with the same average temperature but with different layer's temperatures 76 Celsius degrees, 64 and 52 Celsius degrees, also with uniform mass distribution, yields for SP a value equal to quantitative evaluation of the stratification structure of thermal reservoirs. [Spanish] Es bien conocido que la estratificacion fluida en tanques de almacenamiento termico mejora el rendimiento total de los sistemas termicos solares en comparacion con sistemas que operan con temperatura uniforme del fluido. Desde el punto de vista

  7. Storage of Spent Nuclear Fuel. Specific Safety Guide

    International Nuclear Information System (INIS)

    2012-01-01

    This Safety Guide provides recommendations and guidance on the storage of spent nuclear fuel. It covers all types of storage facilities and all types of spent fuel from nuclear power plants and research reactors. It takes into consideration the longer storage periods that have become necessary owing to delays in the development of disposal facilities and the decrease in reprocessing activities. It also considers developments associated with nuclear fuel, such as higher enrichment, mixed oxide fuels and higher burnup. The Safety Guide is not intended to cover the storage of spent fuel if this is part of the operation of a nuclear power plant or spent fuel reprocessing facility. Guidance is provided on all stages for spent fuel storage facilities, from planning through siting and design to operation and decommissioning, and in particular retrieval of spent fuel. Contents: 1. Introduction; 2. Protection of human health and the environment; 3. Roles and responsibilities; 4. Management system; 5. Safety case and safety assessment; 6. General safety considerations for storage of spent fuel. Appendix I: Specific safety considerations for wet or dry storage of spent fuel; Appendix II: Conditions for specific types of fuel and additional considerations; Annex: I: Short term and long term storage; Annex II: Operational and safety considerations for wet and dry spent fuel storage facilities; Annex III: Examples of sections of operating procedures for a spent fuel storage facility; Annex IV: Site conditions, processes and events for consideration in a safety assessment (external human induced phenomena); Annex V: Site conditions, processes and events for consideration in a safety assessment (external natural phenomena); Annex VI: Site conditions, processes and events for consideration in a safety assessment (external human induced phenomena); Annex VII: Postulated initiating events for consideration in a safety assessment (internal phenomena).

  8. Evaluation of Final Radiological Conditions at Areas of the Niagara Falls Storage Site Remediated under the Formerly Utilized Sites Remedial Action Program -12184

    Energy Technology Data Exchange (ETDEWEB)

    Clayton, Christopher [U.S Department of Energy Office of Legacy Management, Washington, DC; Kothari, Vijendra [U.S Department of Energy Office of Legacy Management, Morgantown, West Virginia; Starr, Ken [U.S Department of Energy Office of Legacy Management, Westminster, Colorado; Widdop, Michael; Gillespie, Joey [SM Stoller Corporation, Grand Junction, Colorado

    2012-02-26

    The U. S. Department of Energy (DOE) methods and protocols allow evaluation of remediation and final site conditions to determine if remediated sites remain protective. Two case studies are presented that involve the Niagara Falls Storage Site (NFSS) and associated vicinity properties (VPs), which are being remediated under the Formerly Utilized Sites Remedial Action Program (FUSRAP). These properties are a part of the former Lake Ontario Ordnance Works (LOOW). In response to stakeholders concerns about whether certain remediated NFSS VPs were putting them at risk, DOE met with stakeholders and agreed to evaluate protectiveness. Documentation in the DOE records collection adequately described assessed and final radiological conditions at the completed VPs. All FUSRAP wastes at the completed sites were cleaned up to meet DOE guidelines for unrestricted use. DOE compiled the results of the investigation in a report that was released for public comment. In conducting the review of site conditions, DOE found that stakeholders were also concerned about waste from the Separations Process Research Unit (SPRU) at the Knolls Atomic Power Laboratory (KAPL) that was handled at LOOW. DOE agreed to determine if SPRU waste remained at that needed to be remediated. DOE reviewed records of waste characterization, historical handling locations and methods, and assessment and remediation data. DOE concluded that the SPRU waste was remediated on the LOOW to levels that pose no unacceptable risk and allow unrestricted use and unlimited exposure. This work confirms the following points as tenets of an effective long-term surveillance and maintenance (LTS&M) program: Stakeholder interaction must be open and transparent, and DOE must respond promptly to stakeholder concerns. DOE, as the long-term custodian, must collect and preserve site records in order to demonstrate that remediated sites pose no unacceptable risk. DOE must continue to maintain constructive relationships with the U

  9. 2727-S Nonradioactive Dangerous Waste Storage Facility Closure Plan

    International Nuclear Information System (INIS)

    Wilczek, T.A.; Laws, J.R.; Izatt, R.D.

    1992-01-01

    This closure plan describes the activities for final closure of the 2727-S Nonradioactive Dangerous Waste Storage (NRDWS) Facility at the Hanford Site. The 2727-S NRDWS Facility provided container storage for nonradioactive dangerous and extremely hazardous wastes generated in the research and development laboratories, process operations, and maintenance and transportation functions throughout the Hanford Site. Storage operations began at the 2727-S NRDWS Facility March 14, 1983, and continued until December 30, 1986, when the last shipment of materials from the facility took place. These storage operations have been moved to the new 616 NRDWS Facility, which is an interim status unit located between the 200 East and 200 West Areas of the Hanford Site

  10. Transcriptional activation of transforming growth factor alpha by estradiol: requirement for both a GC-rich site and an estrogen response element half-site.

    Science.gov (United States)

    Vyhlidal, C; Samudio, I; Kladde, M P; Safe, S

    2000-06-01

    17beta-Estradiol (E2) induces transforming growth factor alpha (TGFalpha) gene expression in MCF-7 cells and previous studies have identified a 53 bp (-252 to -200) sequence containing two imperfect estrogen responsive elements (EREs) that contribute to E2 responsiveness. Deletion analysis of the TGFalpha gene promoter in this study identified a second upstream region of the promoter (-623 to -549) that is also E2 responsive. This sequence contains three GC-rich sites and an imperfect ERE half-site, and the specific cis-elements and trans-acting factors were determined by promoter analysis in transient transfection experiments, gel mobility shift assays and in vitro DNA footprinting. The results are consistent with an estrogen receptor alpha (ERalpha)/Sp1 complex interacting with an Sp1(N)(30) ERE half-site ((1/2)) motif in which both ERalpha and Sp1 bind promoter DNA. The ER/Sp1-DNA complex is formed using nuclear extracts from MCF-7 cells but not with recombinant human ERalpha or Sp1 proteins, suggesting that other nuclear factor(s) are required for complex stabilization. The E2-responsive Sp1(N)(x)ERE(1/2) motif identified in the TGFalpha gene promoter has also been characterized in the cathepsin D and heat shock protein 27 gene promoters; however, in the latter two promoters the numbers of intervening nucleotides are 23 and 10 respectively.

  11. Rethinking the economics of centralized spent fuel storage

    International Nuclear Information System (INIS)

    Wood, T.W.; Short, S.M.; Dippold, D.G.; Rod, S.R.; Williams, J.W.

    1991-01-01

    The technology for extended storage of spent nuclear fuel (SNF), either at-reactor or in a centralized facility such as a monitored retrievable storage (MRS) facility, is well-developed and proven from an engineering and safety perspective. The question of whether spent fuel should await its final geologic disposal while at a reactor site or in an MRS facility is essentially an economic one. While intuition and previous results suggest that centralized storage will be more economical than at-reactor storage beyond some break-even quantity of SNF, the incremental costs of pool storage at-reactor are close to zero as long as pool capacity is generally available. Thus, if economics is the prime motivator, the quantity of spent fuel required to warrant centralized storage could be quite large. The economics of centralizing the storage of spent fuel at a single site, as opposed to continued storage at over 100 reactor sites, has been the subject of several recent analyses. Most of these analyses involved calculating the benefits of an MRS facility (in terms of avoided utility costs) with a pre-defined MRS operating scenario (e.g., spent fuel acceptance schedule, storage capacity, and typical storage cycle). While these analyses provided some insight into the economic justification for an MRS facility, even the most favorable scenarios resulted in net costs of hundreds of millions of dollars when evaluated on a discounted cash flow basis

  12. Niagara Falls Storage Site environmental report for calendar year 1992, 1397 Pletcher Road, Lewiston, New York. Formerly Utilized Sites Remedial Action Program (FUSRAP)

    Energy Technology Data Exchange (ETDEWEB)

    1993-05-01

    This report describes the environmental surveillance program at the Niagara Falls Storage Site (NFSS) and provides the results for 1992. From 1944 to the present, the primary use of NFSS has been storage of radioactive residues produced as a by-product of uranium production. All onsite areas of residual radioactivity above guidelines have been remediated. Materials generated during remediation are stored onsite in the 4-ha (10-acre) waste containment structure (WCS). The WCS is a clay-lined, clay-capped, and grass-covered storage pile. The environmental surveillance program at NFSS includes sampling networks for radon concentrations in air; external gamma radiation exposure; and total uranium and radium-226 concentrations in surface water, sediments, and groundwater. Several chemical parameters, including seven metals, are also routinely measured in groundwater. This surveillance program assists in fulfilling the DOE policy of measuring and monitoring effluents from DOE activities and calculating hypothetical doses. Monitoring results are compared with applicable Environmental Protection Agency (EPA) and New York State Department of Environmental Conservation (NYSDEC) standards, DOE derived concentration guides (DCGs), dose limits, and other DOE requirements. Results of environmental monitoring during 1992 indicate that levels of the parameters measured were in compliance with all but one requirement: Concentrations of iron and manganese in groundwater were above NYSDEC groundwater quality standards. However, these elements occur naturally in the soils and groundwater associated with this region. In 1992 there were no environmental occurrences or reportable quantity releases.

  13. Sampling and analysis plan for Wayne Interim Storage Site (WISS), Wayne, New Jersey

    International Nuclear Information System (INIS)

    Brown, K.S.; Murray, M.E.; Rodriguez, R.E.

    1998-10-01

    This field sampling plan describes the methodology to perform an independent radiological verification survey and chemical characterization of a remediated area of the subpile at the Wayne Interim Storage Site, Wayne, New Jersey.Data obtained from collection and analysis of systematic and biased soil samples will be used to assess the status of remediation at the site and verify the final radiological status. The objective of this plan is to describe the methods for obtaining sufficient and valid measurements and analytical data to supplement and verify a radiological profile already established by the Project Remediation Management Contractor (PMC). The plan describes the procedure for obtaining sufficient and valid analytical data on soil samples following remediation of the first layer of the subpile. Samples will be taken from an area of the subpile measuring approximately 30 m by 80 m from which soil has been excavated to a depth of approximately 20 feet to confirm that the soil beneath the excavated area does not exceed radiological guidelines established for the site or chemical regulatory limits for inorganic metals. After the WISS has been fully remediated, the Department of Energy will release it for industrial/commercial land use in accordance with the Record of Decision. This plan provides supplemental instructions to guidelines and procedures established for sampling and analysis activities. Procedures will be referenced throughout this plan as applicable, and are available for review if necessary

  14. Biosorption of uranium by Azolla, SP, Brazil

    International Nuclear Information System (INIS)

    Vieira, Ludmila C.; Alves, Eliakim G.; Marumo, Julio T.; Ferreira, Rafael V. de P.; Canevesi, Rafael L.S.; Silva, Edson A.

    2015-01-01

    Radioactive liquid waste needs special attention and requires suitable treatment before deposition. Among the potential technologies under development for the treatment of liquid radioactive wastes the biosorption has been highlighted by being an efficient and low cost technique. Biosorption process involves the exchange of ions contained in the biomass matrix by others present in solution. There are many biomasses that could be applied in treatment of radioactive wastes, for example, agricultural residues and macrophyte. The aim of this study is evaluate the ability of the Azolla sp., a floating aquatic plant, to absorb uranium in solution. Azolla sp. is a macrophyte that has been used to treat effluents containing heavy metals. The biosorption capacity of uranium by Azolla sp. was experimentally determined and modeled by isotherms. Experiments were performed to determine metal uptake, and then the solutions were analyzed by inductively coupled plasma optical emission spectrometry (ICP-OES). The isotherms applied to model the data was Langmuir, Freundlich, Sips Toth, Redlich Peternson, Two-Site-Langmuir, Radke Prausnitz to develop a technique for the treatment of radioactive liquid waste generated at the Nuclear and Energy Research Institute (IPEN-CNEN/SP), Brazil. (author)

  15. Biosorption of uranium by Azolla, SP, Brazil

    Energy Technology Data Exchange (ETDEWEB)

    Vieira, Ludmila C.; Alves, Eliakim G.; Marumo, Julio T., E-mail: lcvieira@ipen.br [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil); Ferreira, Rafael V. de P., E-mail: rafael@itatijuca.com [Itatijuca Biotech, Sao Paulo, SP (Brazil); Canevesi, Rafael L.S.; Silva, Edson A., E-mail: edson.silva2@unioeste.br [Universidade Estadual do Oeste Parana (UNIOESTE), Toledo, PR (Brazil)

    2015-07-01

    Radioactive liquid waste needs special attention and requires suitable treatment before deposition. Among the potential technologies under development for the treatment of liquid radioactive wastes the biosorption has been highlighted by being an efficient and low cost technique. Biosorption process involves the exchange of ions contained in the biomass matrix by others present in solution. There are many biomasses that could be applied in treatment of radioactive wastes, for example, agricultural residues and macrophyte. The aim of this study is evaluate the ability of the Azolla sp., a floating aquatic plant, to absorb uranium in solution. Azolla sp. is a macrophyte that has been used to treat effluents containing heavy metals. The biosorption capacity of uranium by Azolla sp. was experimentally determined and modeled by isotherms. Experiments were performed to determine metal uptake, and then the solutions were analyzed by inductively coupled plasma optical emission spectrometry (ICP-OES). The isotherms applied to model the data was Langmuir, Freundlich, Sips Toth, Redlich Peternson, Two-Site-Langmuir, Radke Prausnitz to develop a technique for the treatment of radioactive liquid waste generated at the Nuclear and Energy Research Institute (IPEN-CNEN/SP), Brazil. (author)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2006-07-01

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

  17. Colonie Interim Storage Site environmental report for calendar year 1992, 1130 Central Avenue, Colonie, New York

    International Nuclear Information System (INIS)

    1993-05-01

    This report describes the environmental surveillance program at the Colonie Interim Storage Site (CISS) and provides the results for 1992. The site is located in eastern New York State, approximately 6.4 km (4.0 mi) northwest of downtown Albany. From 1958 to 1984, National Lead (NL) Industries used the facility to manufacture various components from depleted and enriched uranium natural thorium. Environmental monitoring of CISS began in 1984 when Congress added, the site to the US Department of Energy's (DOE) Formerly Utilized Sites Remedial Action Program (FUSRAP). FUSRAP is a program established to identify and decontaminate or otherwise control sites where residual radioactive materials remain from the early years of the nation's atomic energy program or from commercial operations causing conditions that Congress has authorized DOE to remedy. The environmental surveillance program at CISS includes sampling networks for external gamma radiation exposure and for thorium-232 and total uranium concentrations in surface water, sediment, and groundwater. Several chemical parameters are also measured in groundwater, including total metals, volatile organics, and water quality parameters. This surveillance program assists in fulfilling the DOE policy of measuring and monitoring effluents from DOE activities and calculating hypothetical doses. Results are compared with applicable Environmental Protection Agency (EPA) and New York State Department of Environmental Conservation (NYSDEC) standards, DOE derived concentration guides (DCGs), dose limits, and other DOE requirements

  18. Advanced and Integrated Petrophysical Characterization for CO2 Storage: Application to the Ketzin Site Caractérisation pétrophysique intégrée pour le stockage de CO2 : application au site de Ketzin

    Directory of Open Access Journals (Sweden)

    Fleury M.

    2013-06-01

    Full Text Available Advanced and Integrated Petrophysical Characterization for CO2 Storage: Application to the Ketzin Site — Reservoir simulations and monitoring of CO2 storage require specific petrophysical data. We show a workflow that can be applied to saline aquifers and caprocks in order to provide the minimum data set for realistic estimations of storage potential and perform pertinent simulations of CO2 injection. The presented series of experiments are fully integrated with quantitative log data analysis to estimate porosity, irreducible saturation, drainage capillary pressure and water relative permeability, residual gas saturation, resistivity-saturation relationships and caprock transport properties (permeability and diffusivity. The case considered is a saline aquifer of the Triassic Stuttgart formation studied in the framework of the CO2SINK onshore research storage, the first in situ testing site of CO2 injection in Germany located near the city of Ketzin. We used petrophysical methods that can provide the required data in a reasonable amount of time while still being representative of the in situ injection process. For two phase transport properties, we used the centrifuge technique. For resistivity measurements, we used the Fast Resistivity Index Measurement (FRIM method in drainage and imbibition, at ambient and storage conditions. For caprock characterization, we used a fast NMR (Nuclear Magnetic Resonance deuterium tracer technique to measure diffusivity and a modified steady state innovative technique to determine permeability. Entry pressure has also been evaluated using several methods. Resistivity and NMR logs were analyzed to provide a continuous estimation of irreducible saturation for the entire storage zone and to judge on the representativity of the samples analyzed in the laboratory. For the Ketzin site, the storage zone is a clayey sandstone of fluvial origin locally highly cemented, with porosity around 30% and permeability ranging

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

    Science.gov (United States)

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

    2008-12-01

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

  20. Effects of Purple-fleshed Sweet Potato (Ipomoera batatas Cultivar Ayamurasaki) Powder Addition on Color and Texture Properties and Sensory Characteristics of Cooked Pork Sausages during Storage

    Science.gov (United States)

    Jin, Sang-Keun; Kim, Yeong-Jung; Park, Jae Hong; Hur, In-Chul; Nam, Sang-Hae; Shin, Daekeun

    2012-01-01

    This study was conducted to evaluate the effects of adding purple-fleshed sweet potato (PFP) powder on the texture properties and sensory characteristics of cooked pork sausage. Sodium nitrite alone and sodium nitrite in combination with PFP were added to five different treatments sausages (CON (control) = 0.01% sodium nitrite, SP25 = 0.005% sodium nitrite and 0.25% purple-fleshed sweet potato powder combination, SP50 = 0.005% sodium nitrite and 0.5% purple-fleshed sweet potato powder combination, PP25 = 0.25% purple-fleshed sweet potato powder, PP50 = 0.5% purple-fleshed sweet potato powder). The sausages were cooked to 74°C, stored at 4°C for 6 wks, and used for chemical analysis, textural properties, and a sensory evaluation on 0, 2, 4 and 6 wks of storage, respectively. Similar CIE a* and b* values were determined in sausages from CON, SP25 and SP50 at the end of storage, and they were higher in CIE a* but lower in CIE b* than that of the PP25 and PP50 sausages. Significant differences were observed for brittleness and hardness when PFP was added to the sausages but were not confirmed after 4 wks of storage. The objective color score was influenced by adding PFP; however, the effect was not dose dependent. In overall acceptability, panelists favored the CON, SP25, SP50, and PP50 sausages but did not prefer PP25 sausages at the end of storage. Therefore, adding PFP to cooked pork sausages improved color and texture properties and sensory characteristics, but further study is needed to determine the proper ratio of sodium nitrite and PFP. PMID:25049698

  1. Feasibility of a subsurface storage

    International Nuclear Information System (INIS)

    1998-11-01

    This report analyses the notion of subsurface storage under the scientifical, technical and legal aspects. This reflection belongs to the studies about long duration storage carried out in the framework of the axis 3 of the December 30, 1991 law. The report comprises 3 parts. The first part is a synthesis of the complete subsurface storage study: definitions, aim of the report, very long duration storage paradigm, description files of concepts, thematic synthesis (legal aspects, safety, monitoring, sites, seismicity, heat transfers, corrosion, concretes, R and works, handling, tailings and dismantlement, economy..), multi-criteria/multi-concept cross-analysis. The second part deals with the technical aspects of the subsurface storage: safety approach (long duration impact, radiation protection, mastery of effluents), monitoring strategy, macroscopic inventory of B-type waste packages, inventory of spent fuels, glasses, hulls and nozzles, geological contexts in the French territory (sites selection and characterization), on-site activities, hydrogeological and geochemical aspects, geo-technical works and infrastructures organization, subsurface seismic effects, cooling modes (ventilation, heat transfer with the geologic environment), heat transfer research programs (convection, poly-phase cooling in porous media), handling constraints, concretes (use, behaviour, durability), corrosion of metallic materials, technical-economical analysis, international context (experience feedback from Sweden (CLAB) and the USA (Yucca Mountain), other European and French facilities). The last part of the report is a graphical appendix with 3-D views and schemes of the different concepts. (J.S.)

  2. Results of the radiological survey at the former ore storage site, Palmerton, Pennsylvania (PP001)

    International Nuclear Information System (INIS)

    Cottrell, W.D.; Quillen, J.L.; Crutcher, J.W.

    1990-12-01

    As part of the Formerly Utilized Sites Remedial Action Program (FUSRAP), the US Department of Energy (DOE) is implementing a radiological survey program to determine the radiological conditions at sites that were used by the department's predecessor agencies. The radiological survey discussed in this report for the former ore storage site in Palmerton, Pennsylvania, is part of the FUSRAP effort and was conducted at the request of DOE by members of the Measurement Applications and Development group of Oak Ridge National Laboratory (ORNL) in 1988. In 1953 and 1954 the Atomic Energy Commission (AEC) established an ore stockpile on the property of the New Jersey Zinc Corporation in Palmerton, Pennsylvania. Approximately 57 truckloads of ore (about 360 tons) were stored at this site and remained there until 1973, when the AEC initiated a clean-up program. The 1988 ORNL radiological survey included a gamma scan at the ground surface, gamma measurements at discrete locations at the surface and at 1 m above the surface, gamma logging of 80 auger holes, and collection of 161 surface and subsurface soil samples. Of these 161 soil samples, 98% were below DOE guidelines for 226 Ra concentration in soil. Interpretation of the data suggests small, isolated spots of residual ore. The data indicate that it is highly unlikely that an individual living or working on this site could receive a radiation dose approaching the 100 mrem annual limit. However, it is suggested that DOE evaluate potential exposures at this site to ensure compliance with their policy that all exposures to radiation are reduced to levels that are as low as reasonably achievable. 4 refs., 88 figs., 4 tabs

  3. Transfer of Plutonium-Uranium Extraction Plant and N Reactor irradiated fuel for storage at the 105-KE and 105-KW fuel storage basins, Hanford Site, Richland Washington

    International Nuclear Information System (INIS)

    1995-07-01

    The U.S. Department of Energy (DOE) needs to remove irradiated fuel from the Plutonium-Uranium Extraction (PUREX) Plant and N Reactor at the Hanford Site, Richland, Washington, to stabilize the facilities in preparation for decontamination and decommissioning (D ampersand D) and to reduce the cost of maintaining the facilities prior to D ampersand D. DOE is proposing to transfer approximately 3.9 metric tons (4.3 short tons) of unprocessed irradiated fuel, by rail, from the PUREX Plant in the 200 East Area and the 105 N Reactor (N Reactor) fuel storage basin in the 100 N Area, to the 105-KE and 105-KW fuel storage basins (K Basins) in the 100 K Area. The fuel would be placed in storage at the K Basins, along with fuel presently stored, and would be dispositioned in the same manner as the other existing irradiated fuel inventory stored in the K Basins. The fuel transfer to the K Basins would consolidate storage of fuels irradiated at N Reactor and the Single Pass Reactors. Approximately 2.9 metric tons (3.2 short tons) of single-pass production reactor, aluminum clad (AC) irradiated fuel in four fuel baskets have been placed into four overpack buckets and stored in the PUREX Plant canyon storage basin to await shipment. In addition, about 0.5 metric tons (0.6 short tons) of zircaloy clad (ZC) and a few AC irradiated fuel elements have been recovered from the PUREX dissolver cell floors, placed in wet fuel canisters, and stored on the canyon deck. A small quantity of ZC fuel, in the form of fuel fragments and chips, is suspected to be in the sludge at the bottom of N Reactor's fuel storage basin. As part of the required stabilization activities at N Reactor, this sludge would be removed from the basin and any identifiable pieces of fuel elements would be recovered, placed in open canisters, and stored in lead lined casks in the storage basin to await shipment. A maximum of 0.5 metric tons (0.6 short tons) of fuel pieces is expected to be recovered

  4. Closure Report for Corrective Action Unit 481: Area 12 T-Tunnel Conditional Release Storage Yard, Nevada Test Site, Nevada

    International Nuclear Information System (INIS)

    2008-01-01

    Corrective Action Unit (CAU) 481 is identified in the Federal Facility Agreement and Consent Order (FFACO) as Area 12 T-Tunnel Conditional Release Storage Yard. CAU 481 is located in Area 12 of the Nevada Test Site, which is approximately 65 miles northwest of Las Vegas, Nevada. This CAU consists of one Corrective Action Site (CAS), CAS 12-42-05, Housekeeping Waste. CAU 481 closure activities were conducted by the Defense Threat Reduction Agency from August 2007 through July 2008 according to the FFACO and Revision 3 of the Sectored Clean-up Work Plan for Housekeeping Category Waste Sites. Closure activities included removal and disposal of construction debris and low-level waste. Drained fluids, steel, and lead was recycled as appropriate. Waste generated during closure activities was appropriately managed and disposed.

  5. An Extended VIKOR-Based Approach for Pumped Hydro Energy Storage Plant Site Selection with Heterogeneous Information

    Directory of Open Access Journals (Sweden)

    Yunna Wu

    2017-08-01

    Full Text Available The selection of a desirable site for constructing a pumped hydro energy storage plant (PHESP plays a vital important role in the whole life cycle. However, little research has been done on the site selection of PHESP, which affects the rapid development of PHESP. Therefore, this paper aims to select the most ideal PHESP site from numerous candidate alternatives using the multi-criteria decision-making (MCDM technique. Firstly, a comprehensive evaluation criteria system is established for the first time. Then, considering quantitative and qualitative criteria coexist in this system, multiple types of representations, including crisp numerical values (CNVs, triangular intuitionistic fuzzy numbers (TIFNs, and 2-dimension uncertain linguistic variables (2DULVs, are employed to deal with heterogeneous criteria information. To determine the weight of criteria and fully take the preference of the decision makers (DMs into account, the analytic hierarchy process (AHP method is applied for criteria weighting. After that, an extended Vlsekriterijumska Optimizacija I Kompromisno Resenje (VIKOR method is utilized to provide compromise solutions for the PHESP site considering such heterogeneous information. At last, the proposed model is then applied in a case study of Zhejiang province, China to illustrate its practicality and efficiency. The result shows the Changlongshan should be selected as the optimal PHESP.

  6. Modular vault dry storage system for interim storage of irradiated fuel

    International Nuclear Information System (INIS)

    Cundill, B.R.; Ealing, C.J.; Agarwal, B.K.

    1988-01-01

    The Foster Wheeler Energy Application (FWEA) Modular Vault Dry Store (MVDS) is a dry storage concept for the storage of all types of irradiated reactor fuel. For applications in the US, FWEA submitted an MVDS Topical Report to the US NRC during 1986. Following NRC approval of the MVDS Topical Report concept for unconsolidated LWR fuel, US utilities have available a new, compact, economic and flexible system for the storage of irradiated fuel at the reactor site for time periods of at least 20 years (the period of the first license). The MVDS concept jointly developed by FWEA and GEC in the U.K., has other applications for large central away from reactor storage facilities such as a Monitorable Retrievable Storage (MRS) installation. This paper describes the licensed MVDS design, aspects of performance are discussed and capital costs compared with alternative concepts. Alternative configurations of MVDS are outlined

  7. Environmental assessment: Solid waste retrieval complex, enhanced radioactive and mixed waste storage facility, infrastructure upgrades, and central waste support complex, Hanford Site, Richland, Washington

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-09-01

    The U.S. Department of Energy (DOE) needs to take action to: retrieve transuranic (TRU) waste because interim storage waste containers have exceeded their 20-year design life and could fail causing a radioactive release to the environment provide storage capacity for retrieved and newly generated TRU, Greater-than-Category 3 (GTC3), and mixed waste before treatment and/or shipment to the Waste Isolation Pilot Project (WIPP); and upgrade the infrastructure network in the 200 West Area to enhance operational efficiencies and reduce the cost of operating the Solid Waste Operations Complex. This proposed action would initiate the retrieval activities (Retrieval) from Trench 4C-T04 in the 200 West Area including the construction of support facilities necessary to carry out the retrieval operations. In addition, the proposed action includes the construction and operation of a facility (Enhanced Radioactive Mixed Waste Storage Facility) in the 200 West Area to store newly generated and the retrieved waste while it awaits shipment to a final disposal site. Also, Infrastructure Upgrades and a Central Waste Support Complex are necessary to support the Hanford Site`s centralized waste management area in the 200 West Area. The proposed action also includes mitigation for the loss of priority shrub-steppe habitat resulting from construction. The estimated total cost of the proposed action is $66 million.

  8. Hanford Site solid waste acceptance criteria

    International Nuclear Information System (INIS)

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

    1991-09-01

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

  9. SiteChar. Characterisation of European CO2 storage. Deliverable D8.2. Trust building and raising public awareness

    Energy Technology Data Exchange (ETDEWEB)

    Brunsting, S.; Pol, M.; Mastop, E.A. [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.; Howell, R. [Scottish Carbon Capture and Storage SCCS, Edinburg, Scotland (United Kingdom)

    2012-08-15

    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 and community engagement process does increase the likelihood thereof. This deliverable is a follow-up to deliverable D8.1 'Social site characterisation'. Social site characterisation can be used as an instrument to explore, plan and evaluate a process of active and constructive local stakeholder and citizen engagement in a prospective CCS project as a parallel activity to technical site characterisation. It serves as an analytical tool to describe the local social circumstances in the area and to design and evaluate stakeholder and community engagement efforts with the aims of building trust and raising public awareness. Using results from the social site characterisation of the area, the present deliverable focuses on the second purpose. It presents results from public engagement activities designed to raise public awareness and inform public opinion of a prospective CCS site in Poland (onshore) and the UK (offshore): focus conferences. Furthermore, by initiating an enhanced cooperation in planning of new storage sites between project developers, authorities and the local public, focus conferences aim to serve as a 'hinge' between social site characterisation as a research effort and application to real-life project settings. The focus conferences are part of a range of public engagement activities including the setup of public information websites on generic and site-specific CCS, information meetings. A second survey eventually shall evaluate the results of the public engagement activities. The aim of the focus conferences was to raise public awareness and assist public opinion forming processes of a prospective CCS site in Poland (onshore) and the UK (offshore). At the same time, it aimed to present and test a

  10. Study of mined storage caverns

    International Nuclear Information System (INIS)

    1975-06-01

    All available information concerning 75 mined storage caverns as well as the investigative techniques utilized to determine the feasibility of a cavern site is presented. Potential new storage caverns may be for products such as high or low vapor pressure petroleum products, other chemical products, aid industrial or nuclear waste

  11. Formerly utilized MED/AEC sites Remedial Action Program. Radiological survey of the St. Louis Airport Storage Site, St. Louis, Missouri. Final report. [U, Ra-bearing wastes stored in 1940-60's

    Energy Technology Data Exchange (ETDEWEB)

    None

    1979-09-01

    Results of two radiological surveys of the St. Louis-Lambert Airport property, formerly known as the Airport Storage Site, St. Louis, Missouri, are presented. Uranium- and radium-bearing waste materials were stored from the 1940's to the late 1960's in this area. The surveys included direct measurements of beta-gamma radiation; determination of uranium, actinium, and radium concentrations in soil samples and from bore holes; determination of radionuclide concentrations in groundwater and surface water; measurement of radon flux from the ground surface; and measurements of /sup 222/Rn in air near the site. Results indicate that some offsite drainage pathways are becoming contaminated, probably by runoff from the site; no migration of /sup 222/Rn from the site was observed.

  12. A null-parameter formula for storage-evapotranspiration relationship based on generalized proportionality hypothesis and its applications

    Science.gov (United States)

    Han, P. F.; Wang, X. S.; Istanbulluoglu, E.

    2017-12-01

    Different formulas have been developed to estimate the mean annual evapotranspiration ratio (E/P) at catchment scale from the mean annual aridity index (Ep/P) based on the Budyko framework. A major challenge in using the Budyko framework for the inter-annual behaviors of a catchment is the missed storage in these formulas. Efforts have been contributed to modify the formulas for estimating the annual E/P from both of the annual Ep/P and the change in storage, leading to a significant increase in the number of empirical parameters. In this paper we develop a null-parameter formula of the storage-evapotranspiration relationship based on a new interpretation of the proportionality hypothesis, which takes the storage in the soil-plant-atmosphere continuum (SPAC) as the accessible water for the evapotranspiration processes. According to the formula, the annual E/P depends on the annual Ep/P and S/P values where S is the initial SPAC storage in a year. The difference between the S values of two years represents the inter-annual change in storage in the SPAC system. An annual water balance model including groundwater storage for a basin is required to estimate the annual runoff and S/P from year to year. We develop a tri-parameters model using this null-parameter formula to minimize the number of parameters and successfully applied to investigate the NLRB basin in Nebraska, USA. For mean annual water balance, the tri-parameters model results in one-parameter formulas to estimate both of the mean annual E/P and S/P so that the status of storage can be included in the Budyko framework. The tri-parameters model is further extended to a twin-zones model for the effect of irrigation in croplands and applied to reconstruct the hydrological behaviors in the natural state for 12 catchments in Illinois, USA, with different cropland areas. It is found in the Illinois examples (where Ep/P is less than 2) that the annual E/P increases with the increasing Ep/P almost in a linear

  13. Maywood Interim Storage Site environmental report for calendar year 1992, 100 West Hunter Avenue, Maywood, New Jersey. Formerly Utilized Sites Remedial Action Program (FUSRAP)

    Energy Technology Data Exchange (ETDEWEB)

    1993-05-01

    This report describes the environmental surveillance program at the Maywood Interim Storage Site (MISS) and provides the results for 1992. Environmental monitoring of MISS began in 1984, when the site was assigned to DOE by Congress through the Energy and Water Development Appropriations Act and was placed under DOE`s Formerly Utilized Sites Remedial Action Program (FUSRAP). FUSRAP was established to identify and decontaminate or otherwise control sites where residual radioactive materials remain from the early years of the nation`s atomic energy program or from commercial operations causing conditions that Congress has authorized DOE to remedy. MISS is part of a National Priorities List (NPL) site. The environmental surveillance program at MISS includes sampling networks for radon and thoron in air; external gamma radiation exposure; and radium-226, radium-228, thorium-232, and total uranium in surface water, sediment, and groundwater. Additionally, chemical analysis includes metals and organic compounds in surface water and groundwater and metals in sediments. This program assists in fulfilling the DOE objective of measuring and monitoring effluents from DOE activities and calculating hypothetical doses to members of the general public. Monitoring results are compared with applicable Environmental Protection Agency (EPA) and state standards, DOE derived concentration guides (DCGs), dose limits, and other DOE requirements. Environmental standards are established to protect public health and the environment. The radiological data for all media sampled support the conclusion that doses to the public are not distinguishable from natural background radiation.

  14. Down-regulation of human topoisomerase IIα expression correlates with relative amounts of specificity factors Sp1 and Sp3 bound at proximal and distal promoter regions

    Directory of Open Access Journals (Sweden)

    Isaacs Richard J

    2007-05-01

    Full Text Available Abstract Background Topoisomerase IIα has been shown to be down-regulated in doxorubicin-resistant cell lines. The specificity proteins Sp1 and Sp3 have been implicated in regulation of topoisomerase IIα transcription, although the mechanism by which they regulate expression is not fully understood. Sp1 has been shown to bind specifically to both proximal and distal GC elements of the human topoisomerase IIα promoter in vitro, while Sp3 binds only to the distal GC element unless additional flanking sequences are included. While Sp1 is thought to be an activator of human topoisomerase IIα, the functional significance of Sp3 binding is not known. Therefore, we sought to determine the functional relationship between Sp1 and Sp3 binding to the topoisomerase IIα promoter in vivo. We investigated endogenous levels of Sp1, Sp3 and topoisomerase IIα as well as binding of both Sp1 and Sp3 to the GC boxes of the topoisomerase IIα promoter in breast cancer cell lines in vivo after short term doxorubicin exposure. Results Functional effects of Sp1 and Sp3 were studied using transient cotransfection assays using a topoisomerase IIα promoter reporter construct. The in vivo interactions of Sp1 and Sp3 with the GC elements of the topoisomerase IIα promoter were studied in doxorubicin-treated breast cancer cell lines using chromatin immunoprecipitation assays. Relative amounts of endogenous proteins were measured using immunoblotting. In vivo DNA looping mediated by proteins bound at the GC1 and GC2 elements was studied using the chromatin conformation capture assay. Both Sp1 and Sp3 bound to the GC1 and GC2 regions. Sp1 and Sp3 were transcriptional activators and repressors respectively, with Sp3 repression being dominant over Sp1-mediated activation. The GC1 and GC2 elements are linked in vivo to form a loop, thus bringing distal regulatory elements and their cognate transcription factors into close proximity with the transcription start site

  15. Optimization of time and location dependent spent nuclear fuel storage capacity

    International Nuclear Information System (INIS)

    Macek, V.

    1977-01-01

    A linear spent fuel storage model is developed to identify cost-effective spent nuclear fuel storage strategies. The purpose of this model is to provide guidelines for the implementation of the optimal time-dependent spent fuel storage capacity expansion in view of the current economic and regulatory environment which has resulted in phase-out of the closed nuclear fuel cycle. Management alternatives of the spent fuel storage backlog, which is created by mismatch between spent fuel generation rate and spent fuel disposition capability, are represented by aggregate decision variables which describe the time dependent on-reactor-site and off-site spent fuel storage capacity additions, and the amount of spent fuel transferred to off-site storage facilities. Principal constraints of the model assure determination of cost optimal spent fuel storage expansion strategies, while spent fuel storage requirements are met at all times. A detailed physical and economic analysis of the essential components of the spent fuel storage problem, which precedes the model development, assures its realism. The effects of technological limitations on the on-site spent fuel storage expansion and timing of reinitiation of the spent fuel reprocessing on optimal spent fuel storage capacity expansion are investigated. The principal results of the study indicate that (a) expansion of storage capacity beyond that of currently planned facilities is necessary, and (b) economics of the post-reactor fuel cycle is extremely sensitive to the timing of reinitiation of spent fuel reprocessing. Postponement of reprocessing beyond mid-1982 may result in net negative economic liability of the back end of the nuclear fuel cycle

  16. Assessing storage adequacy

    International Nuclear Information System (INIS)

    Amirault, P.

    2004-01-01

    Government policy encourages the use of natural gas. It is expected that liquefied natural gas (LNG) and Arctic gas will make up 20 to 25 per cent of supply. This presentation provided an outlook of storage value based on a technical analysis by the National Petroleum Counsel (NPC) report. A moderately robust growth is expected in the residential and commercial load which may be partially offset by robust growth in electricity. The net result is an increase in storage requirements. It was concluded that there is a strong case for growth in storage demand but a lack of good sites for additional capacity. This will lead to higher storage values. The NPC sees the need for 1 Tcf more storage use by 2025, of which 700 Bcf will need to come from new storage. In particular, current storage levels may not be sufficient to meet a colder than normal winter, and deliverability is affected by field inventory. Most storage capacity was built before 1985, mostly by regulated entities. It is expected that only 250 to 400 Bcf will be added over the next 25 years in North America. If storage becomes scarce, prices will move to the marginal cost of new additions, and the upper limit on price will be determined by salt cavern storage. An increase of $1.00 in the price of leasing storage would add about $0.11 to the average price of consumed gas. tabs., figs

  17. Remedial action work plan for the Colonie site. Revision 1

    International Nuclear Information System (INIS)

    1985-08-01

    The Colonie site is a DOE Formerly Utilized Sites Remedial Action Program (FUSRAP) site located in the Town of Colonie, New York, and consisting of an interim storage site and several vicinity properties. The Colonie Interim Storage Site (CISS) is the former National Lead (NL) Industries plant located at 1130 Central Avenue. There are 11 vicinity properties that received remedial action in 1984: 7 located south of the site on Yardboro and Palmer Avenues just across the Colonie-Albany town limits in Albany, and 4 located northwest of the site along Central Avenue in Colonie. Of these properties, nine are residences and two are commercial properties. This document describes the engineering design, construction, and associated plans for remedial action on the vicinity properties and the interim storage site. These plans include both radiological and chemical work. Radiological work includes: excavating the above-guideline radioactive wastes on the vicinity properties; designing required facilities for the interim storage site; preparing the interim storage site to receive these contaminated materials; transporting the contaminated materials to the interim waste storage stockpile; and preparing necessary schedules for accomplishing the remedial actions. Chemical work involves: developing the Resource Conservation and Recovery Act (RCRA) closure plans; neutralizing chemical hazards associated with plating solutions; inventorying on-site chemicals; and disposal of chemicals and/or residues. 17 refs., 5 figs., 1 tab

  18. Growth and Cultivation of the Unusual Generalized Transducing Bacillus Bacteriophage SP-15

    Science.gov (United States)

    Taylor, Martha J.; Goldberg, Ivan D.

    1971-01-01

    Additional properties of SP-15, a generalized transducing bacteriophage notable for the ability to transfer an unusually large fragment of deoxyribonucleic acid (DNA) to Bacillus subtilis and B. licheniformis, are presented together with improved methods that enhance its utility. Simple means have been found to provide the rigid control over moisture that is necessary for the assay of plaque-forming units (PFU). Reproducible procedures for propagating transducing phage, which depend upon an appropriate mixing of PFU with uninfected bacteria, have replaced less reliable methods that utilized infected spores. Transduction of B. subtilis W-23 increased linearly when MgSO4 in recipient cell-SP-15 mixtures was increased from 0.005 to 0.03 m. Methods have been developed that protect SP-15 from the damaging effects of CsCl and of osmotic shock subsequent to dilution. Evidence that the PFU and transducing particles of lysates decay at the same slow rate during extended storage suggests that the decay is a result of damage to protein rather than to DNA. One-step growth experiments, in which SP-15 was propagated on B. subtilis W-23-Sr/1 mg, indicated a latent period of 100 min, a rise period of 60 min, and a burst size of 25 to 34 PFU per infected cell. These findings suggest explanations for some of the technical difficulties SP-15 has presented. PMID:4999971

  19. Optical storage networking

    Science.gov (United States)

    Mohr, Ulrich

    2001-11-01

    For efficient business continuance and backup of mission- critical data an inter-site storage network is required. Where traditional telecommunications costs are prohibitive for all but the largest organizations, there is an opportunity for regional carries to deliver an innovative storage service. This session reveals how a combination of optical networking and protocol-aware SAN gateways can provide an extended storage networking platform with the lowest cost of ownership and the highest possible degree of reliability, security and availability. Companies of every size, with mainframe and open-systems environments, can afford to use this integrated service. Three mayor applications are explained; channel extension, Network Attached Storage (NAS), Storage Area Networks (SAN) and how optical networks address the specific requirements. One advantage of DWDM is the ability for protocols such as ESCON, Fibre Channel, ATM and Gigabit Ethernet, to be transported natively and simultaneously across a single fiber pair, and the ability to multiplex many individual fiber pairs over a single pair, thereby reducing fiber cost and recovering fiber pairs already in use. An optical storage network enables a new class of service providers, Storage Service Providers (SSP) aiming to deliver value to the enterprise by managing storage, backup, replication and restoration as an outsourced service.

  20. Radioactive waste storage issues

    International Nuclear Information System (INIS)

    Kunz, D.E.

    1994-01-01

    In the United States we generate greater than 500 million tons of toxic waste per year which pose a threat to human health and the environment. Some of the most toxic of these wastes are those that are radioactively contaminated. This thesis explores the need for permanent disposal facilities to isolate radioactive waste materials that are being stored temporarily, and therefore potentially unsafely, at generating facilities. Because of current controversies involving the interstate transfer of toxic waste, more states are restricting the flow of wastes into - their borders with the resultant outcome of requiring the management (storage and disposal) of wastes generated solely within a state's boundary to remain there. The purpose of this project is to study nuclear waste storage issues and public perceptions of this important matter. Temporary storage at generating facilities is a cause for safety concerns and underscores, the need for the opening of permanent disposal sites. Political controversies and public concern are forcing states to look within their own borders to find solutions to this difficult problem. Permanent disposal or retrievable storage for radioactive waste may become a necessity in the near future in Colorado. Suitable areas that could support - a nuclear storage/disposal site need to be explored to make certain the health, safety and environment of our citizens now, and that of future generations, will be protected

  1. Modular dry storage of spent fuel

    International Nuclear Information System (INIS)

    Baxter, J.W.

    1982-01-01

    Long term uncertainties in US spent fuel reprocessing and storage policies and programs are forcing the electric utilities to consider means of storing spent fuel at the reactor site in increasing quantitities and for protracted periods. Utilities have taken initial steps in increasing storage capacity. Existing wet storage pools have in many cases been reracked to optimize their capacity for storing spent fuel assemblies

  2. Mulberry (Morus sp. leaf moisture in storage enviroments

    Directory of Open Access Journals (Sweden)

    Antonio José Porto

    2010-02-01

    Full Text Available Mulberry leaves (IZ 56/4 cultivar in the pos-harvest, had been taken to the laboratory and submitted to six storage environments (8 hours in open ambient-O, 8 hours in cover ambient- C, 1hO/7hC, 2hO/6hC, 3hO/5hC and 4hO/4hC, aiming to evaluate moisture exchange capacity . It was utilized the experimental design split plot with five replications (blocks, six principal treatments (parcels and nine secondary treatments (sub parcels, weighing of hour in hour, of 08h00min. until 16h00min.. In the period of eight hours of experimentation mulberry leaves moisturedevreased in all the ambients evaluated. However, for cover leaves with wet cloth, for all periods, the water purport (74,63% was maintained close to the original value (08h00min.- 76,07%, demonstrating the efficiency technique in the conservation of the humidity of leaves for feeding silkworm.

  3. Silencing the SpMPK1, SpMPK2, and SpMPK3 Genes in Tomato Reduces Abscisic Acid—Mediated Drought Tolerance

    Directory of Open Access Journals (Sweden)

    Yan Liang

    2013-11-01

    Full Text Available Drought is a major threat to agriculture production worldwide. Mitogen-activated protein kinases (MAPKs play a pivotal role in sensing and converting stress signals into appropriate responses so that plants can adapt and survive. To examine the function of MAPKs in the drought tolerance of tomato plants, we silenced the SpMPK1, SpMPK2, and SpMPK3 genes in wild-type plants using the virus-induced gene silencing (VIGS method. The results indicate that silencing the individual genes or co-silencing SpMPK1, SpMPK2, and SpMPK3 reduced the drought tolerance of tomato plants by varying degrees. Co-silencing SpMPK1 and SpMPK2 impaired abscisic acid (ABA-induced and hydrogen peroxide (H2O2-induced stomatal closure and enhanced ABA-induced H2O2 production. Similar results were observed when silencing SpMPK3 alone, but not when SpMPK1 and SpMPK2 were individually silenced. These data suggest that the functions of SpMPK1 and SpMPK2 are redundant, and they overlap with that of SpMPK3 in drought stress signaling pathways. In addition, we found that SpMPK3 may regulate H2O2 levels by mediating the expression of CAT1. Hence, SpMPK1, SpMPK2, and SpMPK3 may play crucial roles in enhancing tomato plants’ drought tolerance by influencing stomatal activity and H2O2 production via the ABA-H2O2 pathway.

  4. Wayne Interim Storage Site environmental report for calendar year 1992, 868 Black Oak Ridge Road, Wayne, New Jersey. Formerly Utilized Sites Remedial Action Program (FUSRAP)

    Energy Technology Data Exchange (ETDEWEB)

    1993-05-01

    This report describes the environmental surveillance program at the Wayne Interim Storage Site (WISS) and provides the results for 1992. The fenced, site, 32 km (20 mi) northwest of Newark, New Jersey, was used between 1948 and 1971 for commercial processing of monazite sand to separate natural radioisotopes - predominantly thorium. Environmental surveillance of WISS began in 1984 in accordance with Department of Energy (DOE) Order 5400.1 when Congress added the site to DOE`s Formerly Utilized Sites Remedial Action Program (FUSRAP). The environmental surveillance program at WISS includes sampling networks for radon and thoron in air; external gamma radiation exposure; radium-226, radium-228, thorium-230, thorium-232, total uranium, and several chemicals in surface water and sediment; and total uranium, radium-226, radium-228, thorium-230, thorium-232, and organic and inorganic chemicals in groundwater. Monitoring results are compared with applicable Environmental Protection Agency (EPA) and state standards, DOE derived concentration guides (DCGs), dose limits, and other DOE requirements. This monitoring program assists in fulfilling the DOE policy of measuring and monitoring effluents from DOE activities and calculating hypothetical doses. Results for environmental surveillance in 1992 show that the concentrations of all radioactive and most chemical contaminants were below applicable standards.

  5. Niagara Falls Storage Site environmental report for calendar year 1992, 1397 Pletcher Road, Lewiston, New York

    International Nuclear Information System (INIS)

    1993-05-01

    This report describes the environmental surveillance program at the Niagara Falls Storage Site (NFSS) and provides the results for 1992. From 1944 to the present, the primary use of NFSS has been storage of radioactive residues produced as a by-product of uranium production. All onsite areas of residual radioactivity above guidelines have been remediated. Materials generated during remediation are stored onsite in the 4-ha (10-acre) waste containment structure (WCS). The WCS is a clay-lined, clay-capped, and grass-covered storage pile. The environmental surveillance program at NFSS includes sampling networks for radon concentrations in air; external gamma radiation exposure; and total uranium and radium-226 concentrations in surface water, sediments, and groundwater. Several chemical parameters, including seven metals, are also routinely measured in groundwater. This surveillance program assists in fulfilling the DOE policy of measuring and monitoring effluents from DOE activities and calculating hypothetical doses. Monitoring results are compared with applicable Environmental Protection Agency (EPA) and New York State Department of Environmental Conservation (NYSDEC) standards, DOE derived concentration guides (DCGs), dose limits, and other DOE requirements. Results of environmental monitoring during 1992 indicate that levels of the parameters measured were in compliance with all but one requirement: Concentrations of iron and manganese in groundwater were above NYSDEC groundwater quality standards. However, these elements occur naturally in the soils and groundwater associated with this region. In 1992 there were no environmental occurrences or reportable quantity releases

  6. Corrective Action Decision Document for Corrective Action Unit 204: Storage Bunkers, Nevada Test Site, Nevada, Revision 0 with ROTC 1, 2, and Errata

    Energy Technology Data Exchange (ETDEWEB)

    Wickline, Alfred

    2004-04-01

    This Corrective Action Decision Document (CADD) has been prepared for Corrective Action Unit (CAU) 204 Storage Bunkers, Nevada Test Site (NTS), Nevada, in accordance with the ''Federal Facility Agreement and Consent Order'' (FFACO) that was agreed to by the State of Nevada; U.S. Department of Energy (DOE); and the U.S. Department of Defense (FFACO, 1996). The NTS is approximately 65 miles (mi) north of Las Vegas, Nevada (Figure 1-1). The Corrective Action Sites (CASs) within CAU 204 are located in Areas 1, 2, 3, and 5 of the NTS, in Nye County, Nevada (Figure 1-2). Corrective Action Unit 204 is comprised of the six CASs identified in Table 1-1. As shown in Table 1-1, the FFACO describes four of these CASs as bunkers one as chemical exchange storage and one as a blockhouse. Subsequent investigations have identified four of these structures as instrumentation bunkers (CASs 01-34-01, 02-34-01, 03-34-01, 05-33-01), one as an explosives storage bunker (CAS 05-99-02), and one as both (CAS 05-18-02). The six bunkers included in CAU 204 were primarily used to monitor atmospheric testing or store munitions. The ''Corrective Action Investigation Plan (CAIP) for Corrective Action Unit 204: Storage Bunkers, Nevada Test Site, Nevada'' (NNSA/NV, 2002a) provides information relating to the history, planning, and scope of the investigation; therefore, it will not be repeated in this CADD. This CADD identifies potential corrective action alternatives and provides a rationale for the selection of a recommended corrective action alternative for each CAS within CAU 204. The evaluation of corrective action alternatives is based on process knowledge and the results of investigative activities conducted in accordance with the CAIP (NNSA/NV, 2002a) that was approved prior to the start of the Corrective Action Investigation (CAI). Record of Technical Change (ROTC) No. 1 to the CAIP (approval pending) documents changes to the preliminary action levels

  7. Ovos de Toxocara sp. e larvas de Ancylostoma sp. em praça pública de Lavras, MG Toxocara sp. eggs and Ancylostoma sp. larva in public parks, Brazil

    Directory of Open Access Journals (Sweden)

    Antônio Marcos Guimarães

    2005-04-01

    Full Text Available Larva migrans visceral e cutânea são zoonoses parasitárias causadas pela infecção da larva de Toxocara sp. e Ancylostoma sp., respectivamente. O objetivo do estudo foi verificar a contaminação por ovos de Toxocara sp. e ovos e larvas de Ancylostoma sp. em amostras de solos coletadas de praças públicas e de áreas de recreação infantil de Lavras, Estado de Minas Gerais, por meio da técnica de centrífugo-flutuação e do método de Baermann. A ocorrência de ovos de Toxocara sp. e, ovos e larvas de Ancylostoma sp. foi observada em 69,6% (16/23 das amostras de solo coletadas de praças públicas. A contaminação somente por ovos de Ancylostoma sp. em amostras de solo coletadas em escolas/creches foi de 22,2% (4/18. A percentagem de amostras de areia coletadas de escolas/creches contaminadas somente com larvas de Ancylostoma sp. foi de 11,1% (2/18. Praças públicas são as áreas com maior risco potencial de infecção por Toxocara sp. e Ancylostoma sp. Exame coproparasitológico realizado em 174 amostras de fezes de cães observou 58% e 23%, respectivamente, com ovos de Ancylostoma sp. e Toxocara sp.Visceral and cutaneous larva migrans are parasitic zoonoses caused by the infection of larval nematodes Toxocara sp. and Ancylostoma sp. respectively. The objective of this study was to investigate the contamination by Toxocara sp. eggs and Ancylostoma sp. eggs and larva of soil samples collected from public parks and children's playground areas in state of Minas Gerais, Brazil, using both Baermann's method and centrifugal flotation technique. Toxocara sp. and Ancylostoma sp. eggs were observed in soil samples collected from public squares in 17.4% (4/23 and 69.6 (16/23 respectively. In schools and child day care settings the contamination by Ancylostoma sp. larva in sand samples was 11.1% (2/18. Public parks are settings of more potential risk of Toxocara sp. eggs and Ancylostoma sp. infection. Stool parasitology testing of 174 stool

  8. Onsite LLW storage at Cook

    International Nuclear Information System (INIS)

    MacRae, W.T.

    1994-01-01

    The Donald C. Cook nuclear plant has gained much experience through the onsite storage of low-level radioactive waste. Owned and operated by the Indiana Michigan Power Company, which is owned by American Electric Power, the plant is located in Bridgman, Michigan, on the southeast side of Lake Michigan, about 50 miles from Chicago. In November 1990, waste generators in the state of Michigan were denied access to licensed low-level waste disposal sites because of a lack of progress by the state in developing its own disposal site. Because of this lack, wastes from the Cook plant have been stored onsite for three years. This article covers four issues related to the Cook nuclear plant's experience in the low-level waste storage: storage capacity and waste generation rates, waste form and packages, regulatory issues, and the monitoring of the waste

  9. Feasibility study: Assess the feasibility of siting a monitored retrievable storage facility

    International Nuclear Information System (INIS)

    King, J.W.

    1993-01-01

    The purpose of phase one of this study are: To understand the waste management system and a monitored retrievable storage facility; and to determine whether the applicant has real interest in pursuing the feasibility assessment process. Contents of this report are: Generating electric power; facts about exposure to radiation; handling storage, and transportation techniques; description of a proposed monitored retrievable storage facility; and benefits to be received by host jurisdiction

  10. Proton storage rings

    International Nuclear Information System (INIS)

    Rau, R.R.

    1978-04-01

    A discussion is given of proton storage ring beam dynamic characteristics. Topics considered include: (1) beam energy; (2) beam luminosity; (3) limits on beam current; (4) beam site; (5) crossing angle; (6) beam--beam interaction; (7) longitudinal instability; (8) effects of scattering processes; (9) beam production; and (10) high magnetic fields. Much of the discussion is related to the design parameters of ISABELLE, a 400 x 400 GeV proton---proton intersecting storage accelerator to be built at Brookhaven National Laboratory

  11. QUALITY OF MINIMALLY PROCESSED YAM (Dioscorea sp. STORED AT TWO DIFFERENT TEMPERATURES

    Directory of Open Access Journals (Sweden)

    ADRIANO DO NASCIMENTO SIMÕES

    2016-01-01

    Full Text Available This work studied the physical, chemical and bio chemical alterations in minimally processed yam stored at two different temperatures, as well a s the incidence of bacteria of the genus Pseudomonas . The experimental design was completely randomised in a 2x8 factorial design, with two storage temperature s (5 and 10°C and eight storage times (0, 2, 4, 6, 8, 1 0, 12 and 14 days. Experiments were in triplicate. Yam was selected, peeled and cut into slices of approximate ly 3 cm thickness. The slices were rinsed with wate r, sanitised and then drained in kitchen strainers. Ap proximately 300 g of the processed product were pac ked in nylon multilayers 15 μ m thick, 15 cm wide and 20 cm long. The packs were sealed, weighed and kept at 5 and 10 ± 2°C for 14 days. Fresh weight loss, baking tim e, enzymatic activity of polyphenol oxidases, perox idases and catalases, total soluble phenol content, and an tioxidant capacity were evaluated, as well as visua l analysis and incidence of Pseudomonas sp. Means of temperatures were compared by Tukey ́s test at 5% significance. Yam storage at 5°C reduced weight loss and kept vis ual quality for longer; it also reduced cooking tim e and the activity of the enzymes polyphenol oxidase and pero xidase. In contrast, it promoted higher content of total soluble phenols, as well as a higher catalase activ ity and antioxidant capacity. During the storage ti me, there was no incidence of Pseudomonas sp. Minimally processed yam stored at 10°C may be sold for up to six days, and yam stored at 5ºC for up to 14 days.

  12. Inventory and review of aquifer storage and recovery in southern Florida

    Science.gov (United States)

    Reese, Ronald S.

    2002-01-01

    publications > water resources investigations > report 02-4036 US Department of the Interior US Geological Survey WRI 02-4036Inventory and Review of Aquifer Storage and Recovery in Southern Florida By Ronald S. ReeseTallahassee, Florida 2002 prepared as part of the U.S. Geological Survey Place-Based Studies Program ABSTRACT Abstract Introduction Inventory of Data Case Studies Summary References Tables Aquifer storage and recovery in southern Florida has been proposed on an unprecedented scale as part of the Comprehensive Everglades Restoration Plan. Aquifer storage and recovery wells were constructed or are under construction at 27 sites in southern Florida, mostly by local municipalities or counties located in coastal areas. The Upper Floridan aquifer, the principal storage zone of interest to the restoration plan, is the aquifer being used at 22 of the sites. The aquifer is brackish to saline in southern Florida, which can greatly affect the recovery of the freshwater recharged and stored.Well data were inventoried and compiled for all wells at most of the 27 sites. Construction and testing data were compiled into four main categories: (1) well identification, location, and construction data; (2) hydraulic test data; (3) ambient formation water-quality data; and (4) cycle testing data. Each cycle during testing or operation includes periods of recharge of freshwater, storage, and recovery that each last days or months. Cycle testing data include calculations of recovery efficiency, which is the percentage of the total amount of potable water recharged for each cycle that is recovered.Calculated cycle test data include potable water recovery efficiencies for 16 of the 27 sites. However, the number of cycles at most sites was limited; except for two sites, the highest number of cycles was five. Only nine sites had a recovery efficiency above 10 percent for the first cycle, and 10 sites achieved a recovery efficiency above 30 percent during at least one cycle. The

  13. A Review of Energy Storage Technologies

    DEFF Research Database (Denmark)

    Connolly, David

    2010-01-01

    A brief examination into the energy storage techniques currently available for the integration of fluctuating renewable energy was carried out. These included Pumped Hydroelectric Energy Storage (PHES), Underground Pumped Hydroelectric Energy Storage (UPHES), Compressed Air Energy Storage (CAES...... than PHES depending on the availability of suitable sites. FBES could also be utilised in the future for the integration of wind, but it may not have the scale required to exist along with electric vehicles. The remaining technologies will most likely be used for their current applications...

  14. Data storage accounting and verification in LHC experiments

    CERN Document Server

    Ratnikova ,Natalia

    2012-01-01

    All major experiments at Large Hadron Collider (LHC) need to measure real storage usage at the Grid sites. This information is equally important for the resource management, planning, and operations. To verify consistency of the central catalogs, experiments are asking sites to provide full list of files they have on storage, including size, checksum, and other file attributes. Such storage dumps provided at regular intervals give a realistic view of the storage resource usage by the experiments. Regular monitoring of the space usage and data verification serve as additional internal checks of the system integrity and performance. Both the importance and the complexity of these tasks increase with the constant growth of the total data volumes during the active data taking period at the LHC. Developed common solutions help to reduce the maintenance costs both at the large Tier-1 facilities supporting multiple virtual organizations, and at the small sites that often lack manpower. We discuss requirements...

  15. Effects of CO2 gas as leaks from geological storage sites on agro-ecosystems

    International Nuclear Information System (INIS)

    Patil, Ravi H.; Colls, Jeremy J.; Steven, Michael D.

    2010-01-01

    Carbon capture and storage in geological formations has potential risks in the long-term safety because of the possibility of CO 2 leakage. Effects of leaking gas, therefore, on vegetation, soil, and soil-inhabiting organisms are critical to understand. An artificial soil gassing and response detection field facility developed at the University of Nottingham was used to inject CO 2 gas at a controlled flow rate (1 l min -1 ) into soil to simulate build-up of soil CO 2 concentrations and surface fluxes from two land use types: pasture grassland, and fallow followed by winter bean. Mean soil CO 2 concentrations was significantly higher in gassed pasture plots than in gassed fallow plots. Germination of winter bean sown in gassed fallow plots was severely hindered and the final crop stand was reduced to half. Pasture grass showed stress symptoms and above-ground biomass was significantly reduced compared to control plot. A negative correlation (r = -0.95) between soil CO 2 and O 2 concentrations indicated that injected CO 2 displaced O 2 from soil. Gassing CO 2 reduced soil pH both in grass and fallow plots (p = 0.012). The number of earthworm castings was twice as much in gassed plots than in control plots. This study showed adverse effects of CO 2 gas on agro-ecosystem in case of leakage from storage sites to surface.

  16. Results of ultrasonic testing evaluations on UF6 storage cylinders

    International Nuclear Information System (INIS)

    Lykins, M.L.

    1997-02-01

    The three site cylinder management program is responsible for the safe storage of the DOE owned UF 6 storage cylinders at PORTS, PGDP and at the K-25 site. To ensure the safe storage of the UF 6 in the cylinders, the structural integrity of the cylinders must be evaluated. This report represents the latest cylinder integrity investigation that utilized wall thickness evaluations to identify thinning due to atmospheric exposure

  17. Technical concept for a test of geologic storage of spent reactor fuel in the climax granite, Nevada Test Site

    International Nuclear Information System (INIS)

    Ramspott, L.D.; Ballou, L.B.; Carlson, R.C.; Montan, D.N.; Butkovich, T.R.; Duncan, J.E.; Patrick, W.C.; Wilder, D.G.; Brough, W.G.; Mayr, M.C.

    1979-01-01

    We plan to emplace spent fuel assemblies from an operating commercial nuclear reactor in the Climax granite at the US Department of Energy's Nevada Test Site. In this generic test, 11 canisters of spent fuel will be emplaced with 6 electrical simulator canisters in a storage drift 420 m below in surface and their effects compared. Two adjacent drifts will contain electrical heaters, operated to simulate the temperature-stress-displacement fields of a large repository. We describe the test objectives, the technical issues, the site, the preoperational measurement program, thermal and mechanical response calculations, the characteristics of the spent fuel, the field instrumentation and data-acquisition systems, and the system for handling the spent fuel

  18. Antibacterial Actions and Potential Phototoxic Effects of Volatile oils of Foeniculum sp. (fennel, Salvia sp. (sage, Vitis sp. (grape, Lavandula sp. (lavender

    Directory of Open Access Journals (Sweden)

    Elif Ayse Erdogan Eliuz

    2016-09-01

    Full Text Available In the present study, the volatile compounds of essential oil of Foeniculum vulgare (fennel, Salvia officinalis (sage, Vitis vinifera (grape, Lavandula angustifolia (lavender were analysed by gas chromatography-mass spectrometry (GC-MS using the Nist and Willey libraries. It was determined that the main components of Foeniculum sp. were anethole (41.11%, carvacrol (9.18%. whereas main components of Salvia sp were 1.8 cineole (34.09%, caryophyllene (10.95%, camphor (9.44%, α-pinene (8.42%. Vitis sp. contained linoleic acid (36.98%, 2,4-decadienal (30.79%. Finally, volatile component of Lavandula sp. was linalool (33.57%, linalyl acetate (30.74%. Photoxic antibacterial activity of volatile oil of those plants against Escherichia coli (ATCC 25293, Klebsiella pneumoniae (10031, Salmonella thyphimurium, Bacillus subtilis (ATCC 6633, Staphylococcus aureus (ATCC 25925, Enterococcus feacalis (ATCC 29212 were examined by using disc diffusion method. We demonstrated that volatile oil effectively can be activated by a standard LED light. In vitro, significant phototoxicity was demonstrated by volatile oil of Foeniculum sp. and Vitis sp. (P < 0.05, while minor phototoxicity was induced by Lavandula sp. Therefore, volatile oil of plant can be considered as a potential photosensitizer in the photochemical therapy.

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

    International Nuclear Information System (INIS)

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

    2008-01-01

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

  20. Identifying the Dynamic Catchment Storage That Does Not Drive Runoff

    Science.gov (United States)

    Dralle, D.; Hahm, W. J.; Rempe, D.; Karst, N.; Thompson, S. E.; Dietrich, W. E.

    2017-12-01

    The central importance of subsurface water storage in hydrology has resulted in numerous attempts to develop hydrograph and mass balance based techniques to quantify catchment storage state or capacity. In spite of these efforts, relatively few studies have linked catchment scale storage metrics to Critical Zone (CZ) structure and the status of water in hillslopes. Elucidating these relationships would increase the interpretability of catchment storage metrics, and aid the development of hydrologic models. Here, we propose that catchment storage consists of a dynamic component that varies on seasonal timescales, and a static component with negligible time variation. Discharge is assumed to be explicitly sensitive to changes in some fraction of the dynamic storage, while the remaining dynamic storage varies without directly influencing flow. We use a coupled mass balance and storage-discharge function approach to partition dynamic storage between these driving and non-driving storage pools, and compare inferences with direct observations of saturated and unsaturated dynamic water storages at two field sites in Northern California. We find that most dynamic catchment water storage does not drive streamflow in both sites, even during the wettest times of year. Moreover, the physical character of non-driving dynamic storage depends strongly on catchment CZ structure. At a site with a deep profile of weathered rock, the dynamic storage that drives streamflow occurs as a seasonally perched groundwater table atop fresh bedrock, and that which does not drive streamflow resides as seasonally dynamic unsaturated water in shallow soils and deep, weathered rock. At a second site with a relatively thin weathered zone, water tables rapidly rise to intersect the ground surface with the first rains of the wet season, yet only a small fraction of this dynamic saturated zone storage drives streamflow. Our findings emphasize how CZ structure governs the overlap in time and space of

  1. CHARACTERIZING DOE HANFORD SITE WASTE ENCAPSULATION STORAGE FACILITY CELLS USING RADBALL

    Energy Technology Data Exchange (ETDEWEB)

    Farfan, E.; Coleman, R.

    2011-03-31

    RadBall{trademark} is a novel technology that can locate and quantify unknown radioactive hazards within contaminated areas, hot cells, and gloveboxes. The device consists of a colander-like outer tungsten collimator that houses a radiation-sensitive polymer semi-sphere. The collimator has a number of small holes with tungsten inserts; as a result, specific areas of the polymer are exposed to radiation becoming increasingly more opaque in proportion to the absorbed dose. The polymer semi-sphere is imaged in an optical computed tomography scanner that produces a high resolution 3D map of optical attenuation coefficients. A subsequent analysis of the optical attenuation data using a reverse ray tracing or backprojection technique provides information on the spatial distribution of gamma-ray sources in a given area forming a 3D characterization of the area of interest. RadBall{trademark} was originally designed for dry deployments and several tests, completed at Savannah River National Laboratory and Oak Ridge National Laboratory, substantiate its modeled capabilities. This study involves the investigation of the RadBall{trademark} technology during four submerged deployments in two water filled cells at the DOE Hanford Site's Waste Encapsulation Storage Facility.

  2. Data storage accounting and verification at LHC experiments

    Energy Technology Data Exchange (ETDEWEB)

    Huang, C. H. [Fermilab; Lanciotti, E. [CERN; Magini, N. [CERN; Ratnikova, N. [Moscow, ITEP; Sanchez-Hernandez, A. [CINVESTAV, IPN; Serfon, C. [Munich U.; Wildish, T. [Princeton U.; Zhang, X. [Beijing, Inst. High Energy Phys.

    2012-01-01

    All major experiments at the Large Hadron Collider (LHC) need to measure real storage usage at the Grid sites. This information is equally important for resource management, planning, and operations. To verify the consistency of central catalogs, experiments are asking sites to provide a full list of the files they have on storage, including size, checksum, and other file attributes. Such storage dumps, provided at regular intervals, give a realistic view of the storage resource usage by the experiments. Regular monitoring of the space usage and data verification serve as additional internal checks of the system integrity and performance. Both the importance and the complexity of these tasks increase with the constant growth of the total data volumes during the active data taking period at the LHC. The use of common solutions helps to reduce the maintenance costs, both at the large Tier1 facilities supporting multiple virtual organizations and at the small sites that often lack manpower. We discuss requirements and solutions to the common tasks of data storage accounting and verification, and present experiment-specific strategies and implementations used within the LHC experiments according to their computing models.

  3. MX Siting Investigation. Preliminary Biological and Cultural Resources Inventory and Environmental Evaluation of the Proposed Operational Base Sites in Coyote Spring Valley and the Milford-Beryl Area.

    Science.gov (United States)

    1981-03-20

    Stanleya pinriata (desert prince- plume) Stanleya sp. X CACTACEAE Echinocereus engelmannii (Engel- X X X X X X mann echinocereus) Ferocactus acanthodes...TABLE 3-3 (Cont.) Site Number Species 1 2 3 4 5 6 7 8 9 CACTACEAE (Cont.) Ferocactus sp X X X X *Neolloydia sp. X *-Opuntia basilaris (beavertail X X

  4. Safety assessment document for spent fuel handling, packaging, and storage demonstrations at the E-MAD facility on the Nevada Test Site

    International Nuclear Information System (INIS)

    1985-04-01

    The objectives for spent fuel handling and packaging demonstration are to develop the capability to satisfactorily encapsulate typical commercial nuclear reactor spent fuel assemblies and to establish the suitability of interim dry surface and near surface storage concepts. To accomplish these objectives, spent fuel assemblies from a pressurized water reactor have been received, encapsulated in steel canisters, and emplaced in on-site storage facilities and subjected to other tests. As an essential element of these demonstrations, a thorough safety assessment of the demonstration activities conducted at the E-MAD facility has been completed. This document describes the site location and characteristics, the existing E-MAD facility, and the facility modifications and equipment additions made specifically for the demonstrations. The document also summarizes the Quality Assurance Program utilized, and specifies the principal design criteria applicable to the facility modifications, equipment additions, and process operations. Evaluations have been made of the radiological impacts of normal operations, abnormal operations, and postulated accidents. Analyses have been performed to determine the affects on nuclear criticality safety of postulated accidents and credible natural phenomena. The consequences of postulated accidents resulting in fission product gas release have also been estimated. This document identifies the engineered safety features, procedures, and site characteristics that (1) prevent the occurrence of potential accidents or (2) assure that the consequences of postulated accidents are either insignificant or adequately mitigated

  5. Modifications to an existing waste containment structure at Niagara Falls Storage Site

    International Nuclear Information System (INIS)

    Paez-Restrepo, A.; Darby, J.W.

    1992-01-01

    The Niagara Falls Storage Site (NFSS), located near Lewiston, New York, is an interim waste containment facility for low-level radioactive waste. The facility was completed in 1986 and is managed for the Department of Energy (DOE) by Bechtel National, Inc. (BNI) as part of the Formerly Utilized Sites Remedial Action Program (FUSRAP). The waste containment structure (WCS) at NFSS is approximately 297 m (975 ft) long and 137 m (450 ft) wide and reaches a maximum height of 10.4 m (34 ft). The peripheral slopes rise at an angle of 3:1 (h:v) for a width of about 16.8 m (55 ft), where the inclination decreases to 7.5%. The apex of the pile is higher at the south end, sloping about 1.2 m (4 ft) to the north. The interim layered cap consists of 0.9 m (3 ft) of clay overlain by 0.45 m (1.5 ft) of topsoil. The uppermost 15 cm (6 in.) of soil was loosely compacted to permit the development of a grass cover. In the summer of 1991, approximately 2,677 m 3 (3,500 yd 3 ) of additional contaminated soil and material in temporary storage elsewhere at NFSS was incorporated into the WCS. To accommodate the waste, a portion of the cap roughly centered with the pile [including 0.45 m (1.5 ft) of topsoil and 0.6 m (2 ft) of clay cap] was removed from an area 99 m (325 ft) long and 58.5 m (192 ft) wide, leaving a minimum of 0.3 m (I ft) of clay over the old waste as a radiation and radon barrier. The newly incorporated waste forms a layer 0.6 m (2 ft) thick, replacing the clay portion of the excavated cap. The waste is contained laterally by the old cap and sealed by a new cap, which also consists of 0.9 m (3 ft) of compacted clay and 0.45 m (1.5 ft) of topsoil. A transition zone about 6.1 m (20 ft) wide feathers the new cap to the old cap (see Fig. 3). Except for the uppermost 10.5 to 15.2 cm (4 to 6 in.) of vegetated topsoil, the excavated cap materials were stockpiled and reused in constructing the new cap. Additional material required to complete cap construction was imported from

  6. Spent nuclear fuel storage. (Latest citations from the NTIS bibliographic database). Published Search

    International Nuclear Information System (INIS)

    1997-07-01

    The bibliography contains citations concerning spent nuclear fuel storage technologies, facilities, sites, and assessment. References review wet and dry storage, spent fuel casks and pools, underground storage, monitored and retrievable storage systems, and aluminum-clad spent fuels. Environmental impact, siting criteria, regulations, and risk assessment are also discussed. Computer codes and models for storage safety are covered. (Contains 50-250 citations and includes a subject term index and title list.) (Copyright NERAC, Inc. 1995)

  7. Current status of the first interim spent fuel storage facility in Japan

    International Nuclear Information System (INIS)

    Shinbo, Hitoshi; Kondo, Mitsuru

    2008-01-01

    In Japan, storage of spent fuels outside nuclear power plants was enabled as a result of partial amendments to the Nuclear Reactor Regulation Law in June 2000. Five months later, Mutsu City in Aomori Prefecture asked the Tokyo Electric Power Company (TEPCO) to conduct technical surveys on siting of the interim spent fuel storage facility (we call it 'Recyclable-Fuel Storage Center'). In April 2003, TEPCO submitted the report on siting feasibility examination, concluded that no improper engineering data for siting, construction of the facility will be possible from engineering viewpoint. Siting Activities for publicity and public acceptance have been continued since then. After these activities, Aomori Prefecture and Mutsu City approved siting of the Recyclable Fuel Storage Center in October 2005. Aomori Prefecture, Mutsu City, TEPCO and Japan Atomic Power Company (JAPC) signed an agreement on the interim spent fuel storage Facility. A month later, TEPCO and JAPC established Recyclable-Fuel Storage Company (RFS) in Mutsu City through joint capital investment, specialized in the first interim spent fuel storage Facility in Japan. In May 2007, we made an application for establishment permit, following safety review by regulatory authorities. In March 2008, we started the preparatory construction. RFS will safely store of spent fuels of TEPCO and JAPC until they will be reprocessed. Final storage capacity will be 5,000 ton-U. First we will construct the storage building of 3,000 ton-U to be followed by second building. We aim to start operation by 2010. (author)

  8. Monitored Retrievable Storage System Requirements Document. Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    1994-03-01

    This Monitored Retrievable Storage System Requirements Document (MRS-SRD) describes the functions to be performed and technical requirements for a Monitored Retrievable Storage (MRS) facility subelement and the On-Site Transfer and Storage (OSTS) subelement. The MRS facility subelement provides for temporary storage, at a Civilian Radioactive Waste Management System (CRWMS) operated site, of spent nuclear fuel (SNF) contained in an NRC-approved Multi-Purpose Canister (MPC) storage mode, or other NRC-approved storage modes. The OSTS subelement provides for transfer and storage, at Purchaser sites, of spent nuclear fuel (SNF) contained in MPCs. Both the MRS facility subelement and the OSTS subelement are in support of the CRWMS. The purpose of the MRS-SRD is to define the top-level requirements for the development of the MRS facility and the OSTS. These requirements include design, operation, and decommissioning requirements to the extent they impact on the physical development of the MRS facility and the OSTS. The document also presents an overall description of the MRS facility and the OSTS, their functions (derived by extending the functional analysis documented by the Physical System Requirements (PSR) Store Waste Document), their segments, and the requirements allocated to the segments. In addition, the top-level interface requirements of the MRS facility and the OSTS are included. As such, the MRS-SRD provides the technical baseline for the MRS Safety Analysis Report (SAR) design and the OSTS Safety Analysis Report design.

  9. Transcription of human resistin gene involves an interaction of Sp1 with peroxisome proliferator-activating receptor gamma (PPARgamma.

    Directory of Open Access Journals (Sweden)

    Anil K Singh

    2010-03-01

    Full Text Available Resistin is a cysteine rich protein, mainly expressed and secreted by circulating human mononuclear cells. While several factors responsible for transcription of mouse resistin gene have been identified, not much is known about the factors responsible for the differential expression of human resistin.We show that the minimal promoter of human resistin lies within approximately 80 bp sequence upstream of the transcriptional start site (-240 whereas binding sites for cRel, CCAAT enhancer binding protein alpha (C/EBP-alpha, activating transcription factor 2 (ATF-2 and activator protein 1 (AP-1 transcription factors, important for induced expression, are present within sequences up to -619. Specificity Protein 1(Sp1 binding site (-276 to -295 is also present and an interaction of Sp1 with peroxisome proliferator activating receptor gamma (PPARgamma is necessary for constitutive expression in U937 cells. Indeed co-immunoprecipitation assay demonstrated a direct physical interaction of Sp1 with PPARgamma in whole cell extracts of U937 cells. Phorbol myristate acetate (PMA upregulated the expression of resistin mRNA in U937 cells by increasing the recruitment of Sp1, ATF-2 and PPARgamma on the resistin gene promoter. Furthermore, PMA stimulation of U937 cells resulted in the disruption of Sp1 and PPARgamma interaction. Chromatin immunoprecipitation (ChIP assay confirmed the recruitment of transcription factors phospho ATF-2, Sp1, Sp3, PPARgamma, chromatin modifier histone deacetylase 1 (HDAC1 and the acetylated form of histone H3 but not cRel, C/EBP-alpha and phospho c-Jun during resistin gene transcription.Our findings suggest a complex interplay of Sp1 and PPARgamma along with other transcription factors that drives the expression of resistin in human monocytic U937 cells.

  10. Analysis of Dust Samples Collected from an In-Service Interim Storage System at the Maine Yankee Nuclear Site.

    Energy Technology Data Exchange (ETDEWEB)

    Bryan, Charles R.; Enos, David

    2016-10-01

    In July, 2016, the Electric Power Research Institute and industry partners performed a field test at the Maine Yankee Nuclear Site, located near Wiscasset, Maine. The primary goal of the field test was to evaluate the use of robots in surveying the surface of an in-service interim storage canister within an overpack; however, as part of the demonstration, dust and soluble salt samples were collected from horizontal surfaces within the interim storage system. The storage system is a vertical system made by NAC International, consisting of a steel-lined concrete overpack containing a 304 stainless steel (SS) welded storage canister. The canister did not contain spent fuel but rather greater-than-class-C waste, which did not generate significant heat, limiting airflow through the storage system. The surfaces that were sampled for deposits included the top of the shield plug, the side of the canister, and a shelf at the bottom of the overpack, just below the level of the pillar on which the canister sits. The samples were sent to Sandia National Laboratories for analysis. This report summarizes the results of those analyses. Because the primary goal of the field test was to evaluate the use of robots in surveying the surface of the canister within the overpack, collection of dust samples was carried out in a qualitative fashion, using paper filters and sponges as the sampling media. The sampling focused mostly on determining the composition of soluble salts present in the dust. It was anticipated that a wet substrate would more effectively extract soluble salts from the surface that was sampled, so both the sponges and the filter paper were wetted prior to being applied to the surface of the metal. Sampling was accomplished by simply pressing the damp substrate against the metal surface for two minutes, and then removing it. It is unlikely that the sampling method quantitatively collected dust or salts from the metal surface; however, both substrates did extract a

  11. Engineering evaluation of alternatives for the disposition of Niagara Falls Storage Site, its residues and wastes

    International Nuclear Information System (INIS)

    1984-01-01

    The final disposition scenarios selected by DOE for assessment in this document are consistent with those stated in the Notice of Intent to prepare an Environmental Impact Statement (EIS) for the Niagara Falls Storage Site (NFSS) (DOE, 1983d) and the modifications to the alternatives resulting from the public scoping process. The scenarios are: take no action beyond interim remedial measures other than maintenance and surveillance of the NFSS; retain and manage the NFSS as a long-term waste management facility for the wastes and residues on the site; decontaminate, certify, and release the NFSS for other use, with long-term management of the wastes and residues at other DOE sites; and partially decontaminate the NFSS by removal and transport off site of only the more radioactive residues, and upgrade containment of the remaining wastes and residues on site. The objective of this document is to present to DOE the conceptual engineering, occupational radiation exposure, construction schedule, maintenance and surveillance requirements, and cost information relevant to design and implementation of each of the four scenarios. The specific alternatives within each scenario used as the basis for discussion in this document were evaluated on the bases of engineering considerations, technical feasibility, and regulatory requirements. Selected alternatives determined to be acceptable for each of the four final disposition scenarios for the NFSS were approved by DOE to be assessed and costed in this document. These alternatives are also the subject of the EIS for the NFSS currently being prepared by Argonne National Laboratory (ANL). 40 figures, 38 tables

  12. Bradysia sp. em morangueiro Bradysia sp. in strawberry

    Directory of Open Access Journals (Sweden)

    Bernadete Radin

    2009-04-01

    Full Text Available No trabalho, relatam-se os primeiros registros de Bradysia sp. (Insecta: Diptera: Sciaridae em morangueiro (Fragaria x ananassa Duch., cultivado no Município de Eldorado do Sul, RS. O cultivo foi realizado em sacolas com três metros de comprimento, preenchidas com substrato composto de casca de arroz e turfa, dispostas horizontalmente sobre bancadas de madeira, em ambiente protegido. A presença de Bradysia sp. foi observada na segunda quinzena de agosto de 2005. Neste trabalho, estão descritos os sintomas apresentados no morangueiro pela praga, prováveis conseqüências sobre o aparecimento de doenças e uma breve descrição morfológica da Bradysia sp., adulto e fase larval.This paper describes the first record of Bradysia sp. (Insecta; Diptera; Sciaridae in strawberry (Fragaria x ananassa, cultivated in the city of Eldorado do Sul, RS, Brazil. Strawberry was planted in plastic bags filled with a mixture of burnt rice hulls and peat and cultivated in a greenhouse. The presence of Bradysia sp was noticed in the second fortnight of August, 2005. The symptoms in strawberry and the probable consequences in terms of disease arising were described in the present study, as well as the morphological characterization of Bradysia sp. and its illustrations.

  13. System Specification for Immobilized High-Level Waste Interim Storage

    International Nuclear Information System (INIS)

    CALMUS, R.B.

    2000-01-01

    This specification establishes the system-level functional, performance, design, interface, and test requirements for Phase 1 of the IHLW Interim Storage System, located at the Hanford Site in Washington State. The IHLW canisters will be produced at the Hanford Site by a Selected DOE contractor. Subsequent to storage the canisters will be shipped to a federal geologic repository

  14. Storage of non-defense production reactor spent nuclear fuel at the Department of Energy's Hanford Site

    International Nuclear Information System (INIS)

    Carlson, A.B.

    1998-01-01

    In 1992, the US Department of Energy (DOE) established a program at the Hanford Site for management of DOE-owned spent nuclear fuel (SNF) until final disposition. Currently, the DOE-owned SNF Program is developing and implementing plans to assure existing storage, achieve interim storage, and prepare DOE-owned SNF for final disposition. Program requirements for management of the SNF are delineated in the DOE-owned SNF Program Plan.(DOE 1995a) and the DOE Spent Fuel Program's Requirements Document (DOE 1994a). Major program requirements are driven by the following: commitments established in the Defense Nuclear Facilities Safety Board (DNFSB) Recommendation 94-1 Implementation Plan (DOE 1995b); corrective action plans for resolving vulnerabilities identified in the DOE Spent Fuel Working Group's Report on Health, Safety, and Environmental Vulnerabilities for Reactor Irradiated Nuclear Materials (DOE 1993); the settlement agreement between the US Department of Navy, the US Department of Energy, and the State of Idaho on the record of decision (ROD) from the DOE Programmatic SNF Management and Idaho National Engineering Laboratory Environmental Restoration and Waste Management Programs Environmental Impact Statement (DOE Programmatic SNF EIS) (Idaho, 1995)

  15. Dry cask storage: a Vepco/DOE/EPRI cooperative demonstration program

    International Nuclear Information System (INIS)

    Smith, M.L.

    1984-01-01

    In response to a Department of Energy (DOE) Solicitation for Cooperative Agreement Proposal, Virginia Electric and Power Company (Vepco) proposed to participate in a spent fuel storage demonstration program utilizing the dry cask storage technology. This proposed program includes dry cask storage at Vepco's Surry Nuclear Power Station and research and development activities at a DOE site in support of the licensed program at Surry. Phase I of Vepco's two-phase program involves a demonstration of the licensed dry cask storage of spent fuel in an inert atmosphere at the Surry Power Station site. Phase II of Vepco's proposed program will involve the demonstration of storing unconsolidated and consolidated spent fuel in dry casks filled only with air. This phase of the program will involve DOE site testing similar to Phase I and is expected to require an additional (fourth) cask to demonstrate storage of unconsolidated spent fuel in air-filled casks

  16. Interim spent-fuel storage options at commercial nuclear power plants

    International Nuclear Information System (INIS)

    Thakkar, A.R.; Hylko, J.M.

    1991-01-01

    Although spent fuel can be stored safely in waterfilled pools at reactor sites, some utilities may not possess sufficient space for life-of-plant storage capability. In-pool storage capability may be increased by reracking assemblies, rod consolidation, double tiering spent-fuel racks, and by shipping spent fuel to other utility-owned facilities. Long-term on-site storage capability for spent fuel may be provided by installing (dry-type) metal casks, storage and transportation casks, concrete casks, horizontal concrete modules, modular concrete vaults, or by constructing additional (pool-type) storage installations. Experience to date has provided valuable information regarding dry-type or pool-type installations, cask handling and staffing requirements, security features, decommissioning activities, and radiological issues

  17. Unsaturated zone investigation at the radioactive waste storage facility site

    Energy Technology Data Exchange (ETDEWEB)

    Skuratovic, Zana; Mazeika, Jonas; Petrosius, Rimantas; Jakimaviciute-Maseliene, Vaidote [Nature Research Centre, Akademijos St. 2, LT-08412, Vilnius (Lithuania); Klizas, Petras; Mokrik, Robert [Vilnius University, M.K. Ciurlionio St. 21/27, LT-03101 Vilnius (Lithuania)

    2014-07-01

    Unsaturated zone is an important part of water circulation cycle and an integral part of many hydrological and hydrogeological factors and processes. The soils of unsaturated zone are regarded as the first natural barrier to a large extent able to limit the spread of contaminants. Nuclear waste disposal site (Maisiagala radioactive waste storage facility site) was analysed in terms of the moisture movement through the unsaturated zone. Extensive data sets of the hydraulic properties, water content and isotope composition have been collected and summarized. The main experimental and observational tasks included the collection of soil samples; determination of the physical properties and the hydraulic conductivity values of soil samples, moisture extraction from the soil sample for isotopic studies; observation of the groundwater dynamics at the Maisiagala piezometer; groundwater sampling for isotopic analysis ({sup 3}H, {sup 18}O/{sup 16}O, {sup 2}H/{sup 1}H ); and monthly precipitation isotopic analysis. Distribution features of globally widespread radionuclide tritium ({sup 3}H) and the water molecule tracer isotopes in precipitation, unsaturated zone soil moisture profiles and groundwater were determined. It was used the well-known unsaturated flow and transport model of HYDRUS-1D (Simunek et al., 2008). In this study, van Genuchten equations for the retention and conductivity estimations have been used. The retention characteristics and van Genuchten model parameters were estimated internally by HYDRUS based on the empirical equations involved in the program. Basic inputs of the tritium transport simulation are the tritium input function and meteorological variables (precipitation and potential evapotranspiration). In order to validate the representativeness of the hydraulic parameters, the model has been used to estimate the tritium distribution in the unsaturated zone, which properly represents the dynamics of the unsaturated zone. The uniformity of the daily

  18. The US Department of Energy's attempt to site the Monitored Retrievable Storage Facility (MRS) in Tennessee, 1985--1987

    International Nuclear Information System (INIS)

    Fitzgerald, M.R.; McCabe, A.S.

    1988-05-01

    This report is concerned with how America's public sector is handling the challenge of implementing a technical, environmental policy, that of managing the nation's high-level nuclear waste, as reflected in the attempt of the US Department of Energy (DOE) to site a Monitored Retrievable Storage Facility (MRS) for high-level radioactive waste in Tennessee. It has been observed that ''radioactive wastes present some of societies' most complex and vexing choices.'' There is deep and abiding disagreement about almost every aspect of radioactive waste management (RWM)

  19. NF1, Sp1 and HSF1 are synergistically involved in sulfide-induced sqr activation in echiuran worm Urechis unicinctus

    Energy Technology Data Exchange (ETDEWEB)

    Liu, Xiaolong; Qin, Zhenkui; Li, Xueyu; Ma, Xiaoyu; Gao, Beibei; Zhang, Zhifeng, E-mail: zzfp107@ouc.edu.cn

    2016-06-15

    Highlights: • Sulfide activates sqr transcription against respiratory toxicity in Urechis unicinctus. • Sulfide increases expressions and activities of NF1, Sp1 and HSF1 in a time-dependent manner. • NF1 and Sp1 participate in both basal and early sulfide-induced sqr transcription. • HSF1 functions more significantly than NF1 and Sp1 in sulfide-induced sqr transcription. • Transcription factors NF1, Sp1 and HSF1 enhance sqr promoter activity synergistically. - Abstract: Background: Sulfide is a well-known environmental toxic substance. Mitochondrial sulfide oxidation is a main mechanism of sulfide detoxification in organisms, and sulfide: quinone oxidoreductase (SQR) is a key enzyme which is involved in transferring electrons from sulfide to ubiquinone and converting sulfide into thiosulfate. Previous studies have revealed the SQR-mediated mitochondrial sulfide oxidation exists in the echiuran worm Urechis unicinctus, and its sqr mRNA level increased significantly when the worm is exposed to sulfide. In this study, we attempt to reveal the synergistic regulation of transcription factors on sulfide-induced sqr transcription in U. unicinctus. Methods: ChIP and EMSA were used to identify the interactions between sqr proximal promoter (from −391 to +194 bp) and transcription factors NF1 (nuclear factor 1) and Sp1 (specificity protein 1). Site-directed mutation and transfection assays further revealed their binding sites and synergistic roles of HSF1, NF1 and Sp1 in the sqr transcription. When U. unicinctus were exposed to 150 μM sulfide, the expression levels and nuclear contents of NF1 and Sp1 were examined by Western blotting, and the binding contents between NF1 or Sp1 and the sqr promoter were also detected by ChIP. Results: Transcription factors NF1 and Sp1 were confirmed to interact with the sqr proximal promoter, and their binding sites were identified in −75 to −69 bp for NF1 and −210 to −201 bp for Sp1. Transfection assays showed mutation

  20. Maywood Interim Storage Site environmental report for calendar year 1992, 100 West Hunter Avenue, Maywood, New Jersey

    International Nuclear Information System (INIS)

    1993-05-01

    This report describes the environmental surveillance program at the Maywood Interim Storage Site (MISS) and provides the results for 1992. Environmental monitoring of MISS began in 1984, when the site was assigned to DOE by Congress through the Energy and Water Development Appropriations Act and was placed under DOE's Formerly Utilized Sites Remedial Action Program (FUSRAP). FUSRAP was established to identify and decontaminate or otherwise control sites where residual radioactive materials remain from the early years of the nation's atomic energy program or from commercial operations causing conditions that Congress has authorized DOE to remedy. MISS is part of a National Priorities List (NPL) site. The environmental surveillance program at MISS includes sampling networks for radon and thoron in air; external gamma radiation exposure; and radium-226, radium-228, thorium-232, and total uranium in surface water, sediment, and groundwater. Additionally, chemical analysis includes metals and organic compounds in surface water and groundwater and metals in sediments. This program assists in fulfilling the DOE objective of measuring and monitoring effluents from DOE activities and calculating hypothetical doses to members of the general public. Monitoring results are compared with applicable Environmental Protection Agency (EPA) and state standards, DOE derived concentration guides (DCGs), dose limits, and other DOE requirements. Environmental standards are established to protect public health and the environment. The radiological data for all media sampled support the conclusion that doses to the public are not distinguishable from natural background radiation

  1. Assessment of Ademe's R and D actions for the CO2 capture and storage sector

    International Nuclear Information System (INIS)

    2015-05-01

    This publication presents research actions and projects supported by the ADEME in the field of CO 2 capture and storage. This programme aims at promoting the emergence of significant innovations, at developing the national technology portfolio, at identifying and reducing uncertainties related to exploitation, and at developing and strengthening its technological integration in manufacturing industry and energy sectors. While indicating the invested amount, research demonstrator projects are mentioned. Results obtained between 2007 and 2013 in different fields are briefly described: technical-economic studies or pre-feasibility studies, CO 2 capture (capture in post-combustion or in oxy-combustion), CO 2 geological storage (site selection, knowledge development on storage site sustainability, safety of CO 2 storage sites, monitoring of CO 2 storage sites, environmental impacts of storage sites), and issue of social feasibility of CO 2 capture and storage

  2. Niagara Falls storage site annual environmental report for calendar year 1990, Lewiston, New York

    International Nuclear Information System (INIS)

    1991-08-01

    Environmental monitoring of the US DOE Niagara Falls Storage Site (NFSS) and surrounding area began in 1981. NFSS is part of a DOE program to decontaminate or otherwise control sites where residual radioactive materials remain from the early years of the nation's atomic energy program or from commercial, operations causing conditions the Congress has authorized DOE to remedy. Environmental monitoring systems at NFSS include sampling networks for radon concentrations in air; external gamma radiation exposure; and total uranium and radium-226 concentrations in surface water sediments, and groundwater. Additionally, several nonradiological parameters are routinely measured in groundwater. During 1990, the average ambient air radon concentration (including background) at NFSS ranged from 0.3 to 0.7 pCi/L (0.01 to 0.03 Bq/L); the maximum at any location for any quarter was 1.6 pCi/L (0.06 Bq/L). The average on-site external gamma radiation exposure level was 69 mR/yr; the average at the property line was 68 mR/yr (including background). The average background radiation level in the area was 66 mR/yr. Average annual concentrations of radium-226 and total uranium in surface water ranged from 0.4E-9 to 0.9E-9 μCi/m1 (0.02 to 0.03 Bq/L) and from 5E-9 to 9E-9 μCi/m1 (0.2 to 0.3 Bq/L), respectively. Routine analyses of groundwater samples from NFSS included the indicator parameters total organic carbon, total organic halides, pH, and specific conductivity

  3. Niagara Falls storage site annual environmental report for calendar year 1990, Lewiston, New York

    Energy Technology Data Exchange (ETDEWEB)

    1991-08-01

    Environmental monitoring of the US DOE Niagara Falls Storage Site (NFSS) and surrounding area began in 1981. NFSS is part of a DOE program to decontaminate or otherwise control sites where residual radioactive materials remain from the early years of the nation's atomic energy program or from commercial, operations causing conditions the Congress has authorized DOE to remedy. Environmental monitoring systems at NFSS include sampling networks for radon concentrations in air; external gamma radiation exposure; and total uranium and radium-226 concentrations in surface water sediments, and groundwater. Additionally, several nonradiological parameters are routinely measured in groundwater. During 1990, the average ambient air radon concentration (including background) at NFSS ranged from 0.3 to 0.7 pCi/L (0.01 to 0.03 Bq/L); the maximum at any location for any quarter was 1.6 pCi/L (0.06 Bq/L). The average on-site external gamma radiation exposure level was 69 mR/yr; the average at the property line was 68 mR/yr (including background). The average background radiation level in the area was 66 mR/yr. Average annual concentrations of radium-226 and total uranium in surface water ranged from 0.4E-9 to 0.9E-9 {mu}Ci/m1 (0.02 to 0.03 Bq/L) and from 5E-9 to 9E-9 {mu}Ci/m1 (0.2 to 0.3 Bq/L), respectively. Routine analyses of groundwater samples from NFSS included the indicator parameters total organic carbon, total organic halides, pH, and specific conductivity.

  4. Ontario hydro waste storage concepts and facilities

    International Nuclear Information System (INIS)

    Carter, T.J.; Mentes, G.A.

    1976-01-01

    Ontario Hydro presently operates 2,200 MWe of CANDU heavy water reactors with a further 11,000 MWe under design or construction. The annual quantities of low and medium level solid wastes expected to be produced at these stations are tabulated. In order to manage these wastes, Ontario Hydro established a Radioactive Waste Operations Site within the Bruce Nuclear Power Development located on Lake Huron about 250 km northwest of Toronto. The Waste Operations Site includes a 19-acre Storage Site plus a Radioactive Waste Volume Reduction Facility consisting of an incinerator and waste compactor. Ontario has in use or under construction both in-ground and above-ground storage facilities. In-ground facilities have been used for a number of years while the above-ground facilities are a more recent approach. Water, either in the form of precipitation, surface or subsurface water, presents the greatest concern with respect to confinement integrity and safe waste handling and storage operations

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2007-09-18

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

  6. INTERAKSI ANTARA Trichoderma Harzianum, Penicillium SP. DAN Pseudomonas SP. SERTA KAPASITAS ANTAGONISMENYA TERHADAP Phytophthora CapsicilN VITRO*[Interaction Among Trichoderma Harzianum, Penicillium SP., Pseudomonas SP. and Antagonism Capacities Against Phy

    OpenAIRE

    Suharna, Nandang

    2003-01-01

    A preliminary study has been done to know antagonism capacities of three isolates of Trichoderma harzianum, two isolates of Penicillium sp.and one isolate of Pseudomonas sp.against Phytophthora capsici in vitro and interaction among those six antagonists.The highest antagonism capacity possessed by Penicillium sp. KN1, respectively followed by Penicillium sp.KN2,Pseudomonas sp. GH1 and the three T. harzianum isolates. Except for those three T. harzianum isolates, the two Penicillium sp.isolat...

  7. Drinking Water Quality Criterion - Based site Selection of Aquifer Storage and Recovery Scheme in Chou-Shui River Alluvial Fan

    Science.gov (United States)

    Huang, H. E.; Liang, C. P.; Jang, C. S.; Chen, J. S.

    2015-12-01

    Land subsidence due to groundwater exploitation is an urgent environmental problem in Choushui river alluvial fan in Taiwan. Aquifer storage and recovery (ASR), where excess surface water is injected into subsurface aquifers for later recovery, is one promising strategy for managing surplus water and may overcome water shortages. The performance of an ASR scheme is generally evaluated in terms of recovery efficiency, which is defined as percentage of water injected in to a system in an ASR site that fulfills the targeted water quality criterion. Site selection of an ASR scheme typically faces great challenges, due to the spatial variability of groundwater quality and hydrogeological condition. This study proposes a novel method for the ASR site selection based on drinking quality criterion. Simplified groundwater flow and contaminant transport model spatial distributions of the recovery efficiency with the help of the groundwater quality, hydrological condition, ASR operation. The results of this study may provide government administrator for establishing reliable ASR scheme.

  8. Intervention in independent spent fuel storage facility license application proceedings for storage on the power plant site

    International Nuclear Information System (INIS)

    Jordan, J.

    1992-01-01

    This presentation summarizes the intervention in the Nuclear Regulatory Commission (NRC) licensing process for currently operating Independent Spent fuel Storage Installation (ISFSI) projects at Carolina Power and Light's Company's H.B. Robinson, Duke Power Company's Oconee, and Virginia Power Company's Surry. In addition, intervention at dry storage facilities that are currently under development are also described. The utilities and reactors include Baltimore Gas and Electric Company's Calvert Cliffs, Public Service Company of Colorado's Fort St. Vrain plant, Northern States Power Company's Prairie Island, Wisconsin Electric Power Company's Point Beach, and Consumers Power Company's Palisades

  9. Assessment of Hanford burial grounds and interim TRU storage

    International Nuclear Information System (INIS)

    Geiger, J.F.; Brown, D.J.; Isaacson, R.E.

    1977-08-01

    A review and assessment is made of the Hanford low level solid radioactive waste management sites and facilities. Site factors considered favorable for waste storage and disposal are (1) limited precipitation, (2) a high deficiency of moisture in the underlying sediments (3) great depth to water table, all of which minimize radionuclide migration by water transport, and (4) high sorbtive capacity of the sediments. Facilities are in place for 20 year retrievable storage of transuranic (TRU) wastes and for disposal of nontransuranic radioactive wastes. Auxiliary facilities and services (utilities, roads, fire protection, shops, etc.) are considered adequate. Support staffs such as engineering, radiation monitoring, personnel services, etc., are available and are shared with other operational programs. The site and associated facilities are considered well suited for solid radioactive waste storage operations. However, recommendations are made for study programs to improve containment, waste package storage life, land use economy, retrievability and security of TRU wastes

  10. Inhibition of xyloglucanase from an alkalothermophilic Thermomonospora sp. by a peptidic aspartic protease inhibitor from Penicillium sp. VM24.

    Science.gov (United States)

    Menon, Vishnu; Rao, Mala

    2012-11-01

    A bifunctional inhibitor from Penicillium sp VM24 causing inactivation of xyloglucanase from Thermomonospora sp and an aspartic protease from Aspergillus saitoi was identified. Steady state kinetics studies of xyloglucanase and the inhibitor revealed an irreversible, non-competitive, two-step inhibition mechanism with IC(50) and K(i) values of 780 and 500nM respectively. The interaction of o-phthalaldehyde (OPTA)-labeled xyloglucanase with the inhibitor revealed that the inhibitor binds to the active site of the enzyme. Far- and near-UV spectrophotometric analysis suggests that the conformational changes induced in xyloglucanase by the inhibitor may be due to irreversible denaturation of enzyme. The bifunctional inhibitor may have potential as a biocontrol agent for the protection of plants against phytopathogenic fungi. Copyright © 2012 Elsevier Ltd. All rights reserved.

  11. Accidental Release of Chlorine from a Storage Facility and an On-Site Emergency Mock Drill: A Case Study

    Directory of Open Access Journals (Sweden)

    Ambalathumpara Raman Soman

    2015-01-01

    Full Text Available In the current industrial scenario there is a serious need for formulating strategies to handle hazardous substances in the safest way. Manufacture, storage, and use of hazardous substances pose a serious risk to industry, people, and the environment. Accidental release of toxic chemicals can lead to emergencies. An emergency response plan (ERP is inevitable to minimize the adverse effects of such releases. The on-site emergency plan is an integral component of any process safety and risk management system. This paper deals with an on-site emergency response plan for a chlorine manufacturing industry. It was developed on the basis of a previous study on chlorine release and a full scale mock drill has been conducted for testing the plan. Results indicated that properly trained personnel can effectively handle each level of incidents occurring in the process plant. As an extensive guideline to the district level government authorities for off-site emergency planning, risk zone has also been estimated with reference to a chlorine exposure threshold of 3 ppm.

  12. Differences in nutrient uptake capacity of the benthic filamentous algae Cladophora sp., Klebsormidium sp. and Pseudanabaena sp. under varying N/P conditions.

    Science.gov (United States)

    Liu, Junzhuo; Vyverman, Wim

    2015-03-01

    The N/P ratio of wastewater can vary greatly and directly affect algal growth and nutrient removal process. Three benthic filamentous algae species Cladophora sp., Klebsormidium sp. and Pseudanabaena sp. were isolated from a periphyton bioreactor and cultured under laboratory conditions on varying N/P ratios to determine their ability to remove nitrate and phosphorus. The N/P ratio significantly influenced the algal growth and phosphorus uptake process. Appropriate N/P ratios for nitrogen and phosphorus removal were 5-15, 7-10 and 7-20 for Cladophora sp., Klebsormidium sp. and Pseudanabaena sp., respectively. Within these respective ranges, Cladophora sp. had the highest biomass production, while Pseudanabaena sp. had the highest nitrogen and phosphorus contents. This study indicated that Cladophora sp. had a high capacity of removing phosphorus from wastewaters of low N/P ratio, and Pseudanabaena sp. was highly suitable for removing nitrogen from wastewaters with high N/P ratio. Copyright © 2014 Elsevier Ltd. All rights reserved.

  13. CARBON STORAGE AND FLUXES IN PONDEROSA PINE AT DIFFERENT SUCCESSIONAL STAGES

    Science.gov (United States)

    We compared carbon storage and fluxes in young and old ponderosa pine stands in Oregon, including plant and soil storage, net primary productivity, respiration fluxes, and eddy flux estimates of net ecosystem exchange. The young site (Y site) was previously an old-growth pondero...

  14. Technical concept for test of geologic storage of spent reactor fuel in the Climax granite, Nevada Test Site

    International Nuclear Information System (INIS)

    Ramspott, L.D.; Ballou, L.B.; Carlson, R.C.; Montan, D.N.; Butkovich, T.R.; Duncan, J.E.; Patrick, W.C.; Wilder, D.G.; Brough, W.G.; Mayr, M.C.

    1979-01-01

    The Spent Fuel Test in the Climax granite at the Nevada Test Site is a generic test in which spent fuel assemblies from an operating commercial nuclear reactor are emplaced at, and retrieved from, a plausible waste repository depth in a typical granite. Eleven canisters of spent fuel are emplaced in a storage drift 420 m below the surface along with six electrical simulator canisters. Two adjacent drifts contain electrical heaters which are operated so as to simulate the initial five years of the temperature-stress-displacement fields of a large repository. The site is described, and the pre-operational measurement program and characteristics of the spent fuel are given. Both thermal and mechanical response calculations are summarized. The field instrumentation and data acquisition systems are described, as well as the system for handling the spent fuel

  15. Tannin Acyl Hydrolase Production by Citrobacter sp. isolated from ...

    African Journals Online (AJOL)

    Bacterial isolate, Citrobacter sp., from tannery effluent loaded sites has proved as a potent producer of tannase. Production of tannase was compared in solid-state and submerged fermentation using tamarind seed as sole carbon source. Two times increase in tannase activity was seen in solid-state fermentation (90 U) than ...

  16. Utilization of Integrated Assessment Modeling for determining geologic CO2 storage security

    Science.gov (United States)

    Pawar, R.

    2017-12-01

    Geologic storage of carbon dioxide (CO2) has been extensively studied as a potential technology to mitigate atmospheric concentration of CO2. Multiple international research & development efforts, large-scale demonstration and commercial projects are helping advance the technology. One of the critical areas of active investigation is prediction of long-term CO2 storage security and risks. A quantitative methodology for predicting a storage site's long-term performance is critical for making key decisions necessary for successful deployment of commercial scale projects where projects will require quantitative assessments of potential long-term liabilities. These predictions are challenging given that they require simulating CO2 and in-situ fluid movements as well as interactions through the primary storage reservoir, potential leakage pathways (such as wellbores, faults, etc.) and shallow resources such as groundwater aquifers. They need to take into account the inherent variability and uncertainties at geologic sites. This talk will provide an overview of an approach based on integrated assessment modeling (IAM) to predict long-term performance of a geologic storage site including, storage reservoir, potential leakage pathways and shallow groundwater aquifers. The approach utilizes reduced order models (ROMs) to capture the complex physical/chemical interactions resulting due to CO2 movement and interactions but are computationally extremely efficient. Applicability of the approach will be demonstrated through examples that are focused on key storage security questions such as what is the probability of leakage of CO2 from a storage reservoir? how does storage security vary for different geologic environments and operational conditions? how site parameter variability and uncertainties affect storage security, etc.

  17. Stimulation of ribosomal RNA gene promoter by transcription factor Sp1 involves active DNA demethylation by Gadd45-NER pathway.

    Science.gov (United States)

    Rajput, Pallavi; Pandey, Vijaya; Kumar, Vijay

    2016-08-01

    The well-studied Pol II transcription factor Sp1 has not been investigated for its regulatory role in rDNA transcription. Here, we show that Sp1 bound to specific sites on rDNA and localized into the nucleoli during the G1 phase of cell cycle to activate rDNA transcription. It facilitated the recruitment of Pol I pre-initiation complex and impeded the binding of nucleolar remodeling complex (NoRC) to rDNA resulting in the formation of euchromatin active state. More importantly, Sp1 also orchestrated the site-specific binding of Gadd45a-nucleotide excision repair (NER) complex resulting in active demethylation and transcriptional activation of rDNA. Interestingly, knockdown of Sp1 impaired rDNA transcription due to reduced engagement of the Gadd45a-NER complex and hypermethylation of rDNA. Thus, the present study unveils a novel role of Sp1 in rDNA transcription involving promoter demethylation. Copyright © 2016 Elsevier B.V. All rights reserved.

  18. Storage of vacuum-packaged smoked bologna sausage prepared from Nile tilapia

    Directory of Open Access Journals (Sweden)

    Dayse Aline Ferreira Silva Bartolomeu

    2014-02-01

    Full Text Available Changes in smoked bologna sausage manufactured with Niletilapia (Oreochromis niloticus, and wheat fibers in refrigerated storage (6 ± 2°C during 30 days were evaluated. Minced fish (MF obtained from waste (parings from the filleting fish operations of Nile tilapia (Oreochromis niloticus was used as raw material. In this experiment, were determined Staphylococcus count, the detection of Salmonella sp. (day 0, psychrotrophic count, total and fecal coliforms at45°C, the acceptance sensory test (days 0 and 30, water activity, instrumental color, pH and lipid oxidation analysis (Thiobarbituric acid reactive substances - TBARS days 0, 5, 10, 15, 20, 25 and 30 of storage. Lipid oxidation (TBARS and water activity provided significant differences among storage days. However it was concluded that the bologna sausage remained stable and with acceptable quality for 30 days of storage may be a new alternative to adding value to fish products, because the researched microorganisms had a low count, changes in pH were not significant and sensory test indicated good acceptance of the product during the 30 days of storage.

  19. First report of Anisakis sp. in Epinephelus sp. in East Indonesia

    OpenAIRE

    Annytha Ina Rohi Detha; Diana Agustiani Wuri; Julianty Almet; Yuni Riwu; Christin Melky

    2018-01-01

    Objective: The present research was conducted to identify the prevalence of Anisakis sp. as fish-borne zoonoses in Epinephelus sp. in territorial waters of East Nusa Tenggara, Indonesia. Materials and methods: A total of 50 fish (Epinephelus sp.) were collected from Kupang Fish Market in East Nusa Tenggara. Identification of Anisakis sp. was performed based on morphological observations considering shape of ventriculus, boring tooth, and mucron using binocular microscope. Results: Prev...

  20. Sheet GT3-2. General approach of life phases on a long term for uranium mining residues storages and comparison with other storages

    International Nuclear Information System (INIS)

    2009-01-01

    This document aims at specifying the short term, middle term and long term boundaries for a sustainable management and rehabilitated ancient uranium mining sites and of uranium mining residue storage sites. It presents a general overview of site evolution in time, and then, more precisely, the different functions (rehabilitation management, corrective actions, control and monitoring, and so on) and equipment (confinement works, measurement system) at stake in the management of these sites and the control of their impacts. Functions and equipment implemented on such a site, as well as time scales corresponding to different approaches are compared with those of other types of storage. The peculiarity of ancient uranium mining sites and its implications in terms of management on a long term are discussed

  1. Prolonged storage of packed red blood cells for blood transfusion.

    Science.gov (United States)

    Martí-Carvajal, Arturo J; Simancas-Racines, Daniel; Peña-González, Barbra S

    2015-07-14

    A blood transfusion is an acute intervention, used to address life- and health-threatening conditions on a short-term basis. Packed red blood cells are most often used for blood transfusion. Sometimes blood is transfused after prolonged storage but there is continuing debate as to whether transfusion of 'older' blood is as beneficial as transfusion of 'fresher' blood. To assess the clinical benefits and harms of prolonged storage of packed red blood cells, in comparison with fresh, on recipients of blood transfusion. We ran the search on 1st May 2014. We searched the Cochrane Injuries Group Specialized Register, Cochrane Central Register of Controlled Trials (CENTRAL, The Cochrane Library), MEDLINE (OvidSP), Embase (OvidSP), CINAHL (EBSCO Host) and two other databases. We also searched clinical trials registers and screened reference lists of the retrieved publications and reviews. We updated this search in June 2015 but these results have not yet been incorporated. Randomised clinical trials including participants assessed as requiring red blood cell transfusion were eligible for inclusion. Prolonged storage was defined as red blood cells stored for ≥ 21 days in a blood bank. We did not apply limits regarding the duration of follow-up, or country where the study took place. We excluded trials where patients received a combination of short- and long-stored blood products, and also trials without a clear definition of prolonged storage. We independently performed study selection, risk of bias assessment and data extraction by at least two review authors. The major outcomes were death from any cause, transfusion-related acute lung injury, and adverse events. We estimated relative risk for dichotomous outcomes. We measured statistical heterogeneity using I(2). We used a random-effects model to synthesise the findings. We identified three randomised clinical trials, involving a total of 120 participants, comparing packed red blood cells with ≥ 21 days storage

  2. Evaluation of ZFS as an efficient WLCG storage backend

    Science.gov (United States)

    Ebert, M.; Washbrook, A.

    2017-10-01

    A ZFS based software raid system was tested for performance against a hardware raid system providing storage based on the traditional Linux file systems XFS and EXT4. These tests were done for a healthy raid array as well as for a degraded raid array and during the rebuild of a raid array. It was found that ZFS performs better in almost all test scenarios. In addition, distinct features of ZFS were tested for WLCG data storage use, like compression and higher raid levels with triple redundancy information. The long term reliability was observed after converting all production storage servers at the Edinburgh WLCG Tier-2 site to ZFS, resulting in about 1.2PB of ZFS based storage at this site.

  3. The simplified spherical harmonics (SP{sub L}) methodology with space and moment decomposition in parallel environments

    Energy Technology Data Exchange (ETDEWEB)

    Gianluca, Longoni; Alireza, Haghighat [Florida University, Nuclear and Radiological Engineering Department, Gainesville, FL (United States)

    2003-07-01

    In recent years, the SP{sub L} (simplified spherical harmonics) equations have received renewed interest for the simulation of nuclear systems. We have derived the SP{sub L} equations starting from the even-parity form of the S{sub N} equations. The SP{sub L} equations form a system of (L+1)/2 second order partial differential equations that can be solved with standard iterative techniques such as the Conjugate Gradient (CG). We discretized the SP{sub L} equations with the finite-volume approach in a 3-D Cartesian space. We developed a new 3-D general code, Pensp{sub L} (Parallel Environment Neutral-particle SP{sub L}). Pensp{sub L} solves both fixed source and criticality eigenvalue problems. In order to optimize the memory management, we implemented a Compressed Diagonal Storage (CDS) to store the SP{sub L} matrices. Pensp{sub L} includes parallel algorithms for space and moment domain decomposition. The computational load is distributed on different processors, using a mapping function, which maps the 3-D Cartesian space and moments onto processors. The code is written in Fortran 90 using the Message Passing Interface (MPI) libraries for the parallel implementation of the algorithm. The code has been tested on the Pcpen cluster and the parallel performance has been assessed in terms of speed-up and parallel efficiency. (author)

  4. Wayne Interim Storage Site environmental report for calendar year 1992, 868 Black Oak Ridge Road, Wayne, New Jersey

    International Nuclear Information System (INIS)

    1993-05-01

    This report describes the environmental surveillance program at the Wayne Interim Storage Site (WISS) and provides the results for 1992. The fenced, site, 32 km (20 mi) northwest of Newark, New Jersey, was used between 1948 and 1971 for commercial processing of monazite sand to separate natural radioisotopes - predominantly thorium. Environmental surveillance of WISS began in 1984 in accordance with Department of Energy (DOE) Order 5400.1 when Congress added the site to DOE's Formerly Utilized Sites Remedial Action Program (FUSRAP). The environmental surveillance program at WISS includes sampling networks for radon and thoron in air; external gamma radiation exposure; radium-226, radium-228, thorium-230, thorium-232, total uranium, and several chemicals in surface water and sediment; and total uranium, radium-226, radium-228, thorium-230, thorium-232, and organic and inorganic chemicals in groundwater. Monitoring results are compared with applicable Environmental Protection Agency (EPA) and state standards, DOE derived concentration guides (DCGs), dose limits, and other DOE requirements. This monitoring program assists in fulfilling the DOE policy of measuring and monitoring effluents from DOE activities and calculating hypothetical doses. Results for environmental surveillance in 1992 show that the concentrations of all radioactive and most chemical contaminants were below applicable standards

  5. Study for the selection of a supplementary spent fuel storage facility for KANUPP

    International Nuclear Information System (INIS)

    Ahmed, W.; Iqbal, M.J.; Arshad, M.

    1999-01-01

    Steps taken for construction of the spent fuel facility of Karachi Nuclear Power Plant (KANUPP) are the following: choice of conceptual design and site selection; preliminary design and preparation of Preliminary Safety Analysis Report (PSAR); Construction of the facility and preparation of PSAR; testing/commissioning and loading of the storage facility. Characterisation of the spent fuel is essential for design of the storage facility. After comparison of various storage types, it seems that construction of dry storage facility based on concrete canisters at KANUPP site is a suitable option to enhance the storage capacity

  6. Possible use of dual purpose dry storage casks for transportation and future storage of spent nuclear fuel from IRT-Sofia

    International Nuclear Information System (INIS)

    Manev, L.; Baltiyski, M.

    2003-01-01

    Objectives: The main objective of the present paper is related to one of the priority goals stipulated in Bulgarian Governmental Decision No.332 from May 17, 1999 - removal of SNF from IRT-Sofia site and its exporting for reprocessing and/or for temporary storage at Kozloduy NPP site. The variant of using dual purpose dry storage casks for transportation and future temporary storage of SNF from IRT-Sofia aims to find out a reasonable alternative of the existing till now variant for temporary SNF storage under water in the existing Kozloduy NPP Spent Fuel Storage Facility until its export for reprocessing. Results: Based on the given data for the condition of 73 Spent Nuclear Fuel Assemblies (SNFA) stored in the storage pool and technical data as well as data for available equipment and IRT-Sofia layout the following framework are specified: draft technical features of dual purpose dry storage casks and their overall dimensions; the suitability of the available equipment for safety and reliable performance of transportation and handling operations of assemblies from storage pool to dual purpose dry storage casks; the necessity of new equipment for performance of the above mentioned operations; Assemblies' transportation and handling operations are described; requirements to and conditions for future safety and reliable storage of SNFA loaded casks are determined. When selecting the technical solutions for safety assurance during performance of site handling operations of IRT-Sofia and for description of the exemplary casks the Effective Bulgarian Regulations are considered. The experience of other countries in performance of transfer and transportation of SNFA from such types of research reactors is taken into account. Also, Kozloduy NPP experience in SNF handling operations is taken into account. Conclusions: The Decision of Council of Minister for refurbishment of research reactor into a low power one and its future utilization for experimental and training

  7. Site 300 SPCC Plan

    Energy Technology Data Exchange (ETDEWEB)

    Griffin, D. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

    2016-11-23

    This Spill Prevention, Control, and Countermeasure (SPCC) Plan describes the measures that are taken at Lawrence Livermore National Laboratory’s (LLNL) Experimental Test Site (Site 300) near Tracy, California, to prevent, control, and handle potential spills from aboveground containers that can contain 55 gallons or more of oil. This SPCC Plan complies with the Oil Pollution Prevention regulation in Title 40 of the Code of Federal Regulations, Part 112 (40 CFR 112) and with 40 CFR 761.65(b) and (c), which regulates the temporary storage of polychlorinated biphenyls (PCBs). This Plan has also been prepared in accordance with Division 20, Chapter 6.67 of the California Health and Safety Code (HSC 6.67) requirements for oil pollution prevention (referred to as the Aboveground Petroleum Storage Act [APSA]), and the United States Department of Energy (DOE) Order No. 436.1. This SPCC Plan establishes procedures, methods, equipment, and other requirements to prevent the discharge of oil into or upon the navigable waters of the United States or adjoining shorelines for aboveground oil storage and use at Site 300. This SPCC Plan has been prepared for the entire Site 300 facility and replaces the three previous plans prepared for Site 300: LLNL SPCC for Electrical Substations Near Buildings 846 and 865 (LLNL 2015), LLNL SPCC for Building 883 (LLNL 2015), and LLNL SPCC for Building 801 (LLNL 2014).

  8. Nanostructured porous graphene and its composites for energy storage applications

    Science.gov (United States)

    Ramos Ferrer, Pablo; Mace, Annsley; Thomas, Samantha N.; Jeon, Ju-Won

    2017-10-01

    Graphene, 2D atomic-layer of sp2 carbon, has attracted a great deal of interest for use in solar cells, LEDs, electronic skin, touchscreens, energy storage devices, and microelectronics. This is due to excellent properties of graphene, such as a high theoretical surface area, electrical conductivity, and mechanical strength. The fundamental structure of graphene is also manipulatable, allowing for the formation of an even more extraordinary material, porous graphene. Porous graphene structures can be categorized as microporous, mesoporous, or macroporous depending on the pore size, all with their own unique advantages. These characteristics of graphene, which are further explained in this paper, may be the key to greatly improving a wide range of applications in energy storage systems.

  9. Area 5 Radioactive Waste Management Site Safety Assessment Document

    International Nuclear Information System (INIS)

    Horton, K.K.; Kendall, E.W.; Brown, J.J.

    1980-02-01

    The Area 5 Radioactive Waste Management Safety Assessment Document evaluates site characteristics, facilities and operating practices which contribute to the safe handling and storage/disposal of radioactive wastes at the Nevada Test Site. Physical geography, cultural factors, climate and meteorology, geology, hydrology (with emphasis on radionuclide migration), ecology, natural phenomena, and natural resources are discussed and determined to be suitable for effective containment of radionuclides. Also considered, as a separate section, are facilities and operating practices such as monitoring; storage/disposal criteria; site maintenance, equipment, and support; transportation and waste handling; and others which are adequate for the safe handling and storage/disposal of radioactive wastes. In conclusion, the Area 5 Radioactive Waste Management Site is suitable for radioactive waste handling and storage/disposal for a maximum of twenty more years at the present rate of utilization

  10. Installation restoration program site investigation. Gulfport Field Training Site, Mississippi Air National Guard Gulfport-Biloxi Regional Airport Gulfport, Mississippi. Volume 2. Final report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1992-12-01

    Site Investigation Report, Volume: 2. A Site Investigation was performed at 3 sites at the Combat Readiness Training Center, Gulfport-Bolixi. The 3 sites investigated are the: Former Fire Training Area (Site 1), the Former JP-4 Bulk Storage Area, Mill Road (Site 2), and the Motor Pool Above-Ground Diesel Fuel Storage Tank Area (Site 3). The findings of this investigation recommended further investigation at the Fire Training Area and the JP-4 Bulk Storage Tank. At Site 3 the levels of contamination did not represent a risk to human health or the environment; therefore, no further action was recommended. Volume two of this report consisted of the following Appendixes: Site Photographs (A), Well Inventory (B), Boring Logs (C), CSL Technical Memorandum (D), Data Review and Validation (E), GPS Memorandum (F), Level C Analytical Data Summary Tables (G), Slug Test (H), Special-Status Species (I), and Representative Species of Less Mobile Fish and Wildlife (J).

  11. Sp1 transcriptional activity is up-regulated by phosphatase 2A in dividing T lymphocytes.

    Science.gov (United States)

    Lacroix, Isabelle; Lipcey, Carol; Imbert, Jean; Kahn-Perlès, Brigitte

    2002-03-15

    We have followed Sp1 expression in primary human T lymphocytes induced, via CD2 plus CD28 costimulation, to sustained proliferation and subsequent return to quiescence. Binding of Sp1 to wheat germ agglutinin lectin was not modified following activation, indicating that the overall glycosylation of the protein was unchanged. Sp1 underwent, instead, a major dephosphorylation that correlated with cyclin A expression and, thus, with cell cycle progression. A similar change was observed in T cells that re-entered cell cycle following secondary interleukin-2 stimulation, as well as in serum-induced proliferating NIH/3T3 fibroblasts. Phosphatase 2A (PP2A) appears involved because 1) treatment of dividing cells with okadaic acid or cantharidin inhibited Sp1 dephosphorylation and 2) PP2A dephosphorylated Sp1 in vitro and strongly interacted with Sp1 in vivo. Sp1 dephosphorylation is likely to increase its transcriptional activity because PP2A overexpression potentiated Sp1 site-driven chloramphenicol acetyltransferase expression in dividing Kit225 T cells and okadaic acid reversed this effect. This increase might be mediated by a stronger affinity of dephosphorylated Sp1 for DNA, as illustrated by the reduced DNA occupancy by hyperphosphorylated Sp factors from cantharidin- or nocodazole-treated cells. Finally, Sp1 dephosphorylation appears to occur throughout cell cycle except for mitosis, a likely common feature to all cycling cells.

  12. Assessment of Washing with Antioxidant on the Oxidative Stability of Fatty Fish Mince during Processing and Storage

    DEFF Research Database (Denmark)

    Eymard, Sylvie; Jacobsen, Charlotte; Baron, Caroline

    2010-01-01

    Fatty fish have been recognized as potential raw material for the production of surimi; however, they can easily oxidize. The ability of antioxidants added in the washing water to reduce oxidation during the washing and subsequent storage needs to be evaluated. Horse mackerel (Trachurus trachurus...... performed. Results indicated that the antioxidants were accumulated differently, but all antioxidants tested were able to prevent lipid oxidation in fatty fish mince during washing and subsequent storage. The ranking in terms of oxidative stability of the washed minces was CA = PG > SP > W. The antioxidants......) mince was washed three times with 3 volumes of cold water (W) or the antioxidant solutions caffeic acid (CA) or propyl gallate (PG), at concentrations of 100 mg/kg, or spermine (SP), at a concentration of 400 mg/kg. Accumulation of antioxidant in the mince at each washing step was evaluated...

  13. Acceleration and parallelization calculation of EFEN-SP_3 method

    International Nuclear Information System (INIS)

    Yang Wen; Zheng Youqi; Wu Hongchun; Cao Liangzhi; Li Yunzhao

    2013-01-01

    Due to the fact that the exponential function expansion nodal-SP_3 (EFEN-SP_3) method needs further improvement in computational efficiency to routinely carry out PWR whole core pin-by-pin calculation, the coarse mesh acceleration and spatial parallelization were investigated in this paper. The coarse mesh acceleration was built by considering discontinuity factor on each coarse mesh interface and preserving neutron balance within each coarse mesh in space, angle and energy. The spatial parallelization based on MPI was implemented by guaranteeing load balancing and minimizing communications cost to fully take advantage of the modern computing and storage abilities. Numerical results based on a commercial nuclear power reactor demonstrate an speedup ratio of about 40 for the coarse mesh acceleration and a parallel efficiency of higher than 60% with 40 CPUs for the spatial parallelization. With these two improvements, the EFEN code can complete a PWR whole core pin-by-pin calculation with 289 × 289 × 218 meshes and 4 energy groups within 100 s by using 48 CPUs (2.40 GHz frequency). (authors)

  14. Incidence of fungus and physiological quality of seeds of Jatropha curcas L. after cryogenic storage

    Directory of Open Access Journals (Sweden)

    Míriam Goldfarb

    2010-03-01

    Full Text Available The objective of this work was to evaluate the incidence of fungi in stored seeds of Jatropha curcas. The research was carried out at Cryogenic/UFCG, Sanity/UFPB and Cotton/Embrapa. The material for analysis showed an 8% water level, and 200 seeds were stored for treatment in cryogenic containers with nitrogen in the vapor and liquid phases. Four periods of crioconservation (0, 30, 60 and 90 days, were employed. After each period, the seeds were tested for sanity (Blotter test and germination. Superficial disinfestation, was carried out and seeds were distributed in Petri dishes, for incubation at 25 ± 2ºC, over a period of 7 days. The evaluation of the incidence of fungi was carried out in a stereoscopic microscope with observation of fungal structures, and values were expressed as percentages of seeds with fungus. The statistical experiment was completely randomized with temperature x days of storage. Analysis of variance was conducted and the means were compared by Tukey’s test at 5%. After 30 days of cryogenic storage, a greater incidence of Aspergillus sp., Cladosporium sp. and Fusarium sp. was detected. It was concluded that crioconservation at cryogenic temperatures did not reduce the incidence of fungus on Jatropha curcas seeds. The physiological quality was preserved during the cryoconservation.

  15. Inspection and Analysis of Aluminum Storage Racks in Spent Fuel Storage Basins

    International Nuclear Information System (INIS)

    Howell, J.P.; Nelson, D.Z.

    1998-07-01

    Aluminum-clad spent nuclear fuel is stored in water filled basins at the Savannah River Site awaiting processing or other disposition. After more than 35 years of service underwater, the aluminum storage racks that position the fuel bundles in the basin were replaced. During the removal of the racks from the basin, a failure occurred in one of the racks and the Savannah River Technology Center was asked to investigate. This paper presents results of the failure analysis and provides a discussion of the effects of corrosion on the structural integrity of the storage racks

  16. Prediction Primary Available Blend Biodiesel of Waste Oil from Aurantiochytrium sp. for General Diesel Engines

    Directory of Open Access Journals (Sweden)

    Shu-Yao Tsai

    2018-01-01

    Full Text Available Chemical and enzyme transesterification were compared by discussing preliminary transesterification of waste oil of Aurantiochytrium sp., which was then used in transesterification for the primary available blend biodiesel for a general diesel engine in this study. We made progress on the winterized characteristics of the waste oil’s biodiesel of Aurantiochytrium sp. and its biodiesel, which included the reactivity parameters and properties. This approach led to the development of a novel idea for the evaluation of kinetic parameters of winterization, along with obtaining the suitable operation and storage conditions of biodiesel. Therefore, the waste oil of Aurantiochytrium sp. could be developed for biodiesel production and successfully made into a suitable blend diesel. Overall, we acquired the best condition of mixtures and the highly mixed rate of petrodiesel: biodiesel = 80 : 20 (activation energy of winterization 21.32 kJ/mol; onset temperature of winterization -4.15 °C; heat of combustion 43.15 MJ/kg; kinematic viscosity 3.51 mm2/s; flash point 67.5 °C, which was an appropriate blend biodiesel from the waste oil’s biodiesel of Aurantiochytrium sp.

  17. Status of US storage efforts

    International Nuclear Information System (INIS)

    Leasburg, R.H.

    1984-01-01

    Tasks involved in the implementation of the Nuclear Waste Policy Act are discussed. The need for speedy action on applications to deal with spent fuel storage problems is stressed. The problems faced by the Virginia Electric and Power Company, where full core discharge capability at the 1600-megawatt Surry power station is expected to be reached in early 1986, are reviewed. It is pointed out that although the Nuclear Waste Policy Act does not apply in this case, the problems illustrate the situation that may be faced after the Act is implemented. Problems involved in intro-utility transhipments and dry cask storage of spent fuel from Surry, including transportation ordinances at state and local levels and approval for the use of dry casks for storage, are reported. The suggestion that dry casks be used for interim storage and eventual transport to monitored retrievable storage facilities or permanent storage sites is considered. It is pointed out that data from a proposed 3-utility demonstration program of dry cask storage of consolidated fuels and the storage of fuels in air should give information applicable to the timely implementation of the Nuclear Waste Policy Act

  18. Colonie Interim Storage Site annual environmental report for calendar year 1991, Colonie, New York

    International Nuclear Information System (INIS)

    1992-09-01

    This document describes the environmental monitoring program at the Colonie Interim Storage Site (CISS) and surrounding area, implementation of the program, and monitoring results for 1991. Environmental monitoring at CISS began in 1984 when Congress added the site to the US Department of Energy's Formerly Utilized Sites Remedial Action Program. CISS property and surrounding areas were radioactively contaminated by operations conducted by National Lead Industries, which manufactured various components from uranium and thorium from 1958 to 1984. The environmental monitoring program at CISS includes sampling networks for external gamma radiation exposure and for radium-226, thorium-232, and total uranium concentrations in surface water, sediment, and groundwater. Additionally, several nonradiological parameters are measured in groundwater. In 1992 the program will also include sampling networks for radioactive and chemical contaminants in stormwater to meet permit application requirements under the Clean Water Act. Monitoring results are compared with applicable Environmental Protection Agency (EPA) standards, DOE derived concentration guides (DCGs), dose limits, and other requirements in DOE.orders. Environmental standards are established to protect public health and the environment. Results of environmental monitoring during 1991 indicate that average concentrations of radioactive contaminants of concern were well below applicable standards and DCGS. Concentrations of some chemical contaminants in groundwater were above-the New York State Department of Environmental Conservation (Class GA) and EPA guidelines for drinking water. The potential annual radiation exposure (excluding background) calculated for a hypothetical maximally exposed individual is 0.23 mrem (milliroentgen equivalent man), which is less than an individual would receive while traveling in an airplane at 12,000 meters (39,000 feet) for one hour

  19. Integral Monitored Retrievable Storage (MRS) Facility conceptual design report

    International Nuclear Information System (INIS)

    1985-09-01

    This document, Volume 5 Book 7, contains cost estimate information for a monitored retrievable storage (MRS) facility. Cost estimates are for onsite improvements, waste storage, and offsite improvements for the Clinch River Site

  20. Cadmium biosorption by Streptomyces sp. F4 isolated from former uranium mine.

    Science.gov (United States)

    Siñeriz, Manuel Louis; Kothe, Erika; Abate, Carlos Mauricio

    2009-09-01

    46 actinomycetes were isolated from two polluted sites and one unpolluted site. One strain, F4, was selected through primary qualitative screening assays because of its cadmium resistance, and physiologically and taxonomically characterized. F4 was able to grow at 7.5% NaCl and 100 microg/ml lysozyme and at a pH between 6 and 10. 16S rDNA sequence analysis showed that F4 was closely related to Streptomyces tendae. Growth of Streptomyces sp. F4 on culture medium with 8 mg/l Cd(2+) for 8 days showed 80% inhibition. Maximum specific biosorption was 41.7 mg Cd(2+)/g dry weight after 7 days of growth and highest Cd(2+ )concentration was found in the cell wall (41.2%). The exopolysaccharide layer only contained 7.4%, whereas 39.4% of Cd(2+) was found in the cytosolic fraction. Twelve % was found in the ribosomes and membrane fraction. This was verified with TEM, showing Streptomyces sp. F4 cytoplasm with dark granulate appearance. This study could present the potential capacity of Streptomyces sp. F4 for Cd(2+) bioremediation. Copyright 2009 WILEY-VCH Verlag GmbH & Co. KGaA, Weinheim.

  1. Effective cultivation of microalgae for biofuel production: a pilot-scale evaluation of a novel oleaginous microalga Graesiella sp. WBG-1.

    Science.gov (United States)

    Wen, Xiaobin; Du, Kui; Wang, Zhongjie; Peng, Xinan; Luo, Liming; Tao, Huanping; Xu, Yan; Zhang, Dan; Geng, Yahong; Li, Yeguang

    2016-01-01

    Commercial production of microalgal biodiesel is not yet economically viable, largely because of low storage lipid yield in microalgae mass cultivation. Selection of lipid-rich microalgae, thus, becomes one of the key research topics for microalgal biodiesel production. However, the laboratory screening protocols alone cannot predict the ability of the strains to dominate and perform in outdoor ponds. Comprehensive assessment of microalgae species should be performed not only under the laboratory conditions, but also in the fields. Laboratory investigations using a bubbled column photobioreactor indicated the microalga Graesiella sp. WBG-1 to be the most productive species among the 63 Chlorophyta strains. In a 10 L reactor, mimicking the industrial circular pond, Graesiella sp. WBG-1 produced 12.03 g biomass m(-2) day(-1) and 5.44 g lipids (45.23 % DW) m(-2) day(-1) under 15 mol m(-2) day(-1) artificial light irradiations. The lipid content decreased to ~34 % DW when the microalga was cultured in 30 L tank PBR under natural solar irradiations, but the decline of lipid content with scaling up was the minimum among the tested strains. Based on these results, the microalga was further tested for its lipid production and culture competitiveness using a pilot-scale raceway pond (200 m(2) illuminated area, culture volume 40,000 L). Consequently, Graesiella sp. WBG-1 maintained a high lipid content (33.4 % DW), of which ~90 % was storage TAGs. Results from the outdoor experiments indicated the nice adaptability of the Graesiella sp. WBG-1 to strong and fluctuating natural solar irradiance and temperature, and also demonstrated several other features, such as large cell size (easy for harvest and resistant to swallow by protozoa) and tolerance to high culture pH (helpful to CO2 fixation). Graesiella sp. WBG-1 was a promising strain capable of accumulating large amount of storage lipid under nature solar irradiance and temperature. The high lipid content

  2. IMPACT OF AMARANTH (AMARANTH SP. ON TECHNOLOGICAL QUALITY OF BAKERY PRODUCTS DURING FROZEN STORAGE

    Directory of Open Access Journals (Sweden)

    Tatiana Bojňanská

    2014-02-01

    Full Text Available Frozen baking semi-finished meals and dough bring to consumer daily fresh products with the added value from the point of view of comfort and storage, as well as fresh products of comparable quality with baking yeasts products. The aim of this study was to observe the impact of adding 30% of flour from amaranth to the wheat flour T 650 on the quality of immediately baked products stored one, three and six months in a freezer at the temperature of -18°. The overall quality of baked loaves from frozen dough was declining gradually depending on the length of storage in the freezing box, while the highest decline in quality was recorded after three and six months of storage. Specifically, after one month there was a decline in the loaf volume - the one of the most important indicators for bakery quality - by 10.5% and after three and six months by 26.3% in comparison to fresh loaves. The decline in bakery quality was caused mainly by decreasing activity of yeast cells which were damaged by crystals of ice, by the afterward loss of their ability to yeast and by gradual decrease of dough firmness.

  3. Interim Storage Facility decommissioning. Final report

    International Nuclear Information System (INIS)

    Johnson, R.P.; Speed, D.L.

    1985-01-01

    Decontamination and decommissioning of the Interim Storage Facility were completed. Activities included performing a detailed radiation survey of the facility, removing surface and imbedded contamination, excavating and removing the fuel storage cells, restoring the site to natural conditions, and shipping waste to Hanford, Washington, for burial. The project was accomplished on schedule and 30% under budget with no measurable exposure to decommissioning personnel

  4. The influence of small-mammal burrowing activity on water storage at the Hanford Site

    International Nuclear Information System (INIS)

    Landeen, D.S.

    1994-01-01

    This paper summarizes the activities that were conducted in support of the long-term surface barrier development program by Westinghouse Hanford Company to determine the degree that small-mammal burrow systems affect the loss or retention of water in the soils at the Hanford Site in Washington state. An animal intrusion lysimeter facility was constructed, consisting of two outer boxes buried at grade, which served as receptacles for six animal intrusion lysimeters. Small burrowing animals common the Hanford Site were introduced over a 3- to 4-month period. Supplemental precipitation was added monthly to three of the lysimeters with a rainfall simulator (rainulator). Information collected from the five tests indicated that (1) during summer months, water was lost in all the lysimeters, including the supplemental precipitation added with the rainulator; and (2) during winter months, all lysimeters gained water. The data indicate little difference in the amount of water stored between control and animal lysimeters. The overall water loss was attributed to surface evaporation, a process that occurred equally in control and treatment lysimeters. Other causes of water loss are a result of (1) constant soil turnover and subsequent drying, and (2) burrow ventilation effects. This suggests that burrow systems will not contribute to any significant water storage at depth and, in fact, may enhance the removal of water from the soil

  5. Penicillium araracuarense sp. nov., Penicillium elleniae sp. nov., Penicillium penarojense sp. nov., Penicillium vanderhammenii sp. nov. and Penicillium wotroi sp. nov., isolated from leaf litter.

    Science.gov (United States)

    Houbraken, Jos; López-Quintero, Carlos A; Frisvad, Jens C; Boekhout, Teun; Theelen, Bart; Franco-Molano, Ana Esperanza; Samson, Robert A

    2011-06-01

    Several species of the genus Penicillium were isolated during a survey of the mycobiota of leaf litter and soil in Colombian Amazon forest. Five species, Penicillium penarojense sp. nov. (type strain CBS 113178(T) = IBT 23262(T)), Penicillium wotroi sp. nov. (type strain CBS 118171(T) = IBT 23253(T)), Penicillium araracuarense sp. nov. (type strain CBS 113149(T) = IBT 23247(T)), Penicillium elleniae sp. nov. (type strain CBS 118135(T) = IBT 23229(T)) and Penicillium vanderhammenii sp. nov. (type strain CBS 126216(T) = IBT 23203(T)) are described here as novel species. Their taxonomic novelty was determined using a polyphasic approach, combining phenotypic, molecular (ITS and partial β-tubulin sequences) and extrolite data. Phylogenetic analyses showed that each novel species formed a unique clade for both loci analysed and that they were most closely related to Penicillium simplicissimum, Penicillium janthinellum, Penicillium daleae and Penicillium brasilianum. An overview of the phylogeny of this taxonomically difficult group is presented, and 33 species are accepted. Each of the five novel species had a unique extrolite profile of known and uncharacterized metabolites and various compounds, such as penicillic acid, andrastin A, pulvilloric acid, paxillin, paspaline and janthitrem, were commonly produced by these phylogenetically related species. The novel species had a high growth rate on agar media, but could be distinguished from each other by several macro- and microscopical characteristics.

  6. Effect of gamma-irradiation and refrigerated storage on mold growth and keeping quality of strawberry (Fragaria sp) cv 'Confitura'

    International Nuclear Information System (INIS)

    Hussain, P.R.; Meena, R.S.; Dar, M.A.; Wani, A.M.; Mir, M.A.; Shafi, F.

    2007-01-01

    Gamma-irradiation of fresh matured strawberries at 0.5-2.0 kGy and storage under ambient and refrigerated conditions was tested for delaying the mold appearance and extension of storage life. Radiation dose of 2.0 kGy was effective in extending the storage life of fresh strawberries by 2 days under ambient conditions. Samples irradiated at 1.5 and 2.0 kGy followed by refrigerated storage delayed the mold growth significantly (p≤0.05) and extended the storage life by 8 days. (author)

  7. Safety analysis of spent fuel transport and storage casks under extreme impact conditions

    International Nuclear Information System (INIS)

    Wolff, D.; Wieser, G.; Ballheimer, V.; Voelzke, H.; Droste, B.

    2005-01-01

    Full text: Worldwide the security of transport and storage of spent fuel with respect to terrorism threats is a matter of concern. In Germany a spent nuclear fuel management program was developed by the government including a new concept of dry on-site interim storage instead of centralized interim storage. In order to minimize transports of spent fuel casks between nuclear power plants, reprocessing plants and central storage facilities, the operators of NPPs have to erect and to use interim storage facilities for spent nuclear fuel on the site or in the vicinity of nuclear power plants. Up to now, 11 on-site interim storage buildings, one storage tunnel and 4 on-site interim storage areas (preliminary cask storage till the on-site interim storage building is completed) have been licensed at 12 nuclear power plant sites. Inside the interim storage buildings the casks are kept in upright position, whereas at the preliminary interim storage areas horizontal storage of the casks on concrete slabs is used and each cask is covered by concrete elements. Storage buildings and concrete elements are designed only for gamma and neutron radiation shielding reasons and as weather protection. Therefore the security of spent fuel inside a dual purpose transport and storage cask depends on the inherent safety of the cask itself. For nearly three decades BAM has been investigating cask safety under severe accident conditions like drop tests from more than 9 m onto different targets and without impact limiters as well as artificially damaged prototype casks. Since the terror attacks of 11 September 2001 the determination of casks' inherent safety also under extreme impact conditions due to terrorist attacks has been of our increasing interest. With respect to spent fuel storage one of the most critical scenarios of a terrorist attack for a cask is the centric impact of a dynamic load onto the lid-seal-system caused e.g. by direct aircraft crash or its engine as well as by a

  8. Environmental assessment: Solid waste retrieval complex, enhanced radioactive and mixed waste storage facility, infrastructure upgrades, and central waste support complex, Hanford Site, Richland, Washington

    International Nuclear Information System (INIS)

    1995-09-01

    The U.S. Department of Energy (DOE) needs to take action to: retrieve transuranic (TRU) waste because interim storage waste containers have exceeded their 20-year design life and could fail causing a radioactive release to the environment provide storage capacity for retrieved and newly generated TRU, Greater-than-Category 3 (GTC3), and mixed waste before treatment and/or shipment to the Waste Isolation Pilot Project (WIPP); and upgrade the infrastructure network in the 200 West Area to enhance operational efficiencies and reduce the cost of operating the Solid Waste Operations Complex. This proposed action would initiate the retrieval activities (Retrieval) from Trench 4C-T04 in the 200 West Area including the construction of support facilities necessary to carry out the retrieval operations. In addition, the proposed action includes the construction and operation of a facility (Enhanced Radioactive Mixed Waste Storage Facility) in the 200 West Area to store newly generated and the retrieved waste while it awaits shipment to a final disposal site. Also, Infrastructure Upgrades and a Central Waste Support Complex are necessary to support the Hanford Site's centralized waste management area in the 200 West Area. The proposed action also includes mitigation for the loss of priority shrub-steppe habitat resulting from construction. The estimated total cost of the proposed action is $66 million

  9. Measurement of residual CO2 saturation at a geological storage site using hydraulic tests

    Science.gov (United States)

    Rötting, T. S.; Martinez-Landa, L.; Carrera, J.; Russian, A.; Dentz, M.; Cubillo, B.

    2012-12-01

    Estimating long term capillary trapping of CO2 in aquifers remains a key challenge for CO2 storage. Zhang et al. (2011) proposed a combination of thermal, tracer, and hydraulic experiments to estimate the amount of CO2 trapped in the formation after a CO2 push and pull test. Of these three types of experiments, hydraulic tests are the simplest to perform and possibly the most informative. However, their potential has not yet been fully exploited. Here, a methodology is presented to interpret these tests and analyze which parameters can be estimated. Numerical and analytical solutions are used to simulate a continuous injection in a porous medium where residual CO2 has caused a reduction in hydraulic conductivity and an increase in storativity over a finite thickness (a few meters) skin around the injection well. The model results are interpreted using conventional pressure build-up and diagnostic plots (a plot of the drawdown s and the logarithmic derivative d s / d ln t of the drawdown as a function of time). The methodology is applied using the hydraulic parameters estimated for the Hontomin site (Northern Spain) where a Technology Demonstration Plant (TDP) for geological CO2 storage is planned to be set up. The reduction of hydraulic conductivity causes an increase in observed drawdowns, the increased storativity in the CO2 zone causes a delay in the drawdown curve with respect to the reference curve measured before CO2 injection. The duration (characteristic time) of these effects can be used to estimate the radius of the CO2 zone. The effects of reduced permeability and increased storativity are well separated from wellbore storage and natural formation responses, even if the CO2-brine interface is inclined (i.e. the CO2 forms a cone around the well). We find that both skin hydraulic conductivity and storativity (and thus residual CO2 saturation) can be obtained from the water injection test provided that water flow rate is carefully controlled and head build

  10. Thermal analyses of SRS Pu storage cans inside BNFL 3013 container

    International Nuclear Information System (INIS)

    Paul, P.K.

    1999-10-01

    Plutonium metal is stored at the Savannah River Site (SRS) using different storage can configurations. The temperatures at different locations in the storage configuration play an important role in designing and configuring different storage arrangements. The present work consists of calculating temperatures at different locations in two different storage configurations

  11. Assessment of spent WWER-440 fuel performance under long-term storage conditions

    Energy Technology Data Exchange (ETDEWEB)

    Kupca, L [VUJE Inc. (Slovakia)

    2012-07-01

    In the Slovak Republic are under operation 6 units (4 in the Jaslovske Bohunice site, and 2 in the Mochovce), 2 units are under construction in Mochovce site. All units are WWER-440 type. The fresh fuel is imported from the Russian Federation. The spent fuel assemblies are stored in wet conditions in Bohunice Interim Storage Spent Fuel Facility (SFIS). By 15 July 2008, there were 8413 assemblies in SFIS. The objectives are: 1) Wet AR storage of spent fuel from the NPP Bohunice and Mochovce: Surveillance of conditions for spent fuel storage in the at-reactor (AR) storage pools of both NPP's (characteristics of pool water, corrosion product data); Visual control of storage pool components; Evaluation of storage conditions with respect to long-term stability (corrosion of fuel cladding, structural materials); 2) Wet SFIS storage at Bohunice: Measurement of spent fuel conditions during the long-term wet storage, activity data in the storage casks and amount of crud; Surveillance program for SFIS structural materials.

  12. Hydrogen storage by physisorption on porous materials

    Energy Technology Data Exchange (ETDEWEB)

    Panella, B

    2006-09-13

    A great challenge for commercializing hydrogen powered vehicles is on-board hydrogen storage using economic and secure systems. A possible solution is hydrogen storage in light-weight solid materials. Here three principle storage mechanisms can be distinguished: i) absorption of hydrogen in metals ii) formation of compounds with ionic character, like complex hydrides and iii) physisorption (or physical adsorption) of hydrogen molecules on porous materials. Physical adsorption exhibits several advantages over chemical hydrogen storage as for example the complete reversibility and the fast kinetics. Two classes of porous materials were investigated for physical hydrogen storage, i.e. different carbon nanostructures and crystalline metal-organic frameworks possessing extremely high specific surface area. Hydrogen adsorption isotherms were measured using a Sieverts' apparatus both at room temperature and at 77 K at pressures up to the saturation regime. Additionally, the adsorption sites of hydrogen in these porous materials were identified using thermal desorption spectroscopy extended to very low temperatures (down to 20 K). Furthermore, the adsorbed hydrogen phase was studied in various materials using Raman spectroscopy at different pressures and temperatures. The results show that the maximum hydrogen storage capacity of porous materials correlates linearly with the specific surface area and is independent of structure and composition. In addition the pore structure of the adsorbent plays an important role for hydrogen storage since the adsorption sites for H2 could be assigned to pores possessing different dimensions. Accordingly it was shown that small pores are necessary to reach high storage capacities already at low pressures. This new understanding may help to tailor and optimize new porous materials for hydrogen storage. (orig.)

  13. Hydrogen storage by physisorption on porous materials

    Energy Technology Data Exchange (ETDEWEB)

    Panella, B.

    2006-09-13

    A great challenge for commercializing hydrogen powered vehicles is on-board hydrogen storage using economic and secure systems. A possible solution is hydrogen storage in light-weight solid materials. Here three principle storage mechanisms can be distinguished: i) absorption of hydrogen in metals ii) formation of compounds with ionic character, like complex hydrides and iii) physisorption (or physical adsorption) of hydrogen molecules on porous materials. Physical adsorption exhibits several advantages over chemical hydrogen storage as for example the complete reversibility and the fast kinetics. Two classes of porous materials were investigated for physical hydrogen storage, i.e. different carbon nanostructures and crystalline metal-organic frameworks possessing extremely high specific surface area. Hydrogen adsorption isotherms were measured using a Sieverts' apparatus both at room temperature and at 77 K at pressures up to the saturation regime. Additionally, the adsorption sites of hydrogen in these porous materials were identified using thermal desorption spectroscopy extended to very low temperatures (down to 20 K). Furthermore, the adsorbed hydrogen phase was studied in various materials using Raman spectroscopy at different pressures and temperatures. The results show that the maximum hydrogen storage capacity of porous materials correlates linearly with the specific surface area and is independent of structure and composition. In addition the pore structure of the adsorbent plays an important role for hydrogen storage since the adsorption sites for H2 could be assigned to pores possessing different dimensions. Accordingly it was shown that small pores are necessary to reach high storage capacities already at low pressures. This new understanding may help to tailor and optimize new porous materials for hydrogen storage. (orig.)

  14. Pollution Prevention, Waste Minimization and Material Recycling Successes Realized during Savannah River Site's K Area Materials Storage (KAMS) Project, W226

    International Nuclear Information System (INIS)

    Ellis, M.S.

    2001-01-01

    As DOE continues to forge ahead and re-evaluate post cold war missions, facilities that were constructed and operated for DOE/DOD over the past 50+ years are coming to the end of their useful life span. These various facilities throughout the country had served a very useful purpose in our nations history; however, their time of Cold War materials production has come to an end. With this looming finalization comes a decision as to how to remedy their existence: D and R the facilities and return to ''Greenfield''; or, retrofit the existing facilities to accommodate the newer missions of the DOE Complex. The 105-K Reactor Building located at the Savannah River Site in Aiken, South Carolina was retrofit on an accelerated project schedule for a new mission called K-Area Materials Storage (KAMS). Modifications to the former defense reactor's building and equipment will allow storage of Plutonium from the Rocky Flats Site in Colorado and other materials deemed necessary by the Department of Energy. Proper project planning and activity sequencing allowed the DOE and the Westinghouse Savannah River Company to realize savings from: the recycling and/or reuse of modified facility components; reduction and reclassification of waste; reduction in radiological area footprint (rollbacks)

  15. Soft-template hydrothermal systhesis of nanostructured Copper(II) Tungstate cubes for Electrochemical Charge Storage Application

    International Nuclear Information System (INIS)

    Wei, Chao; Huang, Ying; Zhang, Xin; Chen, Xuefang; Yan, Jing

    2016-01-01

    Highlights: • Soft-template hydrothermal method is firstly respoted for CuWO4 samples. • Nano-size distribution of CuWO4 is mainly ascribed to the soft-template of P123. • Excellent performance is due to Low surface energy, blunt edges and active sites. - Abstract: In this work, the soft-template hydrothermal method is firstly applied to synthesize nanocrystal CuWO 4 cubes for the electrode materials in in electrochemical charge storage application. The structures and morphologies of as-obtained materials are characterized via X-ray diffraction (XRD), Fourier-transform infrared spectroscopy (FT-IR), Scanning electron microscopy (SEM), Transmission electron microscopy (TEM) and X-ray photoelectron spectroscopy (XPS). The effects of the soft-template (P123) and surfactant (Hexamethylenetetramine) also are verified by the electrochemistry test including CV, GCD, EIS. As a result, the CuWO 4 -PH (synthesis with the assistance of P123 and Hexamethylenetetramine) shows a excellent specific capacitance (C sp ) of 302.40 mAh g −1 at the current density of 1 A g −1 and a good rate capability (60.7% retension rate of original Csp even at 10 A g −1 ), as well as cycle life (82.1% retention rate of original C sp after 2000 cycles). These results reveal that our obtained CuWO 4 -PH could be a promissing electrode material.

  16. Energy Storage Management for Grid Operation Purposes

    OpenAIRE

    Ricardo Santos; Ricardo André; Ricardo Bessa; Clara Gouveia; António Araújo; Filipe Guerra; José Damásio; Guillermo Bravo; Jean Sumaili

    2016-01-01

    The Horizon 2020 Storage ENabled SustaInable energy for BuiLdings and communitiEs (SENSIBLE) project is currently looking at the integration of small-scale storage technologies in buildings and distribution networks. In the demonstration site of the SENSIBLE project, EDP has already installed an experimental storage system supplying a university campus in MV. It was mainly designed to increase service quality to the university by providing backup power in the event of MV grid failure, but it ...

  17. Radioactive wastes storage and disposal. Chapter 8

    International Nuclear Information System (INIS)

    2002-01-01

    The Chapter 8 is essentially dedicated to radioactive waste management - storage and disposal. The management safety is being provided due to packages and facilities of waste disposal and storage. It is noted that at selection of sites for waste disposal it is necessary account rock properties and ways of the wastes delivery pathways

  18. SDS-PAGE analysis of high molecular weight glutenin subunits in SP3 from spaceflight carried wheat

    International Nuclear Information System (INIS)

    Zhang Su'na; Lv Jinyin

    2009-01-01

    The compositions of high molecular weight glutenin subunits (HMW-GS) of the third generation (SP 3 ) of two wheat varieties spaceflight carried were analyzed by SDS-PAGE. The quality score of Glu-1 of each site was calculated according to the quality rating system. The results showed that the space flight carried could result in a higher frequency of HMW-GS gene mutation. The variance frequency of HMW-GS in SP 3 of Shaan253 and Xinong1043 were 27.08% and 27.45%, and the quality score in SP 3 of Shaan253 and Xinong1043 were 7 and 6, respectively. Shaan253 SP 3 generation mutants were considered as high-quality wheat. (authors)

  19. Corrective Action Investigation Plan for Corrective Action Unit 214: Bunkers and Storage Areas Nevada Test Site, Nevada: Revision 0, Including Record of Technical Change No. 1 and No. 2

    Energy Technology Data Exchange (ETDEWEB)

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

    2003-05-16

    This Corrective Action Investigation Plan contains the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office's approach to collect the data necessary to evaluate corrective action alternatives appropriate for the closure of Corrective Action Unit (CAU) 214 under the Federal Facility Agreement and Consent Order. Located in Areas 5, 11, and 25 of the Nevada Test Site, CAU 214 consists of nine Corrective Action Sites (CASs): 05-99-01, Fallout Shelters; 11-22-03, Drum; 25-99-12, Fly Ash Storage; 25-23-01, Contaminated Materials; 25-23-19, Radioactive Material Storage; 25-99-18, Storage Area; 25-34-03, Motor Dr/Gr Assembly (Bunker); 25-34-04, Motor Dr/Gr Assembly (Bunker); and 25-34-05, Motor Dr/Gr Assembly (Bunker). These sites are being investigated because existing information on the nature and extent of potential contamination is insufficient to evaluate and recommend corrective action alternatives (CAAs). The suspected contaminants and critical analyte s for CAU 214 include oil (total petroleum hydrocarbons-diesel-range organics [TPH-DRO], polychlorinated biphenyls [PCBs]), pesticides (chlordane, heptachlor, 4,4-DDT), barium, cadmium, chronium, lubricants (TPH-DRO, TPH-gasoline-range organics [GRO]), and fly ash (arsenic). The land-use zones where CAU 214 CASs are located dictate that future land uses will be limited to nonresidential (i.e., industrial) activities. The results of this field investigation will support a defensible evaluation of viable corrective action alternatives that will be presented in the corrective action decision document.

  20. Cyclic high temperature heat storage using borehole heat exchangers

    Science.gov (United States)

    Boockmeyer, Anke; Delfs, Jens-Olaf; Bauer, Sebastian

    2016-04-01

    The transition of the German energy supply towards mainly renewable energy sources like wind or solar power, termed "Energiewende", makes energy storage a requirement in order to compensate their fluctuating production and to ensure a reliable energy and power supply. One option is to store heat in the subsurface using borehole heat exchangers (BHEs). Efficiency of thermal storage is increasing with increasing temperatures, as heat at high temperatures is more easily injected and extracted than at temperatures at ambient levels. This work aims at quantifying achievable storage capacities, storage cycle times, injection and extraction rates as well as thermal and hydraulic effects induced in the subsurface for a BHE storage site in the shallow subsurface. To achieve these aims, simulation of these highly dynamic storage sites is performed. A detailed, high-resolution numerical simulation model was developed, that accounts for all BHE components in geometrical detail and incorporates the governing processes. This model was verified using high quality experimental data and is shown to achieve accurate simulation results with excellent fit to the available experimental data, but also leads to large computational times due to the large numerical meshes required for discretizing the highly transient effects. An approximate numerical model for each type of BHE (single U, double U and coaxial) that reduces the number of elements and the simulation time significantly was therefore developed for use in larger scale simulations. The approximate numerical model still includes all BHE components and represents the temporal and spatial temperature distribution with a deviation of less than 2% from the fully discretized model. Simulation times are reduced by a factor of ~10 for single U-tube BHEs, ~20 for double U-tube BHEs and ~150 for coaxial BHEs. This model is then used to investigate achievable storage capacity, injection and extraction rates as well as induced effects for

  1. Economic and technical feasibility study of compressed air storage

    Energy Technology Data Exchange (ETDEWEB)

    1976-03-01

    The results of a study of the economic and technical feasibility of compressed air energy storage (CAES) are presented. The study, which concentrated primarily on the application of underground air storage with combustion turbines, consisted of two phases. In the first phase a general assessment of the technical alternatives, economic characteristics and the institutional constraints associated with underground storage of compressed air for utility peaking application was carried out. The goal of this assessment was to identify potential barrier problems and to define the incentive for the implementation of compressed air storage. In the second phase, the general conclusions of the assessment were tested by carrying out the conceptual design of a CAES plant at two specific sites, and a program of further work indicated by the assessment study was formulated. The conceptual design of a CAES plant employing storage in an aquifer and that of a plant employing storage in a conventionally excavated cavern employing a water leg to maintain constant pressure are shown. Recommendations for further work, as well as directions of future turbo-machinery development, are made. It is concluded that compressed air storage is technically feasible for off-peak energy storage, and, depending on site conditions, CAES plants may be favored over simple cycle turbine plants to meet peak demands. (LCL)

  2. PARÁMETROS FISICOQUÍMICOS DURANTE EL ALMACENAMIENTO DE SALCHICHAS ELABORADAS A PARTIR DE TILAPIA ROJA (Oreochromis sp. PARÂMETROS FISICO-QUÍMICOS DURANTE O ARMAZENAMENTO DE SALSICHAS FEITAS DE TILAPIA VERMELHA (Oreochromis sp. PHYSICOCHEMICAL PARAMETERS DURING STORAGE OF SAUSAGES MADE FROM RED TILAPIA (Oreochromis sp.

    Directory of Open Access Journals (Sweden)

    JOSÉ IGOR HLEAP Z.

    2012-06-01

    ísico-químicos. As salsichas foram preparadas seguindo o procedimento desenvolvido no Laboratório de Tecnologia de Carnes, da Universidade Nacional da Colômbia - Palmira de um colar de tilapia previamente preparado. Determinada umidade, proteína, carboidrato, gordura, cinzas, valor energético, pH, capacidade de retenção de umidade e atividade de água. As descobertas sugerem que o valor nutricional e funcional da salsicha não e alterada durante os primeiros 30 dias de armazenamento, que são consistentes com os dados relatados na literatura, para salsichas feitas de carne crua demais.The growth of aquaculture of red tilapia (Oreochromis sp. in Colombia has allowed the development of food products of higher added value. One of these products are sausages Frankfurt. The aim of this study was to analyze the physicochemical parameters that affect the shelf life of sausages, prepared with addition of sagu starch (Maranthaarundinacea as a binder or extender material. The raised design allowed evaluation of sausages packed under vacuum and under refrigeration (2 °C ± 2 °C at 0, 2, 6, 10, 15, 22, 27, 31, 45, 58, 100 and 120 days of storage for physicochemical parameters. The sausages were prepared following the procedure developed at the Laboratory of Meat Technology, National University of Colombia - Palmira from a previously prepared tilapia paste. Determined moisture, protein, fat carbohydrate, ash, energy, value, pH, moisture holding capacity and water activity. The findings suggest that the nutritional and functional value of the sausage is not altered during first 30 days of storage, which are consistent with data reported in the literature, for sausages made from other raw meat.

  3. The SP Theory of Intelligence: An Overview

    Directory of Open Access Journals (Sweden)

    J Gerard Wolff

    2013-08-01

    Full Text Available This article is an overview of the SP theory of intelligence, which aims to simplify and integrate concepts across artificial intelligence, mainstream computing and human perception and cognition, with information compression as a unifying theme. It is conceived of as a brain-like system that receives "New" information and stores some or all of it in compressed form as "Old" information; and it is realised in the form of a computer model, a first version of the SP machine. The matching and unification of patterns and the concept of multiple alignment are central ideas. Using heuristic techniques, the system builds multiple alignments that are "good" in terms of information compression. For each multiple alignment, probabilities may be calculated for associated inferences. Unsupervised learning is done by deriving new structures from partial matches between patterns and via heuristic search for sets of structures that are "good" in terms of information compression. These are normally ones that people judge to be "natural", in accordance with the "DONSVIC" principle—the discovery of natural structures via information compression. The SP theory provides an interpretation for concepts and phenomena in several other areas, including "computing", aspects of mathematics and logic, the representation of knowledge, natural language processing, pattern recognition, several kinds of reasoning, information storage and retrieval, planning and problem solving, information compression, neuroscience and human perception and cognition. Examples include the parsing and production of language with discontinuous dependencies in syntax, pattern recognition at multiple levels of abstraction and its integration with part-whole relations, nonmonotonic reasoning and reasoning with default values, reasoning in Bayesian networks, including "explaining away", causal diagnosis, and the solving of a geometric analogy problem.

  4. Interception storage capacities of tropical rainforest canopy trees

    Science.gov (United States)

    Herwitz, Stanley R.

    1985-04-01

    The rainwater interception storage capacities of mature canopy trees in a tropical rainforest site in northeast Queensland, Australia, were approximated using a combination of field and laboratory measurements. The above-ground vegetative surfaces of five selected species (three flaky-barked; two smooth-barked) were saturated under laboratory conditions in order to establish their maximum interception storage capacities. Average leaf surface interception storages ranged from 112 to 161 ml m -2. The interception storages of bark ranged from 0.51 to 0.97 ml cm -3. These standardized interception storages were applied to estimates of leaf surface area and bark volume for 51 mature canopy trees representing the selected species in the field site. The average whole tree interception storage capacities of the five species ranged from 110 to 5281 per tree and 2.2 to 8.3 mm per unit projected crown area. The highly significant interspecific differences in interception storage capacity suggest that both floristic and demographic data are needed in order to accurately calculate a forest-wide interception storage capacity for species-rich tropical rainforest vegetation. Species with large woody surface areas and small projected crown areas are capable of storing the greatest depth equivalents of rainwater under heavy rainfall conditions. In the case of both the flaky-barked and the smooth-barked species, bark accounted for > 50% of the total interception storage capacity under still-air conditions, and > 80% under turbulent air conditions. The emphasis in past interception studies on the role of leaf surfaces in determining the interception storage capacity of a vegetative cover must be modified for tropical rainforests to include the storage capacity provided by the bark tissue on canopy trees.

  5. Changes in competence of public authorities in connection with final storage pursuant to the omnibus law on site selection

    International Nuclear Information System (INIS)

    Keienburg, Bettina

    2012-01-01

    The omnibus law on site finding and selection for a repository for radioactive waste generating heat, and with amendments to other laws, of June 13, 2012 is to reshuffle fundamentally the competences of public authorities for final storage. The federal government is to assume more responsibilities from former federal state competences. Moreover, most of the existing competences of the Federal Office for Radiation Protection are to be transferred to a federal agency yet to be founded, which is called Federal Office for Nuclear Safety in the present draft legislation. The Federal Office for Radiation Protection will only retain its responsibility as project agent for repositories, and that only in the phases of site exploration and licensing. Afterwards, the duty of final storage in the draft legislation is transferred to a 3rd party. Again in the version of the draft legislation, and unlike present regulations, this 3rd party may only be a company whose sole owner is the federal government, which also is to strengthen the influence of the federal government under aspects of company law. Legislative efforts seeking to strengthen the federal government and its competences by assigning licensing duties for repositories to federal agencies are understandable under feasibility aspects and may even be in the emotional interest of the states and their competent representatives in public authorities who, merely because their work is connected with the disputed topic of final storage, often face attacks and accusations by the public. Nevertheless, the transfer to federal agencies of administrative duties is subject to constitutional limits which must be observed. These constitutional aspects are highlighted in the publication. It is left to the reader to assess the meaningfulness of establishing another independent high-level federal agency in the area of responsibility of the Federal Ministry of the Environment (BMU), i.e. a Federal Office for Nuclear Safety, alongside the

  6. Annotated bibliography: overview of energy and mineral resources for the Nevada nuclear-waste-storage investigations, Nevada Test Site, Nye County, Nevada

    International Nuclear Information System (INIS)

    Bell, E.J.; Larson, L.T.

    1982-09-01

    This Annotated Bibliography was prepared for the US Department of Energy as part of the Environmental Area Characterization for the Nevada Nuclear Waste Storage Investigations (NNWSI) at the Nevada Test Site (NTS). References were selected to specifically address energy resources including hydrocarbons, geothermal and radioactive fuel materials, mineral resources including base and precious metals and associated minerals, and industrial minerals and rock materials which occur in the vicinity of the NNWSI area

  7. Time to rethink nuclear waste storage

    International Nuclear Information System (INIS)

    Flynn, J.; Kasperson, R.; Kunreuther, H.; Slovic, P.

    1992-01-01

    The authors feel that given the levels of public opposition and distrust, congress should scrap the current nuclear waste storage program and reconsider the options. They observe that no compelling reason currently exists for siting a permanent repository at an early date. Technology developed in the past decade, especially dry-cask storage, provides assurance that wastes from commercial reactors can be stored safely for a lengthy period at current sites. In the longer term, reprocessing may reduce the volume of high-level wastes; storage elsewhere than in a geological repository may prove attractive; and experimental techniques such as transmutation - aimed at radically reducing the amount of time that wastes remain highly radioactive - could help solve the problem. In the meantime, the authors suggest that the US must begin a long-term effort to engage the public in a process of active collaboration. In doing so, the US has much to learn from other countries, where innovative approaches and techniques have began to establish public confidence

  8. Site 300 City Water Master Plan

    Energy Technology Data Exchange (ETDEWEB)

    Shaw, Jeff [Stantec Consulting Services Inc., Irvine, CA (United States)

    2017-03-13

    Lawrence Livermore National Laboratory (LLNL), a scientific research facility, operates an experimental test site known as Site 300. The site is located in a remote area of southeastern Alameda County, California, and consists of about 100 facilities spread across 7,000-acres. The Site 300 water system includes groundwater wells and a system of storage tanks, booster pumps, and underground piping to distribute water to buildings and significant areas throughout the site. Site 300, which is classified as a non-transient non-community (NTNC) water system, serves approximately 110 employees through 109 service connections. The distribution system includes approximately 76,500-feet of water mains varying from 4- to 10-inches in diameter, mostly asbestos cement (AC) pipe, and eleven water storage tanks. The water system is divided into four pressure zones fed by three booster pump stations to tanks in each zone.

  9. Regulatory supervision of sites for spent fuel and radioactive waste storage in the Russian northwest.

    Science.gov (United States)

    Shandala, N K; Sneve, M K; Smith, G M; Kiselev, M F; Kochetkov, O A; Savkin, M N; Simakov, A V; Novikova, N Ya; Titov, A V; Romanov, V V; Seregin, V A; Filonova, A V; Semenova, M P

    2008-12-01

    In the 1960s two technical bases for the Northern Fleet were created in the Russian northwest at Andreeva Bay in the Kola Peninsula and Gremikha village on the coast of the Barents Sea. They maintained nuclear submarines, receiving and storing radioactive waste and spent nuclear fuel. No further waste was received after 1985, and the technical bases have since been re-categorised as temporary storage sites. The handling of these materials to put them into a safe condition is especially hazardous because of their degraded state. This paper describes regulatory activities which have been carried out to support the supervision of radiological protection during recovery of waste and spent fuel, and to support regulatory decisions on overall site remediation. The work described includes: an assessment of the radiation situation on-site; the development of necessary additional regulatory rules and standards for radiation protection assurance for workers and the public during remediation; and the completion of an initial threat assessment to identify regulatory priorities. Detailed consideration of measures for the control of radiation exposure of workers and radiation exposure of the public during and after operations and emergency preparedness and response are complete and provided in sister papers. The continuing requirements for regulatory activities relevant to the development and implementation of on-going and future remediation activities are also outlined. The Norwegian Radiation Protection Authority supports the work, as part of the Norwegian Government's plan of action to promote improvements in radiation protection and nuclear safety in northwest Russia.

  10. Regulatory supervision of sites for spent fuel and radioactive waste storage in the Russian Northwest

    Energy Technology Data Exchange (ETDEWEB)

    Shandala, N K; Kochetkov, O A; Savkin, M N; Simakov, A V; Novikova, N Ya; Titov, A V; Seregin, V A; Filonova, A V; Semenova, M P [Burnasyan Federal Medical Biophysical Centre, Moscow (Russian Federation); Sneve, M K [Norwegian Radiation Protection Authority, Oslo (Norway); Smith, G M [GMS Abingdon Ltd (United Kingdom); Kiselev, M F; Romanov, V V [Federal Medical-Biological Agency, Moscow (Russian Federation)], E-mail: shandala@srcibph.ru

    2008-12-15

    In the 1960s two technical bases for the Northern Fleet were created in the Russian northwest at Andreeva Bay in the Kola Peninsula and Gremikha village on the coast of the Barents Sea. They maintained nuclear submarines, receiving and storing radioactive waste and spent nuclear fuel. No further waste was received after 1985, and the technical bases have since been re-categorised as temporary storage sites. The handling of these materials to put them into a safe condition is especially hazardous because of their degraded state. This paper describes regulatory activities which have been carried out to support the supervision of radiological protection during recovery of waste and spent fuel, and to support regulatory decisions on overall site remediation. The work described includes: an assessment of the radiation situation on-site; the development of necessary additional regulatory rules and standards for radiation protection assurance for workers and the public during remediation; and the completion of an initial threat assessment to identify regulatory priorities. Detailed consideration of measures for the control of radiation exposure of workers and radiation exposure of the public during and after operations and emergency preparedness and response are complete and provided in sister papers. The continuing requirements for regulatory activities relevant to the development and implementation of on-going and future remediation activities are also outlined. The Norwegian Radiation Protection Authority supports the work, as part of the Norwegian Government's plan of action to promote improvements in radiation protection and nuclear safety in northwest Russia.

  11. Effects of CO{sub 2} gas as leaks from geological storage sites on agro-ecosystems

    Energy Technology Data Exchange (ETDEWEB)

    Patil, Ravi H.; Colls, Jeremy J. [Division of Agricultural and Environmental Sciences, School of Biosciences, University of Nottingham, NG7 2RD, Nottingham (United Kingdom); Steven, Michael D. [School of Geography, University of Nottingham, NG7 2RD, Nottingham (United Kingdom)

    2010-12-15

    Carbon capture and storage in geological formations has potential risks in the long-term safety because of the possibility of CO{sub 2} leakage. Effects of leaking gas, therefore, on vegetation, soil, and soil-inhabiting organisms are critical to understand. An artificial soil gassing and response detection field facility developed at the University of Nottingham was used to inject CO{sub 2} gas at a controlled flow rate (1 l min{sup -1}) into soil to simulate build-up of soil CO{sub 2} concentrations and surface fluxes from two land use types: pasture grassland, and fallow followed by winter bean. Mean soil CO{sub 2} concentrations was significantly higher in gassed pasture plots than in gassed fallow plots. Germination of winter bean sown in gassed fallow plots was severely hindered and the final crop stand was reduced to half. Pasture grass showed stress symptoms and above-ground biomass was significantly reduced compared to control plot. A negative correlation (r = -0.95) between soil CO{sub 2} and O{sub 2} concentrations indicated that injected CO{sub 2} displaced O{sub 2} from soil. Gassing CO{sub 2} reduced soil pH both in grass and fallow plots (p = 0.012). The number of earthworm castings was twice as much in gassed plots than in control plots. This study showed adverse effects of CO{sub 2} gas on agro-ecosystem in case of leakage from storage sites to surface. (author)

  12. NRC perspective on extended on-site storage of low-level radioactive waste after 1993

    International Nuclear Information System (INIS)

    Remick, Forrest J.

    1992-01-01

    The Low-Level Radioactive Waste Policy Amendments Act of 1985 (LLRWPAA) requires that each State, which has not provided for disposal capacity by January 1, 1993, must take title and possession of the low-level radioactive wastes generated in the State. If the states do not take title and possession of the wastes, the rebates to which the states would have been entitled to would be returned to the waste generators. in considering the matter, the Commission solicited comments from States) low-level radioactive waste compacts, local governments, and the general public so that the public's views could be factored into the Commission's deliberations on this issue. This paper addresses the current status of NRC positions on the adequacy of the NRC's existing regulatory framework associated with the title transfer provisions of the LLRWPAA and the Commission's views on extended on-site storage of low-level radioactive wastes after the 1993 and 1996 milestones. (author)

  13. Studies for geologic storage of radioactive waste in the southeast

    International Nuclear Information System (INIS)

    Marine, I.W.

    1977-01-01

    The National Waste Terminal Storage (NWTS) program was initiated to conduct the research necessary to select a site for a geologic repository for the storage of high-level, solidified radioactive waste from commercial power reactors. The program also includes the design and construction of the facility and its operation once completed. As part of this program, the Savannah River Laboratory is conducting geological research that is particularly relevant to potential repository sites in the Southeast, but is also of generic applicability. This paper describes the National Waste Terminal Storage program as well as the research program at the Savannah River Laboratory

  14. Studies for geologic storage of radioactive waste in the southeast

    International Nuclear Information System (INIS)

    Marine, I.W.

    1978-01-01

    The National Waste Terminal Storage (NWTS) program was initiated to conduct the research necessary to select a site for a geologic repository for the storage of high-level, solidified radioactive waste from commercial power reactors. The program also includes the design and construction of the facility and its operation once completed. As part of this program, the Savannah River Laboratory is conducting geological research that is particularly relevant to potential repository sites in the southeast, but is also of generic applicability. This paper describes the National Waste Terminal Storage program as well as the research program at the Savannah River Laboratory. 31 figures

  15. CIS as a successor of the Soviet Union: who is financially responsible for the uranium waste storage sites in Kyrgyzstan?

    International Nuclear Information System (INIS)

    Ajtmatova, J.

    2001-05-01

    weapons' arsenal. Yet, the newly independent Kyrgyz Republic was left alone with an enormous amount of uranium waste, which was extracted on the Kyrgyz territory to produce these nuclear armaments. As a consequence of the Soviet policy, uranium waste storage sites represent a direct danger to the environment of present-day Kyrgyzstan. Therefore, Russia as the official successor of the Soviet Empire should help the Kyrgyz Republic to deal with this costly and extensive problem. These environmental issues serve as a basis for the given work. In turn, research will be primarily concentrated on several the most problematic radioactive waste storage sites, namely, the Mailuu-Suu, Kadji-Say, Kara-Balta, and Ak-Tuz uranium storages. Today, Kyrgyzstan has 50 radioactive waste storage sites, located throughout its territory and contained altogether about 300 million tons of wastes. In general, it could be suggested that the financial responsibility could be delegated to the Kyrgyz government; the Central Asian Community; Russia. It is clear with the first instance, the Kyrgyz government, as it ought to deal with the environmental problems of its country. The situation is more sophisticated and arguable in terms of second and third instance, namely, the Central Asian Community and, particularly, Russia. This paper is designed to prove not only the necessity for their involvement, but rather their responsibility for the present-day situation with the Kyrgyz storage sites. As regards the other Central Asian States, it is in their interests since they are under immediate threat of being affected. Concerning Russia, it is rather a moral right to demand its assistance than a legally legitimate one. All information, related to uranium, its extraction and further utilization was totally classified and only revealed after the Soviet Union's dissolution. Only in 1994 did the Kyrgyz public become acquainted with the truly poor environmental conditions of the newly fledged Republic. Yet, no

  16. Nuclear waste. Storage at Vaalputs

    International Nuclear Information System (INIS)

    Anon.

    1984-01-01

    The Vaalputs nuclear waste dump site in Namaqualand is likely to be used to store used fuel from Koeberg, as well as low and intermediate waste. It is argued that Vaalputs is the most suitable site in the world for the disposal of nuclear waste. The Vaalputs site is sparsely populated, there are no mineral deposits of any value, the agricultural potential is minimal. It is a typical semi-desert area. Geologically it lend itself towards the ground-storage of used nuclear fuel

  17. DPM: Future Proof Storage

    CERN Document Server

    Alvarez, Alejandro; Furano, Fabrizio; Hellmich, Martin; Keeble, Oliver; Rocha, Ricardo; CERN. Geneva. IT Department

    2012-01-01

    The Disk Pool Manager (DPM) is a lightweight solution for grid enabled disk storage management. Operated at more than 240 sites it has the widest distribution of all grid storage solutions in the WLCG infrastructure. It provides an easy way to manage and configure disk pools, and exposes multiple interfaces for data access (rfio, xroot, nfs, gridftp and http/dav) and control (srm). During the last year we have been working on providing stable, high performant data access to our storage system using standard protocols, while extending the storage management functionality and adapting both configuration and deployment procedures to reuse commonly used building blocks. In this contribution we cover in detail the extensive evaluation we have performed of our new HTTP/WebDAV and NFS 4.1 frontends, in terms of functionality and performance. We summarize the issues we faced and the solutions we developed to turn them into valid alternatives to the existing grid protocols - namely the additional work required to prov...

  18. Carbon storage of different soil-size fractions in Florida silvopastoral systems.

    Science.gov (United States)

    Haile, Solomon G; Nair, P K Ramachandran; Nair, Vimala D

    2008-01-01

    Compared with open (treeless) pasture systems, silvopastoral agroforestry systems that integrate trees into pasture production systems are likely to enhance soil carbon (C) sequestration in deeper soil layers. To test this hypothesis, total soil C contents at six soil depths (0-5, 5-15, 15-30, 30-50, 50-75, and 75-125 cm) were determined in silvopastoral systems with slash pine (Pinus elliottii) + bahiagrass (Paspalum notatum) and an adjacent open pasture (OP) with bahiagrass at four sites, representing Spodosols and Ultisols, in Florida. Soil samples from each layer were fractionated into three classes (250-2000, 53-250, and <53 microm), and the C contents in each were determined. Averaged across four sites and all depths, the total soil organic carbon (SOC) content was higher by 33% in silvopastures near trees (SP-T) and by 28% in the alleys between tree rows (SP-A) than in adjacent open pastures. It was higher by 39% in SP-A and 20% in SP-T than in open pastures in the largest fraction size (250-2000 microm) and by 12.3 and 18.8%, respectively, in the intermediate size fraction (53-250 microm). The highest SOC increase (up to 45 kg m(-2)) in whole soil of silvopasture compared with OP was at the 75- to 125-cm depth at the Spodosol sites. The results support the hypothesis that, compared with open pastures, silvopastures contain more C in deeper soil layers under similar ecological settings, possibly as a consequence of a major input to soil organic matter from decomposition of dead tree-roots.

  19. Spent fuel storage at the Rancho Seco Nuclear Generation Station

    International Nuclear Information System (INIS)

    Miller, K.R.; Field, J.J.

    1995-01-01

    The Sacramento Municipal Utility District (SMUD) has developed a strategy for the storage and transport of spent nuclear fuel and is now in the process of licensing and manufacturing a Transportable Storage System (TSS). Staff has also engaged in impact limiter testing, non-fuel bearing component reinsertion, storage and disposal of GTCC waste, and site specific upgrades in support of spent fuel dry storage

  20. Dry interim storage of radioactive material in Germany

    International Nuclear Information System (INIS)

    Drobniewski, Christian; Palmes, Julia

    2013-01-01

    In accordance with the waste management concept in Germany, spent fuel is stored in interim storage facilities for a period of up to 40 years until deposition in a geological repository. In twelve on-site interim storages in the vicinity or directly on the sites of the nuclear power plants, spent fuel elements from reactor operation are stored after the necessary period of decay in wet storage basins inside the reactors. Additionally, three central interim storage facilities for storage of spent fuel of different origin are in operation. The German facilities realize the concept of dry interim storage in metallic transport and storage casks. The confinement of the radioactive material is ensured by the double lid system of the casks, of which the leak tightness is monitored constantly. The casks are constructed to provide adequate heat removal and shielding of gamma and neutron radiation. Usually the storage facilities are halls of thick concrete structures, which ensure the removal of the decay heat by natural convection. The main safety goal of the storage concept is to prevent unnecessary exposure of persons, material goods and environment to ionizing radiation. Moreover any exposure should be kept as low as reasonable achievable. To reach this goal the containment of the radioactive materials, the disposal of decay heat, the sub criticality and the shielding of ionizing radiation has to be demonstrated by the applicant and verified by the licensing authority. In particular accidents, incidents and disasters have to be considered in the facility and cask design. This includes mechanical impacts onto the cask, internal and external fire, and environmental effects like wind, rain, snowfall, flood, earthquakes and landslides. In addition civilizatoric influences like plane crashes and explosions have to be taken into account. In all mentioned cases the secure confinement of the radioactive materials has to be ensured. On-site storage facilities have to consider the

  1. Site selection for nuclear power plants

    International Nuclear Information System (INIS)

    Ehjchkholz, D.

    1980-01-01

    Problem of NPP site selection in the USA including engineering factors, radiation and environmental protection factors is stated in detail. Floating and underground sites are considered especially. The attention in paid to waste storage and risk criterium in siting [ru

  2. 10 CFR 72.96 - Siting limitations.

    Science.gov (United States)

    2010-01-01

    ... REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR THE INDEPENDENT STORAGE OF SPENT NUCLEAR FUEL... site within which there is a candidate site for a HLW repository. This limitation shall apply until such time as DOE decides that such candidate site is no longer a candidate site under consideration for...

  3. A consistent approach to CO{sub 2} storage capacity estimation for deep saline formations

    Energy Technology Data Exchange (ETDEWEB)

    Dose, T. [DEA Mineraloel AG, Hamburg (Germany)

    2008-10-23

    Whereas the methodology of assessing pore volume is well established, a consistent methodology for calculating the pore volume efficiency (PVE) needs to be applied, e.g., as proposed in this paper. (1) Numerical simulations show, that CO{sub 2} storage sites are not restricted to geologic traps like anticlines. Also synclines and flat structures provide feasible storage structures, as long as no shortcut to the surface like leaking faults or wells exist. (2) Among active forces induced by CO{sub 2} injection, differential injection pressure and static pressure increase may turn out to be critical. This can lead to overlap with capillary displacement pressure, fracturing pressure, and exceeding the fault friction limit. (3) If differential injection pressure turns out to be critical, this can be balanced technically. Fault slippage can be avoided by selecting appropriate sites. (4) For the CO{sub 2} storage system to stay in balance, it is required that the static pressure increase stays below the capillary displacement pressure. (5) With this limiting conditions, scenarios show PVEs of 0.1-0.65% for a hydraulic system, mostly dependant on caprock quality and total compressibility. (6) Likely several possible storage sites exist for a hydraulic system. It is almost sure that the sum of the local storage potential will exceed the storage potential of the hydraulic system. (7) Regional pressure effects of CO{sub 2} storage can be significant. Different storage sites injecting at high rates into the same hydraulic system will need large distances between them. (9) Due to likely interference of storage sites and other fluid operations within a hydraulic system, close cooperations between operators may become necessary. (orig.)

  4. Studying unsaturated epikarst water storage properties by time lapse surface to depth gravity measurements

    Science.gov (United States)

    Deville, S.; Champollion, C.; chery, J.; Doerflinger, E.; Le Moigne, N.; Bayer, R.; Vernant, P.

    2011-12-01

    The assessment of water storage in the unsaturated zone in karstic areas is particularly challenging. Indeed, water flow path and water storage occur in quite heterogeneous ways through small scale porosity, fractures, joints and large voids. Due to this large heterogeneity, it is therefore difficult to estimate the amount of water circulating in the vadose zone by hydrological means. One indirect method consists to measure the gravity variation associated to water storage and withdrawal. Here, we apply a gravimetric method in which the gravity is measured at the surface and at depth on different sites. Then the time variations of the surface to depth (STD) gravity differences are compared for each site. In this study we attempt to evaluate the magnitude of epikarstic water storage variation in various karst settings using a CG5 portable gravimeter. Surface to depth gravity measurements are performed two times a year since 2009 at the surface an inside caves at different depths on three karst aquifers in southern France : 1. A limestone site on the Larzac plateau with a vadose zone thickness of 300m On this site measurements are done on five locations at different depths going from 0 to 50 m; 2. A dolomitic site on the Larzac plateau (Durzon karst aquifer) with a vadose zone thickness of 200m; Measurements are taken at the surface and at 60m depth 3. A limestone site on the Hortus karst aquifer and "Larzac Septentrional karst aquifer") with a vadose zone thickness of only 35m. Measurements are taken at the surface and at 30m depth Therefore, our measurements are used in two ways : First, the STD differences between dry and wet seasons are used to estimate the capacity of differential storage of each aquifer. Surprisingly, the differential storage capacity of all the sites is relatively invariant despite their variable geological of hydrological contexts. Moreover, the STD gravity variations on site 1 show that no water storage variation occurs beneath 10m depth

  5. Behavior of spent nuclear fuel in water pool storage

    International Nuclear Information System (INIS)

    Johnson, A.B. Jr.

    1977-09-01

    Storage of irradiated nuclear fuel in water pools (basins) has been standard practice since nuclear reactors first began operation approximately 34 years ago. Pool storage is the starting point for all other fuel storage candidate processes and is a candidate for extended interim fuel storage until policy questions regarding reprocessing and ultimate disposal have been resolved. This report assesses the current performance of nuclear fuel in pool storage, the range of storage conditions, and the prospects for extending residence times. The assessment is based on visits to five U.S. and Canadian fuel storage sites, representing nine storage pools, and on discussions with operators of an additional 21 storage pools. Spent fuel storage experience from British pools at Winfrith and Windscale and from a German pool at Karlsruhe (WAK) also is summarized

  6. Assuring safe interim storage of Hanford high-level tank wastes

    International Nuclear Information System (INIS)

    Bacon, R.F.; Babad, H.; Lerch, R.E.

    1996-01-01

    The federal government established the Hanford Site in South-Eastern Washington near the City of Richland in 1943 to produce plutonium for national defense purposes. The Hanford Site occupies approximately 1,450 square kilometers (560 square miles) of land North of the City of Richland. The production mission ended in 1988, transforming the Hanford Site mission to waste management, environmental restoration, and waste disposal. Thus the primary site mission has shifted from production to the management and disposal of radioactive, hazardous, and mixed waste that exist at the Hanford Site. This paper describes the focus and challenges facing the Tank Waste Remediation System (TWRS) Program related to the dual and parallel missions of interim safe storage and disposal of the tank associated waste. These wastes are presently stored in 2.08E+05 liters (55,000) to 4.16E+06 liters (1,100,000) gallon low-carbon steel tanks. There are 149 single- and 28 double-shell radioactive underground storage tanks, as well as approximately 40 inactive miscellaneous underground storage tanks. In addition, the TWRS mission includes the storage and disposal of the inventory of 1,929 cesium and strontium capsules created as part of waste management efforts. Tank waste was a by-product of producing plutonium and other defense related materials. From 1944 through 1990, four (4) different major chemical processing facilities at the Hanford Site processed irradiated (spent) fuel from defense reactors to separate and recover plutonium for weapons production. As new and improved processes were developed over the last 50 years, the processing efficiency improved and the waste compositions sent to the tanks for storage changed both chemically and radiologically. The earliest separation processes (e.g., bismuth phosphate coprecipitation) carried out in T Plant (1944-1956) and B Plant (1945-1952) recovered only plutonium

  7. Radioactive wastes. Safety of storage facilities

    International Nuclear Information System (INIS)

    Devillers, Ch.

    2001-01-01

    A radioactive waste storage facility is designed in a way that ensures the isolation of wastes with respect to the biosphere. This function comprises the damping of the gamma and neutron radiations from the wastes, and the confinement of the radionuclides content of the wastes. The safety approach is based on two time scales: the safety of the insulation system during the main phase of radioactive decay, and the assessment of the radiological risks following this phase. The safety of a surface storage facility is based on a three-barrier concept (container, storage structures, site). The confidence in the safety of the facility is based on the quality assurance of the barriers and on their surveillance and maintenance. The safety of a deep repository will be based on the site quality, on the design and construction of structures and on the quality of the safety demonstration. This article deals with the safety approach and principles of storage facilities: 1 - recall of the different types of storage facilities; 2 - different phases of the life of a storage facility and regulatory steps; 3 - safety and radiation protection goals (time scales, radiation protection goals); 4 - safety approach and principles of storage facilities: safety of the isolation system (confinement system, safety analysis, scenarios, radiological consequences, safety principles), assessment of the radiation risks after the main phase of decay; 5 - safety of surface storage facilities: safety analysis of the confinement system of the Aube plant (barriers, scenarios, modeling, efficiency), evaluation of radiological risks after the main phase of decay; experience feedback of the Manche plant; variants of surface storage facilities in France and abroad (very low activity wastes, mine wastes, short living wastes with low and average activity); 6 - safety of deep geological disposal facilities: legal framework of the French research; international context; safety analysis of the confinement system

  8. Design cost scoping studies. Nevada Test Site Terminal Waste Storage Program, Subtask 1.3: facility hardening studies

    International Nuclear Information System (INIS)

    Yanev, P.I.; Owen, G.N.

    1978-04-01

    As part of a program being conducted by the U.S. Department of Energy, Nevada Operations Office, to determine the feasibility of establishing a terminal waste storage repository at the Nevada Test Site, URS/John A. Blume and Associates, Engineers, made approximate determinations of the additional costs required to provide protection of structures against seismic forces. A preliminary estimate is presented of the added costs required to harden the surface structures, underground tunnels and storage rooms, and vertical shafts of the repository against ground motion caused by earthquakes and underground nuclear explosions (UNEs). The conceptual design of all of the structures was adapted from proposed bedded-salt waste-isolation repositories. Added costs for hardening were calculated for repositories in three candidate geological materials (Eleana argillite, Climax Stock granite, and Jackass Flats tuff) for several assumed peak ground accelerations caused by earthquakes (0.3g, 0.5g, and 0.7g) and by UNEs (0.5g, 0.7g, and 1.0g). Hardening procedures to protect the tunnels, storage rooms, and shafts against incremental seismic loadings were developed from (1) qualitative considerations of analytically determined seismic stresses and (2) engineering evaluations of the dynamic response of the rock mass and the tunnel support systems. The added costs for seismic hardening of the surface structures were found to be less than 1% of the estimated construction cost of the surface structures. For the underground structures, essentially no hardening was required for peak ground accelerations up to 0.3g; however, added costs became significant at 0.5g, with a possible increase in structural costs for the underground facilities of as much as 35% at 1.0g

  9. Opportunities for low-cost CO2 storage demonstration projects in China

    International Nuclear Information System (INIS)

    Meng, Kyle C.; Williams, Robert H.; Celia, Michael A.

    2007-01-01

    Several CO 2 storage demonstration projects are needed in a variety of geological formations worldwide to prove the viability of CO 2 capture and storage as a major option for climate change mitigation. China has several low-cost CO 2 sources at sites that produce NH 3 from coal via gasification. At these plants, CO 2 generated in excess of the amount needed for other purposes (e.g., urea synthesis) is vented as a relatively pure stream. These CO 2 sources would potentially be economically interesting candidates for storage demonstration projects if there are suitable storage sites nearby. In this study a survey was conducted to estimate CO 2 availability at modern Chinese coal-fed ammonia plants. Results indicate that annual quantities of available, relatively pure CO 2 per site range from 0.6 to 1.1 million tonnes. The CO 2 source assessment was complemented by analysis of possible nearby opportunities for CO 2 storage. CO 2 sources were mapped in relation to China's petroliferous sedimentary basins where prospective CO 2 storage reservoirs possibly exist. Four promising pairs of sources and sinks were identified. Project costs for storage in deep saline aquifers were estimated for each pairing ranging from $15-21/t of CO 2 . Potential enhanced oil recovery and enhanced coal bed methane recovery opportunities near each prospective source were also considered

  10. Advantages of dry hardened cask storage over wet storage for spent nuclear fuel

    Energy Technology Data Exchange (ETDEWEB)

    Romanato, Luiz Sergio, E-mail: romanato@ctmsp.mar.mil.b [Centro Tecnologico da Marinha em Sao Paulo (CTMSP), Sao Paulo, SP (Brazil). Dept. da Qualidade

    2011-07-01

    Pools are generally used to store and maintain spent nuclear fuel assemblies for cooling, after removed from reactors. After three to five years stored in the pools, spent fuel can be reprocessed or sent to a final disposition in a geological repository and handled as radioactive waste or sent to another site waiting for future solution. Spent fuel can be stored in dry or wet installations, depending on the method adopted by the nuclear plant. If this storage were exclusively wet, at the installation decommissioning in the future, another solution for storage will need to be found. Today, after a preliminary cooling, the spent fuel assemblies can be removed from the pool and sent to dry hardened storage installations. This kind of storage does not need complex radiation monitoring and it is safer than wet storage. Brazil has two nuclear reactors in operation, a third reactor is under construction and they use wet spent fuel storage . Dry hardened casks use metal or both metal and concrete for radiation shielding and they are safe, especially during an earthquake. An earthquake struck Japan on March 11, 2011 damaging Fukushima Daiichi nuclear power plant. The occurrence of earthquakes in Brazil is very small but dry casks can resist to other events, including terrorist acts, better than pools. This paper shows the advantages of dry hardened cask storage in comparison with the wet storage (water pools) for spent nuclear fuel. (author)

  11. Advantages of dry hardened cask storage over wet storage for spent nuclear fuel

    International Nuclear Information System (INIS)

    Romanato, Luiz Sergio

    2011-01-01

    Pools are generally used to store and maintain spent nuclear fuel assemblies for cooling, after removed from reactors. After three to five years stored in the pools, spent fuel can be reprocessed or sent to a final disposition in a geological repository and handled as radioactive waste or sent to another site waiting for future solution. Spent fuel can be stored in dry or wet installations, depending on the method adopted by the nuclear plant. If this storage were exclusively wet, at the installation decommissioning in the future, another solution for storage will need to be found. Today, after a preliminary cooling, the spent fuel assemblies can be removed from the pool and sent to dry hardened storage installations. This kind of storage does not need complex radiation monitoring and it is safer than wet storage. Brazil has two nuclear reactors in operation, a third reactor is under construction and they use wet spent fuel storage . Dry hardened casks use metal or both metal and concrete for radiation shielding and they are safe, especially during an earthquake. An earthquake struck Japan on March 11, 2011 damaging Fukushima Daiichi nuclear power plant. The occurrence of earthquakes in Brazil is very small but dry casks can resist to other events, including terrorist acts, better than pools. This paper shows the advantages of dry hardened cask storage in comparison with the wet storage (water pools) for spent nuclear fuel. (author)

  12. Fatty acid composition of Spirulina sp., Chlorella sp. and Chaetoceros sp. microalgae and introduction as potential new sources to extinct omega 3 and omega 6

    Directory of Open Access Journals (Sweden)

    Homan Gorjzdadeh

    2016-05-01

    Full Text Available Background: This study was carried out to determine the oil fatty acids from two special species of microalgae; Spirulina sp.,Chlorella sp. and also Chaetoceros sp. collected from Bahmanshir River. Materials and Methods: Sampling of microalgae Chaetoceros sp. from Bahmanshir River was under taken using bottle samplers during spring season of 2013. Microalgae Spirulina sp. and Chlorella sp. were supplied from Shrimp Research Institute of Iran in Bushehr Province. Samples then were cultured under controlled laboratory conditions and mass culture for 100 liters was undertaken. Isolation of microalgae species from water of cultured media was carried out using filtration and centrifugation methods. The fatty acid compositions were determined by Gas – FID chromatography. Results: Results showed that regarding Saturated Fatty Acids (SFA obtained from purified culture of Chaetoceros sp., Spirulina sp. and Chlorella sp. the maximum amount of total fatty acids were belonged to palmitic acids (C16:0 with 15.21%, 30.1% and 25.17% of total fatty acids  respectively. Analysis of Mono Unsaturated Fatty Acids (MUFA showed that in the Oleic acid was maximum amount of 34% in Spirulina sp. In addition the amount of MUFA in Chlorella sp. was 16.37% of total fatty acids. On the other hand the amount of palmeotic acid in purified culture of Chaetoceros sp. was 30.33% from total content of fatty acids. Analysis of Poly Unsaturated Fatty Acids (PUFA, Linoleic acid (C18:2 (Omega 6, revealed maximum percentage in Spirulina sp. with 18.8%. Results of Alpha linoleic acid (C18:3 (Omega3 analysis showed maximum amount of 9.66% in Chlorella sp. compared to other microalgae with lower omega 3 contents. Spirulina sp. contained maximum amount of Linoleic acid (C18:2 with 18.8% of total fatty acids. Therefore, Spirulina sp. can be considered as a rich source of omega 6 for the purpose of fatty acid extractions. The presence of PUFA in Chlorella sp. and Spirulina sp. was

  13. Methane storage in metal-organic frameworks.

    Science.gov (United States)

    He, Yabing; Zhou, Wei; Qian, Guodong; Chen, Banglin

    2014-08-21

    Natural gas (NG), whose main component is methane, is an attractive fuel for vehicular applications. Realization of safe, cheap and convenient means and materials for high-capacity methane storage can significantly facilitate the implementation of natural gas fuelled vehicles. The physisorption based process involving porous materials offers an efficient storage methodology and the emerging porous metal-organic frameworks have been explored as potential candidates because of their extraordinarily high porosities, tunable pore/cage sizes and easily immobilized functional sites. In this view, we provide an overview of the current status of metal-organic frameworks for methane storage.

  14. PsiQuaSP-A library for efficient computation of symmetric open quantum systems.

    Science.gov (United States)

    Gegg, Michael; Richter, Marten

    2017-11-24

    In a recent publication we showed that permutation symmetry reduces the numerical complexity of Lindblad quantum master equations for identical multi-level systems from exponential to polynomial scaling. This is important for open system dynamics including realistic system bath interactions and dephasing in, for instance, the Dicke model, multi-Λ system setups etc. Here we present an object-oriented C++ library that allows to setup and solve arbitrary quantum optical Lindblad master equations, especially those that are permutationally symmetric in the multi-level systems. PsiQuaSP (Permutation symmetry for identical Quantum Systems Package) uses the PETSc package for sparse linear algebra methods and differential equations as basis. The aim of PsiQuaSP is to provide flexible, storage efficient and scalable code while being as user friendly as possible. It is easily applied to many quantum optical or quantum information systems with more than one multi-level system. We first review the basics of the permutation symmetry for multi-level systems in quantum master equations. The application of PsiQuaSP to quantum dynamical problems is illustrated with several typical, simple examples of open quantum optical systems.

  15. spMC: an R-package for 3D lithological reconstructions based on spatial Markov chains

    Science.gov (United States)

    Sartore, Luca; Fabbri, Paolo; Gaetan, Carlo

    2016-09-01

    The paper presents the spatial Markov Chains (spMC) R-package and a case study of subsoil simulation/prediction located in a plain site of Northeastern Italy. spMC is a quite complete collection of advanced methods for data inspection, besides spMC implements Markov Chain models to estimate experimental transition probabilities of categorical lithological data. Furthermore, simulation methods based on most known prediction methods (as indicator Kriging and CoKriging) were implemented in spMC package. Moreover, other more advanced methods are available for simulations, e.g. path methods and Bayesian procedures, that exploit the maximum entropy. Since the spMC package was developed for intensive geostatistical computations, part of the code is implemented for parallel computations via the OpenMP constructs. A final analysis of this computational efficiency compares the simulation/prediction algorithms by using different numbers of CPU cores, and considering the example data set of the case study included in the package.

  16. Research on an IP disaster recovery storage system

    Science.gov (United States)

    Zeng, Dong; Wang, Yusheng; Zhu, Jianfeng

    2008-12-01

    According to both the Fibre Channel (FC) Storage Area Network (SAN) switch and Fabric Application Interface Standard (FAIS) mechanism, an iSCSI storage controller is put forward and based upon it, an internet Small Computer System Interface (iSCSI) SAN construction strategy for disaster recovery (DR) is proposed and some multiple sites replication models and a closed queue performance analysis method are also discussed in this paper. The iSCSI storage controller lies in the fabric level of the networked storage infrastructure, and it can be used to connect to both the hybrid storage applications and storage subsystems, besides, it can provide virtualized storage environment and support logical volume access control, and by cooperating with the remote peerparts, a disaster recovery storage system can be built on the basis of the data replication, block-level snapshot and Internet Protocol (IP) take-over functions.

  17. (/sup 3/H)Spiperone binding sites in brain: autoradiographic localization of multiple receptors

    Energy Technology Data Exchange (ETDEWEB)

    Palacios, J M; Niehoff, D L; Kuhar, M J [Johns Hopkins Univ., Baltimore, MD (USA). School of Medicine

    1981-01-01

    (/sup 3/H)Spiperone ((/sup 3/H)SP) binding sites were localized by light microscopic autoradiography, after in vitro labelling. The kinetic and pharmacological characteristics of these binding sites were studied in slide-mounted sections of rat forebrain, and optimal labeling conditions were defined. Autoradiograms were obtained by apposing emulsion-coated coverslips to labeled sections. Differential drug sensitivity allowed the selective displacement of (/sup 3/H)SP from dopamine receptors by ADTN, from serotonin receptors by cinanserin, from both by haloperidol and from unique spiperone sites by unlabeled spiperone. The various sites presented a differential anatomical localization. For example, only dopaminergic sites were found in the glomerular layer of the olfactory bulb; only serotonergic sites were found in lamina IV of the neocortex, and a high concentration of unique spiperone sites were found in parts of the hippocampus.

  18. Deep reversible storage. Design options for the storage in deep geological formation - High-medium activity, long living wastes 2009 milestone

    International Nuclear Information System (INIS)

    2010-09-01

    This report aims at presenting a synthesis of currently studied solutions for the different components of the project of deep geological radioactive waste storage centre. For each of these elements, the report indicates the main operational objectives to be taken into account in relationship with safety functions or with reversibility. It identifies the currently proposed design options, presents the technical solutions (with sometime several possibilities), indicates industrial references (in the nuclear sector, in underground works) and comments results of technological tests performed by the ANDRA. After a description of functionalities and of the overall organisation of storage components, the different following elements and aspects are addressed: surface installations, underground architecture, parcel transfer between the surface and storage cells, storage container for medium-activity long-life (MAVL) waste, storage cell for medium-activity long-life waste, handling of MAVL parcels in storage cells, storage container for high-activity (HA) waste, storage cell for HA waste, handling of HA parcels in storage cells, and works for site closing

  19. Feasibility study: Assess the feasibility of siting a monitored retrievable storage facility. Phase 1

    Energy Technology Data Exchange (ETDEWEB)

    King, J.W.

    1993-08-01

    The purpose of phase one of this study are: To understand the waste management system and a monitored retrievable storage facility; and to determine whether the applicant has real interest in pursuing the feasibility assessment process. Contents of this report are: Generating electric power; facts about exposure to radiation; handling storage, and transportation techniques; description of a proposed monitored retrievable storage facility; and benefits to be received by host jurisdiction.

  20. Storage and Disposal of Solid Radioactive Waste

    Energy Technology Data Exchange (ETDEWEB)

    Pomarola, J. [Head of Technical Section, Monitoring and Protection Division, Atomic Energy Commission, Saclay (France)

    1960-07-01

    This paper deals with solutions for the problem of final disposal of solid radioactive waste. I. It is first essential to organize a proper system of temporary storage. II. Final Storage In order to organize final storage, it is necessary to fix, according to the activity and form of the waste, the site and the modes of transport to be used within and outside the nuclear centre. The choice of solutions follows from the foregoing essentials. The paper then considers, in turn, final storage, on the ground, in the sub-soil and in the sea. Economic considerations are an important factor in determining the choice of solution. (author)