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Sample records for characterization facility wscf

  1. Waste Sampling & Characterization Facility (WSCF) Complex Safety Analysis

    Energy Technology Data Exchange (ETDEWEB)

    MELOY, R.T.

    2002-04-01

    This document was prepared to analyze the Waste Sampling and Characterization Facility for safety consequences by: Determining radionuclide and highly hazardous chemical inventories; Comparing these inventories to the appropriate regulatory limits; Documenting the compliance status with respect to these limits; and Identifying the administrative controls necessary to maintain this status. The primary purpose of the Waste Sampling and Characterization Facility (WSCF) is to perform low-level radiological and chemical analyses on various types of samples taken from the Hanford Site. These analyses will support the fulfillment of federal, Washington State, and Department of Energy requirements.

  2. INVESTIGATION OF THE TOTAL ORGANIC HALOGEN ANALYTICAL METHOD AT THE WASTE SAMPLING CHARACTERIZATION FACILITY (WSCF)

    Energy Technology Data Exchange (ETDEWEB)

    DOUGLAS JG; MEZNARICH HD, PHD; OLSEN JR; ROSS GA; STAUFFER M

    2008-09-30

    Total organic halogen (TOX) is used as a parameter to screen groundwater samples at the Hanford Site. Trending is done for each groundwater well, and changes in TOX and other screening parameters can lead to costly changes in the monitoring protocol. The Waste Sampling and Characterization Facility (WSCF) analyzes groundwater samples for TOX using the United States Environmental Protection Agency (EPA) SW-846 method 9020B (EPA 1996a). Samples from the Soil and Groundwater Remediation Project (S&GRP) are submitted to the WSCF for analysis without information regarding the source of the sample; each sample is in essence a 'blind' sample to the laboratory. Feedback from the S&GRP indicated that some of the WSCF-generated TOX data from groundwater wells had a number of outlier values based on the historical trends (Anastos 2008a). Additionally, analysts at WSCF observed inconsistent TOX results among field sample replicates. Therefore, the WSCF lab performed an investigation of the TOX analysis to determine the cause of the outlier data points. Two causes were found that contributed to generating out-of-trend TOX data: (1) The presence of inorganic chloride in the groundwater samples: at inorganic chloride concentrations greater than about 10 parts per million (ppm), apparent TOX values increase with increasing chloride concentration. A parallel observation is the increase in apparent breakthrough of TOX from the first to the second activated-carbon adsorption tubes with increasing inorganic chloride concentration. (2) During the sample preparation step, excessive purging of the adsorption tubes with oxygen pressurization gas after sample loading may cause channeling in the activated-carbon bed. This channeling leads to poor removal of inorganic chloride during the subsequent wash step with aqueous potassium nitrate. The presence of this residual inorganic chloride then produces erroneously high TOX values. Changes in sample preparation were studied to more

  3. Quality assurance program plan for low-level waste at the WSCF Laboratory

    International Nuclear Information System (INIS)

    The purpose of this document is to provide guidance for the implementation of the Quality Assurance Program Plan (QAPP) for the management of low-level waste at the Waste Sampling and Characterization Facility (WSCF) Laboratory Complex as required by WHC-CM-4-2, Quality Assurance Manual, which is based on Quality Assurance Program Requirements for Nuclear Facilities, NQA-1 (ASME)

  4. Waste sampling and characterization facility complex safety analysis

    Energy Technology Data Exchange (ETDEWEB)

    Meloy, R.T., Westinghouse Hanford

    1996-06-04

    The Waste Sampling and Characterization Facility is a `Non-Nuclear, Radiological Facility. This document demonstrates, by analysis, that WSCF can meet the chemical and radiological inventory limits for a radiological facility. It establishes control that ensures those inventories are maintained below threshold values to preserve the `Non- Nuclear, Radiological` classification.

  5. INVESTIGATION OF THE TOTAL ORGANIC HALOGEN ANALYTICAL METHOD AT THE WASTE SAMPLING AND CHARACTERIZATION FACILITY

    International Nuclear Information System (INIS)

    Total organic halogen (TOX) is used as a parameter to screen groundwater samples at the Hanford Site. Trending is done for each groundwater well, and changes in TOX and other screening parameters can lead to costly changes in the monitoring protocol. The Waste Sampling and Characterization Facility (WSCF) analyzes groundwater samples for TOX using the United States Environmental Protection Agency (EPA) SW-S46 method 9020B (EPA 1996a). Samples from the Soil and Groundwater Remediation Project (SGRP) are submitted to the WSCF for analysis without information regarding the source of the sample; each sample is in essence a ''blind'' sample to the laboratory. Feedback from the SGRP indicated that some of the WSCF-generated TOX data from groundwater wells had a number of outlier values based on the historical trends (Anastos 200Sa). Additionally, analysts at WSCF observed inconsistent TOX results among field sample replicates. Therefore, the WSCF lab performed an investigation of the TOX analysis to determine the cause of the outlier data points. Two causes were found that contributed to generating out-of-trend TOX data: (1) The presence of inorganic chloride in the groundwater samples: at inorganic chloride concentrations greater than about 10 parts per million (ppm), apparent TOX values increase with increasing chloride concentration. A parallel observation is the increase in apparent breakthrough of TOX from the first to the second activated-carbon adsorption tubes with increasing inorganic chloride concentration. (2) During the sample preparation step, excessive purging of the adsorption tubes with oxygen pressurization gas after sample loading may cause channeling in the activated carbon bed. This channeling leads to poor removal of inorganic chloride during the subsequent wash step with aqueous potassium nitrate. The presence of this residual inorganic chloride then produces erroneously high TOX values. Changes in sample preparation were studied to more effectively

  6. INVESTIGATION OF THE TOTAL ORGANIC HALOGEN ANALYTICAL METHOD AT THE WASTE SAMPLING AND CHARACTERIZATION FACILITY

    Energy Technology Data Exchange (ETDEWEB)

    JG DOUGLAS; HK MEZNARICH, PHD; JR OLSEN; GA ROSS PHD; M STAUFFER

    2009-02-13

    Total organic halogen (TOX) is used as a parameter to screen groundwater samples at the Hanford Site. Trending is done for each groundwater well, and changes in TOX and other screening parameters can lead to costly changes in the monitoring protocol. The Waste Sampling and Characterization Facility (WSCF) analyzes groundwater samples for TOX using the United States Environmental Protection Agency (EPA) SW-S46 method 9020B (EPA 1996a). Samples from the Soil and Groundwater Remediation Project (SGRP) are submitted to the WSCF for analysis without information regarding the source of the sample; each sample is in essence a ''blind'' sample to the laboratory. Feedback from the SGRP indicated that some of the WSCF-generated TOX data from groundwater wells had a number of outlier values based on the historical trends (Anastos 200Sa). Additionally, analysts at WSCF observed inconsistent TOX results among field sample replicates. Therefore, the WSCF lab performed an investigation of the TOX analysis to determine the cause of the outlier data points. Two causes were found that contributed to generating out-of-trend TOX data: (1) The presence of inorganic chloride in the groundwater samples: at inorganic chloride concentrations greater than about 10 parts per million (ppm), apparent TOX values increase with increasing chloride concentration. A parallel observation is the increase in apparent breakthrough of TOX from the first to the second activated-carbon adsorption tubes with increasing inorganic chloride concentration. (2) During the sample preparation step, excessive purging of the adsorption tubes with oxygen pressurization gas after sample loading may cause channeling in the activated carbon bed. This channeling leads to poor removal of inorganic chloride during the subsequent wash step with aqueous potassium nitrate. The presence of this residual inorganic chloride then produces erroneously high TOX values. Changes in sample preparation were studied

  7. Materials Characterization Facility

    Data.gov (United States)

    Federal Laboratory Consortium — The Materials Characterization Facility enables detailed measurements of the properties of ceramics, polymers, glasses, and composites. It features instrumentation...

  8. Mound facility physical characterization

    Energy Technology Data Exchange (ETDEWEB)

    Tonne, W.R.; Alexander, B.M.; Cage, M.R.; Hase, E.H.; Schmidt, M.J.; Schneider, J.E.; Slusher, W.; Todd, J.E.

    1993-12-01

    The purpose of this report is to provide a baseline physical characterization of Mound`s facilities as of September 1993. The baseline characterizations are to be used in the development of long-term future use strategy development for the Mound site. This document describes the current missions and alternative future use scenarios for each building. Current mission descriptions cover facility capabilities, physical resources required to support operations, current safety envelope and current status of facilities. Future use scenarios identify potential alternative future uses, facility modifications required for likely use, facility modifications of other uses, changes to safety envelope for the likely use, cleanup criteria for each future use scenario, and disposition of surplus equipment. This Introductory Chapter includes an Executive Summary that contains narrative on the Functional Unit Material Condition, Current Facility Status, Listing of Buildings, Space Plans, Summary of Maintenance Program and Repair Backlog, Environmental Restoration, and Decontamination and Decommissioning Programs. Under Section B, Site Description, is a brief listing of the Site PS Development, as well as Current Utility Sources. Section C contains Site Assumptions. A Maintenance Program Overview, as well as Current Deficiencies, is contained within the Maintenance Program Chapter.

  9. FRACTURING FLUID CHARACTERIZATION FACILITY

    Energy Technology Data Exchange (ETDEWEB)

    Subhash Shah

    2000-08-01

    Hydraulic fracturing technology has been successfully applied for well stimulation of low and high permeability reservoirs for numerous years. Treatment optimization and improved economics have always been the key to the success and it is more so when the reservoirs under consideration are marginal. Fluids are widely used for the stimulation of wells. The Fracturing Fluid Characterization Facility (FFCF) has been established to provide the accurate prediction of the behavior of complex fracturing fluids under downhole conditions. The primary focus of the facility is to provide valuable insight into the various mechanisms that govern the flow of fracturing fluids and slurries through hydraulically created fractures. During the time between September 30, 1992, and March 31, 2000, the research efforts were devoted to the areas of fluid rheology, proppant transport, proppant flowback, dynamic fluid loss, perforation pressure losses, and frictional pressure losses. In this regard, a unique above-the-ground fracture simulator was designed and constructed at the FFCF, labeled ''The High Pressure Simulator'' (HPS). The FFCF is now available to industry for characterizing and understanding the behavior of complex fluid systems. To better reflect and encompass the broad spectrum of the petroleum industry, the FFCF now operates under a new name of ''The Well Construction Technology Center'' (WCTC). This report documents the summary of the activities performed during 1992-2000 at the FFCF.

  10. Nanometer Characterization/Manipulation Facility

    Data.gov (United States)

    Federal Laboratory Consortium — FUNCTION: Characterizes the nanometer scale of biological, chemical, physical, electronic, and mechanical properties of surfaces and thin films using scanning probe...

  11. The Decommissioning Facility Characterization DB System (DEFACS)

    International Nuclear Information System (INIS)

    The computer system for the characterization on the nuclear facilities is established as the name of the DEFACS (DEcommissioning FAcility Characterization DB System). his system is consist of the four main part with the grouping of the items and it's code creation and management system, data input system, data processing and data out put system. All the data was processed by a simplified and formatted manner to provide useful information to the decommissioning planner. The four nuclear facilities are objected for the system; the KRR-1 and 2 (Research reactor), Uranium conversion plant (Nuclear chemical plant), UF4 pilot plant and the North Korea nuclear facility (5MWe Research Reactor). All the data from a nuclear facility was categorized and inputted into the several data fields in the input system, which were chosen by considering the facility characteristics. All the hardware is workstation for Web and DB server and PC grade computers for the users and the software 'ORACLE, RDBMS 11g' operated on the WINDOW 2008 O/S, was selected

  12. Characterizing experiments of the PPOOLEX test facility

    Energy Technology Data Exchange (ETDEWEB)

    Puustinen, M.; Laine, J. (Lappeenranta Univ. of Technology, Nuclear Safety Research Unit (Finland))

    2008-07-15

    This report summarizes the results of the characterizing test series in 2007 with the scaled down PPOOLEX facility designed and constructed at Lappeenranta University of Technology. Air and steam/air mixture was blown into the dry well compartment and from there through a DN200 blowdown pipe to the condensation pool (wet well). Altogether eight air and four steam/air mixture experiments, each consisting of several blows (tests), were carried out. The main purpose of the experiment series was to study the general behavior of the facility and the performance of basic instrumentation. Proper operation of automation, control and safety systems was also tested. The test facility is a closed stainless steel vessel divided into two compartments, dry well and wet well. The facility is equipped with high frequency measurements for capturing different aspects of the investigated phenomena. The general behavior of the PPOOLEX facility differs significantly from that of the previous POOLEX facility because of the closed two-compartment structure of the test vessel. Heat-up by several tens of degrees due to compression in both compartments was the most obvious evidence of this. Temperatures also stratified. Condensation oscillations and chugging phenomenon were encountered in those tests where the fraction of non-condensables had time to decrease significantly. A radical change from smooth condensation behavior to oscillating one occurred quite abruptly when the air fraction of the blowdown pipe flow dropped close to zero. The experiments again demonstrated the strong diminishing effect that noncondensable gases have on dynamic unsteady loadings experienced by submerged pool structures. BWR containment like behavior related to the beginning of a postulated steam line break accident was observed in the PPOOLEX test facility during the steam/air mixture experiments. The most important task of the research project, to produce experimental data for code simulation purposes, can be

  13. The spectral imaging facility: Setup characterization

    Energy Technology Data Exchange (ETDEWEB)

    De Angelis, Simone, E-mail: simone.deangelis@iaps.inaf.it; De Sanctis, Maria Cristina; Manzari, Paola Olga [Institute for Space Astrophysics and Planetology, INAF-IAPS, Via Fosso del Cavaliere, 100, 00133 Rome (Italy); Ammannito, Eleonora [Institute for Space Astrophysics and Planetology, INAF-IAPS, Via Fosso del Cavaliere, 100, 00133 Rome (Italy); Department of Earth, Planetary and Space Sciences, University of California, Los Angeles, Los Angeles, California 90095-1567 (United States); Di Iorio, Tatiana [ENEA, UTMEA-TER, Rome (Italy); Liberati, Fabrizio [Opto Service SrL, Campagnano di Roma (RM) (Italy); Tarchi, Fabio; Dami, Michele; Olivieri, Monica; Pompei, Carlo [Selex ES, Campi Bisenzio (Italy); Mugnuolo, Raffaele [Italian Space Agency, ASI, Spatial Geodesy Center, Matera (Italy)

    2015-09-15

    The SPectral IMager (SPIM) facility is a laboratory visible infrared spectrometer developed to support space borne observations of rocky bodies of the solar system. Currently, this laboratory setup is used to support the DAWN mission, which is in its journey towards the asteroid 1-Ceres, and to support the 2018 Exo-Mars mission in the spectral investigation of the Martian subsurface. The main part of this setup is an imaging spectrometer that is a spare of the DAWN visible infrared spectrometer. The spectrometer has been assembled and calibrated at Selex ES and then installed in the facility developed at the INAF-IAPS laboratory in Rome. The goal of SPIM is to collect data to build spectral libraries for the interpretation of the space borne and in situ hyperspectral measurements of planetary materials. Given its very high spatial resolution combined with the imaging capability, this instrument can also help in the detailed study of minerals and rocks. In this paper, the instrument setup is first described, and then a series of test measurements, aimed to the characterization of the main subsystems, are reported. In particular, laboratory tests have been performed concerning (i) the radiation sources, (ii) the reference targets, and (iii) linearity of detector response; the instrumental imaging artifacts have also been investigated.

  14. The spectral imaging facility: Setup characterization

    International Nuclear Information System (INIS)

    The SPectral IMager (SPIM) facility is a laboratory visible infrared spectrometer developed to support space borne observations of rocky bodies of the solar system. Currently, this laboratory setup is used to support the DAWN mission, which is in its journey towards the asteroid 1-Ceres, and to support the 2018 Exo-Mars mission in the spectral investigation of the Martian subsurface. The main part of this setup is an imaging spectrometer that is a spare of the DAWN visible infrared spectrometer. The spectrometer has been assembled and calibrated at Selex ES and then installed in the facility developed at the INAF-IAPS laboratory in Rome. The goal of SPIM is to collect data to build spectral libraries for the interpretation of the space borne and in situ hyperspectral measurements of planetary materials. Given its very high spatial resolution combined with the imaging capability, this instrument can also help in the detailed study of minerals and rocks. In this paper, the instrument setup is first described, and then a series of test measurements, aimed to the characterization of the main subsystems, are reported. In particular, laboratory tests have been performed concerning (i) the radiation sources, (ii) the reference targets, and (iii) linearity of detector response; the instrumental imaging artifacts have also been investigated

  15. The spectral imaging facility: Setup characterization

    Science.gov (United States)

    De Angelis, Simone; Ammannito, Eleonora; Di Iorio, Tatiana; De Sanctis, Maria Cristina; Manzari, Paola Olga; Liberati, Fabrizio; Tarchi, Fabio; Dami, Michele; Olivieri, Monica; Pompei, Carlo; Mugnuolo, Raffaele

    2015-09-01

    The SPectral IMager (SPIM) facility is a laboratory visible infrared spectrometer developed to support space borne observations of rocky bodies of the solar system. Currently, this laboratory setup is used to support the DAWN mission, which is in its journey towards the asteroid 1-Ceres, and to support the 2018 Exo-Mars mission in the spectral investigation of the Martian subsurface. The main part of this setup is an imaging spectrometer that is a spare of the DAWN visible infrared spectrometer. The spectrometer has been assembled and calibrated at Selex ES and then installed in the facility developed at the INAF-IAPS laboratory in Rome. The goal of SPIM is to collect data to build spectral libraries for the interpretation of the space borne and in situ hyperspectral measurements of planetary materials. Given its very high spatial resolution combined with the imaging capability, this instrument can also help in the detailed study of minerals and rocks. In this paper, the instrument setup is first described, and then a series of test measurements, aimed to the characterization of the main subsystems, are reported. In particular, laboratory tests have been performed concerning (i) the radiation sources, (ii) the reference targets, and (iii) linearity of detector response; the instrumental imaging artifacts have also been investigated.

  16. Directional reflectance characterization facility and measurement methodology

    Science.gov (United States)

    McGuckin, B. T.; Haner, D. A.; Menzies, R. T.; Esproles, C.; Brothers, A. M.

    1996-08-01

    A precision reflectance characterization facility, constructed specifically for the measurement of the bidirectional reflectance properties of Spectralon panels planned for use as in-flight calibrators on the NASA Multiangle Imaging Spectroradiometer (MISR) instrument is described. The incident linearly polarized radiation is provided at three laser wavelengths: 442, 632.8, and 859.9 nm. Each beam is collimated when incident on the Spectralon. The illuminated area of the panel is viewed with a silicon photodetector that revolves around the panel (360 ) on a 30-cm boom extending from a common rotational axis. The reflected radiance detector signal is ratioed with the signal from a reference detector to minimize the effect of amplitude instabilities in the laser sources. This and other measures adopted to reduce noise have resulted in a bidirectional reflection function (BRF) calibration facility with a measurement precision with regard to a BRF measurement of 0.002 at the 1 confidence level. The Spectralon test piece panel is held in a computer-controlled three-axis rotational assembly capable of a full 360 rotation in the horizontal plane and 90 in the vertical. The angular positioning system has repeatability and resolution of 0.001 . Design details and an outline of the measurement methodology are presented.

  17. Standard Guide for Preparing Characterization Plans for Decommissioning Nuclear Facilities

    CERN Document Server

    American Society for Testing and Materials. Philadelphia

    2009-01-01

    1.1 This standard guide applies to developing nuclear facility characterization plans to define the type, magnitude, location, and extent of radiological and chemical contamination within the facility to allow decommissioning planning. This guide amplifies guidance regarding facility characterization indicated in ASTM Standard E 1281 on Nuclear Facility Decommissioning Plans. This guide does not address the methodology necessary to release a facility or site for unconditional use. This guide specifically addresses: 1.1.1 the data quality objective for characterization as an initial step in decommissioning planning. 1.1.2 sampling methods, 1.1.3 the logic involved (statistical design) to ensure adequate characterization for decommissioning purposes; and 1.1.4 essential documentation of the characterization information. 1.2 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate saf...

  18. Characterization of the 309 fuel examination facility

    Energy Technology Data Exchange (ETDEWEB)

    Greenhalgh, W.O.; Cornwell, B.C.

    1997-07-09

    This document identifies radiological, chemical and physical conditions inside the Fuel Examination Facility. It is located inside the Plutonium Recycle Test Reactor containment structure (309 Building.) The facility was a hot cell used for examination of PRTR fuel and equipment during the 1960`s. Located inside the cell is a PRTR shim rod assembly, reported are radiological conditions of the sample. The conditions were assessed as part of overall 309 Building transition.

  19. Radiological Characterization and Final Facility Status Report Tritium Research Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    Garcia, T.B.; Gorman, T.P.

    1996-08-01

    This document contains the specific radiological characterization information on Building 968, the Tritium Research Laboratory (TRL) Complex and Facility. We performed the characterization as outlined in its Radiological Characterization Plan. The Radiological Characterization and Final Facility Status Report (RC&FFSR) provides historic background information on each laboratory within the TRL complex as related to its original and present radiological condition. Along with the work outlined in the Radiological Characterization Plan (RCP), we performed a Radiological Soils Characterization, Radiological and Chemical Characterization of the Waste Water Hold-up System including all drains, and a Radiological Characterization of the Building 968 roof ventilation system. These characterizations will provide the basis for the Sandia National Laboratory, California (SNL/CA) Site Termination Survey .Plan, when appropriate.

  20. Characterization Plan for the Old Hydrofracture Facility

    Energy Technology Data Exchange (ETDEWEB)

    Francis, C.W.

    1999-01-01

    US Department of Energy (DOE) facilities are required to comply fully with all federal and state regulations. In response to this requirement, the Oak Ridge National Laboratory (ORNL) has established the remedial action program, to provide comprehensive management of areas where past research, development, and waste management activities have been conducted and have resulted in residual contamination of facilities or the environment. One of the objectives of this program is to define the extent of contamination at these sites. The intent is to document the known environmental characteristics of the sites and identify the additional actions, such as sampling, analytical measurements, and modeling, necessary to confirm contamination and the possible migration of contaminants from the sites. One of these sites is the Old Hydrofracture Facility (OHF). The OHF was used for the permanent disposal of liquid radioactive waste in impermeable shale formations at depths ranging from about 230 to 300 m (750 to 1000 ft), from 1964 to 1979. The liquid waste was blended into a pumpable grout by mixing it with cement and special clays used to immobilize radionuclides against groundwater transport. This report summarizes the results of several studies at ORNL that have measured the concentration of radionuclides and, to some extent, concentrations of hazardous chemicals in the sediment of the impoundment, as well as the concentrations in soils and groundwater near the facility. The report addresses only the contamination of and the potential releases to the environment that might result from the facility per se and makes not attempt to address potential releases that might result from permanent disposal of wastes (i.e., the grout sheets) during its operation. Outlined in the report are the additional actions needed to obtain the information required to confirm the extent of contamination within the facility. The major efforts include the measurement of radionuclides and potentially

  1. Beam Characterization at the Neutron Radiography Facility

    Energy Technology Data Exchange (ETDEWEB)

    Sarah Morgan; Jeffrey King

    2013-01-01

    The quality of a neutron imaging beam directly impacts the quality of radiographic images produced using that beam. Fully characterizing a neutron beam, including determination of the beam’s effective length-to-diameter ratio, neutron flux profile, energy spectrum, image quality, and beam divergence, is vital for producing quality radiographic images. This project characterized the east neutron imaging beamline at the Idaho National Laboratory Neutron Radiography Reactor (NRAD). The experiments which measured the beam’s effective length-to-diameter ratio and image quality are based on American Society for Testing and Materials (ASTM) standards. An analysis of the image produced by a calibrated phantom measured the beam divergence. The energy spectrum measurements consist of a series of foil irradiations using a selection of activation foils, compared to the results produced by a Monte Carlo n-Particle (MCNP) model of the beamline. Improvement of the existing NRAD MCNP beamline model includes validation of the model’s energy spectrum and the development of enhanced image simulation methods. The image simulation methods predict the radiographic image of an object based on the foil reaction rate data obtained by placing a model of the object in front of the image plane in an MCNP beamline model.

  2. Preliminary safety analysis report for the Waste Characterization Facility

    International Nuclear Information System (INIS)

    This safety analysis report outlines the safety concerns associated with the Waste Characterization Facility located in the Radioactive Waste Management Complex at the Idaho National Engineering Laboratory. The three main objectives of the report are to: define and document a safety basis for the Waste Characterization Facility activities; demonstrate how the activities will be carried out to adequately protect the workers, public, and environment; and provide a basis for review and acceptance of the identified risk that the managers, operators, and owners will assume. 142 refs., 38 figs., 39 tabs

  3. Characterization of effluent water qualities from satellite membrane bioreactor facilities.

    Science.gov (United States)

    Hirani, Zakir M; Bukhari, Zia; Oppenheimer, Joan; Jjemba, Patrick; LeChevallier, Mark W; Jacangelo, Joseph G

    2013-09-15

    Membrane bioreactors (MBRs) are often a preferred treatment technology for satellite water recycling facilities since they produce consistent effluent water quality with a small footprint and require little or no supervision. While the water quality produced from centralized MBRs has been widely reported, there is no study in the literature addressing the effluent quality from a broad range of satellite facilities. Thus, a study was conducted to characterize effluent water qualities produced by satellite MBRs with respect to organic, inorganic, physical and microbial parameters. Results from sampling 38 satellite MBR facilities across the U.S. demonstrated that 90% of these facilities produced nitrified (NH4-N <0.4 mg/L-N) effluents that have low organic carbon (TOC <8.1 mg/L), turbidities of <0.7 NTU, total coliform bacterial concentrations <100 CFU/100 mL and indigenous MS-2 bacteriophage concentrations <21 PFU/100 mL. Multiple sampling events from selected satellite facilities demonstrated process capability to consistently produce effluent with low concentrations of ammonia, TOC and turbidity. UV-254 transmittance values varied substantially during multiple sampling events indicating a need for attention in designing downstream UV disinfection systems. Although enteroviruses, rotaviruses and hepatitis A viruses (HAV) were absent in all samples, adenoviruses were detected in effluents of all nine MBR facilities sampled. The presence of Giardia cysts in filtrate samples of two of nine MBR facilities sampled demonstrated the need for an appropriate disinfection process at these facilities. PMID:23871258

  4. Subsidence characterization and modeling for engineered facilities in Arizona, USA

    Science.gov (United States)

    Rucker, M. L.; Fergason, K. C.; Panda, B. B.

    2015-11-01

    Several engineered facilities located on deep alluvial basins in southern Arizona, including flood retention structures (FRS) and a coal ash disposal facility, have been impacted by up to as much as 1.8 m of differential land subsidence and associated earth fissuring. Compressible basin alluvium depths are as deep as about 300 m, and historic groundwater level declines due to pumping range from 60 to more than 100 m at these facilities. Addressing earth fissure-inducing ground strain has required alluvium modulus characterization to support finite element modeling. The authors have developed Percolation Theory-based methodologies to use effective stress and generalized geo-material types to estimate alluvium modulus as a function of alluvium lithology, depth and groundwater level. Alluvial material modulus behavior may be characterized as high modulus gravel-dominated, low modulus sand-dominated, or very low modulus fines-dominated (silts and clays) alluvium. Applied at specific aquifer stress points, such as significant pumping wells, this parameter characterization and quantification facilitates subsidence magnitude modeling at its' sources. Modeled subsidence is then propagated over time across the basin from the source(s) using a time delay exponential decay function similar to the soil mechanics consolidation coefficient, only applied laterally. This approach has expanded subsidence modeling capabilities on scales of engineered facilities of less than 2 to more than 15 km.

  5. Human health risk characterization of petroleum coke calcining facility emissions.

    Science.gov (United States)

    Singh, Davinderjit; Johnson, Giffe T; Harbison, Raymond D

    2015-12-01

    Calcining processes including handling and storage of raw petroleum coke may result in Particulate Matter (PM) and gaseous emissions. Concerns have been raised over the potential association between particulate and aerosol pollution and adverse respiratory health effects including decrements in lung function. This risk characterization evaluated the exposure concentrations of ambient air pollutants including PM10 and gaseous pollutants from a petroleum coke calciner facility. The ambient air pollutant levels were collected through monitors installed at multiple locations in the vicinity of the facility. The measured and modeled particulate levels in ambient air from the calciner facility were compared to standards protective of public health. The results indicated that exposure levels were, on occasions at sites farther from the facility, higher than the public health limit of 150 μg/m(3) 24-h average for PM10. However, the carbon fraction demonstrated that the contribution from the calciner facility was de minimis. Exposure levels of the modeled SO2, CO, NOx and PM10 concentrations were also below public health air quality standards. These results demonstrate that emissions from calcining processes involving petroleum coke, at facilities that are well controlled, are below regulatory standards and are not expected to produce a public health risk. PMID:26520182

  6. Human health risk characterization of petroleum coke calcining facility emissions.

    Science.gov (United States)

    Singh, Davinderjit; Johnson, Giffe T; Harbison, Raymond D

    2015-12-01

    Calcining processes including handling and storage of raw petroleum coke may result in Particulate Matter (PM) and gaseous emissions. Concerns have been raised over the potential association between particulate and aerosol pollution and adverse respiratory health effects including decrements in lung function. This risk characterization evaluated the exposure concentrations of ambient air pollutants including PM10 and gaseous pollutants from a petroleum coke calciner facility. The ambient air pollutant levels were collected through monitors installed at multiple locations in the vicinity of the facility. The measured and modeled particulate levels in ambient air from the calciner facility were compared to standards protective of public health. The results indicated that exposure levels were, on occasions at sites farther from the facility, higher than the public health limit of 150 μg/m(3) 24-h average for PM10. However, the carbon fraction demonstrated that the contribution from the calciner facility was de minimis. Exposure levels of the modeled SO2, CO, NOx and PM10 concentrations were also below public health air quality standards. These results demonstrate that emissions from calcining processes involving petroleum coke, at facilities that are well controlled, are below regulatory standards and are not expected to produce a public health risk.

  7. Laser-based characterization and decontamination of contaminated facilities

    International Nuclear Information System (INIS)

    This study examines the application of laser ablation to the characterization and decontamination of painted and unpainted concrete and metal surfaces that are typical of many facilities within the US Department of Energy complex. The utility of this promising technology is reviewed and the essential requirements for efficient ablation extracted. Recent data obtained on the ablation of painted steel surfaces and concrete are presented. The affects of beam irradiance, ablation speed and efficiency, and characteristics of the aerosol effluent are discussed. Characterization of the ablated components of the surface offers the ability of concurrent determination of the level of contamination. This concept can be applied online where the ablation endpoint can be determined. A conceptual system for the characterization and decontamination of surfaces is proposed

  8. Odor characterization from barns and slurry treatment facilities at a commercial swine facility in South Korea

    Science.gov (United States)

    Jo, Sang-Hee; Kim, Ki-Hyun; Jeon, Byong-Hun; Lee, Min-Hee; Kim, Yong-Hyun; Kim, Bo-Won; Cho, Sung-Back; Hwang, Ok-Hwa; Bhattacharya, Satya Sundar

    2015-10-01

    In this study, emission characteristics of major odorants in pig confinement facilities were investigated through comparative analysis between odorant composition and odor intensity. Odorant samples in ambient air were collected from five different paired sampling sites: (1) in- and outside of windowless pig barn, (2) in- and outside of open pig barn, (3) before/after slurry treatment (via liquid fertilization), (4) before/after composting, and (5) two reference background sites on a pig confinement facility. A total of 47 compounds consisting of key offensive odorants (such as reduced sulfur and volatile organic compounds) were measured from each selected site. When the results are compared in terms of odor intensity, a list of odorants (sulfur compounds, volatile fatty acids, phenols, and indoles) were generally seen at enhanced levels on most sites. In two types of pig barn facilities (windowless ('W') and open ('O')), butyric and valeric acid were the predominant species. The removal efficiency of odorants was quite different between the two slurry treatment approaches of composting and liquid fertilization. Although the efficiencies of odor removal in the former were not sufficient, that of the latter was fairly significant in terms of odor intensity. However, some odorants like hydrogen sulfide, methanethiol, p-cresol, and butyric acid were still retained above the odor threshold level. Accordingly, odorant emissions from animal housing facilities can be characterized most effectively by key odorants such as volatile fatty acids and reduced sulfur species.

  9. Characterizing and Controlling Beam Losses at the LANSCE Facility

    Energy Technology Data Exchange (ETDEWEB)

    Rybarcyk, Lawrence J. [Los Alamos National Laboratory

    2012-09-12

    The Los Alamos Neutron Science Center (LANSCE) currently provides 100-MeV H{sup +} and 800-MeV H{sup -} beams to several user facilities that have distinct beam requirements, e.g. intensity, micropulse pattern, duty factor, etc. Minimizing beam loss is critical to achieving good performance and reliable operation, but can be challenging in the context of simultaneous multi-beam delivery. This presentation will discuss various aspects related to the observation, characterization and minimization of beam loss associated with normal production beam operations in the linac.

  10. Defense Waste Processing Facility (DWPF) startup test program: Glass characterization

    International Nuclear Information System (INIS)

    Liquid high-level nuclear waste will be immobilized at the Savannah River Site (SRS) by vitrification in borosilicate glass. The glass will be processed in the Defense Waste Processing Facility (DWPF) and poured into stainless steel canisters for eventual geologic disposal. Six simulated glass compositions will be processed in the DWPF during initial startup. The glass in 86 of the first 106 full sized canisters will be sampled and characterized. Extensive glass characterization will determine the following: (1) sampling frequency for radioactive operation, (2) verification of the compositionally dependent process-product models, (3) verification of melter mixing, (4) representativeness of the glass from the canister throat sampler, and (5) homogeneity of the canister glass

  11. Characterization report for Building 301 Hot Cell Facility

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-07-01

    During the period from October, 1997, through March, 1998, ANL-E Health Physics conducted a pre-D and D characterization of Building 301, referred to as the Hot Cell Facility. While primary emphasis was placed on radiological evaluation, the presence of non-nuclear hazardous and toxic material was also included in the scope of the characterization. This is one of the early buildings on the ANL-E site, and was heavily used in the 1950`s and 1960`s for various nuclear reaction and reactor design studies. Some degree of cleanup and contamination fixation was done in the 1970`s, so that the building could be used with a minimum of risk of personnel contamination. Work records are largely nonexistent for the early history of the building, so that any assumptions about extent and type of contamination had to be kept very open in the survey planning process. The primary contaminant was found to be painted-over Cs-137 embedded in the concrete floors, although a variety of other nuclides consistent with the work said to have been performed were found in smaller quantities. Due to leaks and drips through the floor, a relatively modest amount of soil contamination was found in the service trench under the building, not penetrating deeply. Two contaminated, disconnected drain lines leaving the building could not be traced by site records, and remain a problem for remediation. The D and D Characterization Plan was fulfilled.

  12. Facile chemical synthesis and structure characterization of copper molybdate nanoparticles

    Science.gov (United States)

    Rahimi-Nasrabadi, Mehdi; Pourmortazavi, Seied Mahdi; Khalilian-Shalamzari, Morteza

    2015-03-01

    Experimental parameters of a synthesis route were optimized by Taguchi robust design for the facile and controllable synthesis of copper molybdate nanoparticles. CuMoO4 nanoparticles were synthesized by chemical precipitation followed by hydrothermal process. Effects of different parameters of synthesis procedure, i.e. concentrations of both reagents, copper feeding flow rate and temperature of reactor on the particle size of prepared copper molybdate nanoparticles were investigated. The results of statistical optimization revealed that the size of copper molybdate particles is dependent on the procedure variables involving copper concentrations, flow rate and temperature of the reactor; while, molybdate concentration has a no considerable role in determining the size of CuMoO4 particles. Based on the results obtained by statistical optimization process, the nanoparticles of copper molybdate were prepared and then their structure and chemical composition were characterized by various techniques, i.e. SEM, TEM, XRD, EDX, FT-IR, UV-Vis and photoluminescence spectroscopy.

  13. (Low-level waste disposal facility siting and site characterization)

    Energy Technology Data Exchange (ETDEWEB)

    Mezga, L.J.; Ketelle, R.H.; Pin, F.G.; Van Hoesen, S.D.

    1985-10-25

    A US team consisting of representatives of Oak Ridge National Laboratory (ORNL), Savannah River Plant (SRP), Savannah river Laboratory (SRL), and the Department of Energy Office of Defense Waste and Byproducts Management participated in the fourth meeting held under the US/French Radioactive Waste Management Agreement between the US Department of Energy and the Commissariat a l'Energie Atomique. This meeting, held at Agence Nationale pour les Gestion des Dechets Radioactifs' (ANDRA's) Headquarters in Paris, was a detailed, technical topical workshop focusing on Low-Level Waste Disposal Facility Siting and Site Characterization.'' The meeting also included a visit to the Centre de la Manche waste management facility operated by ANDRA to discuss and observe the French approach to low-level waste management. The final day of the meeting was spent at the offices of Societe Generale pour les Techniques Nouvelles (SGN) discussing potential areas of future cooperation and exchange. 20 figs.

  14. Characterization of the Old Hydrofracture Facility (OHF) impoundment

    International Nuclear Information System (INIS)

    A characterization study was conducted on the Old Hydrofracture Facility Pond, at Oak Ridge National Laboratory to provide information necessary for its proper disposition. This impoundment was constructed in 1963 to provide a containment basin for radioactive grout in the event of an emergency spill from the Hydrofracture Facility. The impoundment is rectangular and measures about 30 by 6 m at the bottom. Water in the impoundment overlies about 0.3 m of sediment waste. The pond sediment was sampled and analyzed to determine whether it would classify as a hazardous waste under regulatory definitions promulgated in accordance with the Resource Conservation and Recovery Act (RCRA). Chemical analyses indicate that the sediment/waste does not contain hazardous chemical constituents above levels permitted by RCRA regulations. The sediment was found to contain an estimated radioactivity inventory of about 260 Ci, consisting primarily of 137Cs (60 Ci), 90Sr (190 Ci), 60Co (0.3 Ci), and 238U (0.3 Ci). The impoundment is excavated in clay soil and weathered sedimentary rock of the Conasauga Group. Four wells for monitoring the groundwater were constructed around the perimeter of the impoundment to depths ranging from 5.8 to 7.9 m. Sampling and analyses of the groundwater have been completed for the winter and spring seasons (1985) and will be continued for at least two more quarters to account for possible natural seasonal variation in groundwater quality. At the end of that time, a determination as to the effect of the impoundment on the groundwater quality will be made. Analyses from the first two quarters indicate that radioactivity (gross beta resulting from 90Sr and tritium) of the groundwater exceeds limits allowed by RCRA regulations. Low levels (0.0001 mg/L) of polychlorinated biphenyls were also detected in the groundwater

  15. Wastewater characterization of IPEN facilities - a preliminary study

    Energy Technology Data Exchange (ETDEWEB)

    Monteiro, Lucilena R.; Goncalves, Cristina; Terazan, Wagner R.; Cotrim, Marycel E.B.; Pires, Maria Aparecida F., E-mail: lrmonteiro@ipen.b [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

    2011-07-01

    As part of IPEN's Environmental Monitoring Program, wastewater sample collection and analysis was implemented on a daily basis. CQMA- Centro de Quimica e Meio Ambiente was responsible for the determination of total, fixed and volatile solids, pH, metals (as Al, Sb, Ba, Cd, Pb, Co, Cu, Cr, Hg, Mo, Ni, Ag, Na, Zn, Ca, Mg, Be, Sn, Li, K, Sr, Ti and V), semimetals (As, B, Se and Si) and anions (such as chloride, nitrate, sulfate and fluoride). The results were compared to the legal values established by the Sao Paulo State regulation 8,468/76, which defines the maximum permitted values for most of the studied substances in wastewater, aiming its releasing in public wastewater treatment system. The evaluation of this parameters concentration on Ipen's effluent implies that 50% of the wastewater corresponds to organic matter due to the sanitary load and inorganic macro elements, mainly as sodium, potassium, calcium. The only parameter not found in accordance with Brazilian legislation was pH in four out of the one hundred and seven samples collected throughout 2009 (2.8% of the samples analyzed). This preliminary study showed the effluents generated at Ipen's facility is characterized by the presence of organic matter and macro elements, commonly found in sanitary wastewater and it is in compliance with Sao Paulo regulations. (author)

  16. D ampersand D Characterization of the 232-F Old Tritium Facility at the Savannah River Site

    International Nuclear Information System (INIS)

    The 232-F ''Old Tritium Facility'' operated in the 1950s as the first tritium production facility at the Savannah River Site (SRS). In 1957, the 232-F operation ceased with tritium production turned over to a larger, technologically improved facility at SRS. The 232-F Facility was abandoned in 1958 and the process areas have remained contaminated with radiological, hazardous and mixed constituents. Decontamination and decommissioning (D ampersand D) of the 232-F Facility is scheduled to occur in the years 1995-1996. This paper presents the D ampersand D characterization efforts for the 232-F Facility

  17. Shroud boundary condition characterization experiments at the Radiant Heat Facility.

    Energy Technology Data Exchange (ETDEWEB)

    Suo-Anttila, Jill Marie; Nakos, James Thomas; Gill, Walter

    2004-10-01

    A series of experiments was performed to better characterize the boundary conditions from an inconel heat source ('shroud') painted with Pyromark black paint. Quantifying uncertainties in this type of experimental setup is crucial to providing information for comparisons with code predictions. The characterization of this boundary condition has applications in many scenarios related to fire simulation experiments performed at Sandia National Laboratories Radiant Heat Facility (RHF). Four phases of experiments were performed. Phase 1 results showed that a nominal 1000 C shroud temperature is repeatable to about 2 C. Repeatability of temperatures at individual points on the shroud show that temperatures do not vary more than 10 C from experiment to experiment. This variation results in a 6% difference in heat flux to a target 4 inches away. IR camera images showed the shroud was not at a uniform temperature, although the control temperature was constant to about {+-}2 C during a test. These images showed that a circular shaped, flat shroud with its edges supported by an insulated plate has a temperature distribution with higher temperatures at the edges and lower temperatures in the center. Differences between the center and edge temperatures were up to 75 C. Phase 3 results showed that thermocouple (TC) bias errors are affected by coupling with the surrounding environment. The magnitude of TC error depends on the environment facing the TC. Phase 4 results were used to estimate correction factors for specific applications (40 and 63-mil diameter, ungrounded junction, mineral insulated, metal-sheathed TCs facing a cold surface). Correction factors of about 3.0-4.5% are recommended for 40 mil diameter TCs and 5.5-7.0% for 63 mil diameter TCs. When mounted on the cold side of the shroud, TCs read lower than the 'true' shroud temperature, and the TC reads high when on the hot side. An alternate method uses the average of a cold side and hot side TC of

  18. 111-B Metal Examination Facility Concrete Tanks Characterization Plan

    International Nuclear Information System (INIS)

    The 111-B Metal Examination Facility was a single-story, wood frame 'L'-shaped building built on a concrete floor slab. The facility served as a fuel failure inspection facility. Irradiated fuel pieces were stored and examined in two below grade concrete storage tanks filled with water. The tanks have been filled with grout to stabilize the contamination they contained, and overall dimensions are 5 ft 9 in. (1.5 m 22.8 cm ) wide, 9 ft 1 in. (2.7 m 2.54 cm ) deep, and 10 ft 8 in. (3.0 m 20.32 cm) long, and are estimated to weigh 39 tons. The tanks were used to store and examine failed fuel rods, using water as a radiation shield. The tanks were lined with stainless steel; however, drawings show the liner has been removed from at least one tank (south tank) and was partially filled with grout. The south tank was used to contain the Sample Storage Facility, a multi-level metal storage rack for failed nuclear fuel rods (shown in drawings H-1-2889 and -2890). Both tanks were completely grouted sometime before decontamination and demolition (D ampersand D) of the above ground facility in 1984. The 111-B Metal Examination Facility contained two concrete tanks located below floor level for storage and examination of failed fuel. The tanks were filled with concrete as part of decommissioning the facility prior to 1983 (see Appendix A for description of previous work). Funding for removal and disposal of the tanks ran out before they could be properly disposed

  19. Preoperational baseline and site characterization report for the Environmental Restoration Disposal Facility: Volume 1. Revision 1

    International Nuclear Information System (INIS)

    This site characterization report provides the results of the field data collection activities for the Environmental Restoration Disposal Facility site. Information gathered on the geology, hydrology, ecology, chemistry, and cultural resources of the area is presented. The Environmental Restoration Disposal Facility is located at the Hanford Site in Richland, Washington

  20. Preliminary siting characterization Salt Disposition Facility - Site B

    International Nuclear Information System (INIS)

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

  1. Preliminary siting characterization Salt Disposition Facility - Site B

    Energy Technology Data Exchange (ETDEWEB)

    Wyatt, D.

    2000-01-04

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

  2. Characterization of groundwater flow for near surface disposal facilities

    International Nuclear Information System (INIS)

    The main objective of this report is to provide a description of the site investigation techniques and modelling approaches that can be used to characterise the flow of subsurface water at near surface disposal facilities in relation to the various development stages of the repositories. As one of the main goals of defining groundwater flow is to establish the possible contaminant migration, certain aspects related to groundwater transport are also described. Secondary objectives are to discuss the implications of various groundwater conditions with regard to the performance of the isolation systems

  3. Characterization and dispersion modeling of odors from a piggery facility.

    Science.gov (United States)

    Karageorgos, Petros; Latos, Manolis; Mpasiakos, Christos; Chalarakis, Elefterios; Dimitrakakis, Emmanuel; Daskalakis, Charis; Psillakis, Elefteria; Lazaridis, Mihalis; Kalogerakis, Nicolas

    2010-01-01

    Piggeries are known for their nuisance odors, creating problems for workers and nearby residents. Chemical substances that contribute to these odors include sulfurous organic compounds, hydrogen sulfide, phenols and indoles, ammonia, volatile amines, and volatile fatty acids. In this work, daily mean concentrations of ammonia (NH3) and hydrogen sulfide (H2S) were measured by hand-held devices. Measurements were taken in several places within the facility (farrowing to finishing rooms). Hydrogen sulfide concentration was found to be 40 to 50 times higher than the human odor threshold value in the nursery and fattening room, resulting in strong nuisance odors. Ammonia concentrations ranged from 2 to 18 mL m(-3) and also contributed to the total odor nuisance. Emission data from various chambers of the pig farm were used with the dispersion model AERMOD to determine the odor nuisance caused due to the presence of H2S and NH3 to receptors at various distances from the facility. Because just a few seconds of exposure can cause an odor nuisance, a "peak-to-mean" ratio was used to predict the maximum odor concentrations. Several scenarios were examined using the modified AERMOD program, taking into account the complex terrain around the pig farm.

  4. Performance Characterization of the Production Facility Prototype Helium Flow System

    Energy Technology Data Exchange (ETDEWEB)

    Woloshun, Keith Albert [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Dale, Gregory E. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Dalmas, Dale Allen [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Romero, Frank Patrick [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2015-12-16

    The roots blower in use at ANL for in-beam experiments and also at LANL for flow tests was sized for 12 mm diameter disks and significantly less beam heating. Currently, the disks are 29 mm in diameter, with a 12 mm FWHM Gaussian beam spot at 42 MeV and 2.86 μA on each side of the target, 5.72 μA total. The target design itself is reported elsewhere. With the increased beam heating, the helium flow requirement increased so that a larger blower was need for a mass flow rate of 400 g/s at 2.76 MPa (400 psig). An Aerzen GM 12.4 blower was selected, and is currently being installed at the LANL facility for target and component flow testing. This report describes this blower/motor/pressure vessel package and the status of the facility preparations. Blower performance (mass flow rate as a function of loop pressure drop) was measured at 4 blower speeds. Results are reported below.

  5. Characterization of a neutron imaging setup at the INES facility

    International Nuclear Information System (INIS)

    The Italian Neutron Experimental Station (INES) located at the ISIS pulsed neutron source (Didcot, United Kingdom) provides a thermal neutron beam mainly used for diffraction analysis. A neutron transmission imaging system was also developed for beam monitoring and for aligning the sample under investigation. Although the time-of-flight neutron diffraction is a consolidated technique, the neutron imaging setup is not yet completely characterized and optimized. In this paper the performance for neutron radiography and tomography at INES of two scintillator screens read out by two different commercial CCD cameras is compared in terms of linearity, signal-to-noise ratio, effective dynamic range and spatial resolution. In addition, the results of neutron radiographies and a tomography of metal alloy test structures are presented to better characterize the INES imaging capabilities of metal artifacts in the cultural heritage field. -- Highlights: A full characterization of the present INES imaging set-up was carried out. Two CCD cameras and two scintillators (ZnS/6LiF) of different thicknesses were tested. Linearity, effective dynamic range and spatial resolution were determined. Radiographies of steep wedges were performed using the highest dynamic range setup. Tomography of a bronze cube was performed using the best spatial resolution setup

  6. Characterization of a neutron imaging setup at the INES facility

    Energy Technology Data Exchange (ETDEWEB)

    Durisi, E.A., E-mail: elisabettaalessandra.durisi@unito.it [Università di Torino, Dipartimento di Fisica, Via Pietro Giuria 1, 10125 Torino (Italy); Istituto Nazionale di Fisica Nucleare—Sezione di Torino, Via Pietro Giuria 1, 10125 Torino (Italy); Visca, L. [Università di Torino, Dipartimento di Fisica, Via Pietro Giuria 1, 10125 Torino (Italy); Istituto Nazionale di Fisica Nucleare—Sezione di Torino, Via Pietro Giuria 1, 10125 Torino (Italy); Albertin, F.; Brancaccio, R. [Istituto Nazionale di Fisica Nucleare—Sezione di Torino, Via Pietro Giuria 1, 10125 Torino (Italy); Corsi, J. [Università di Torino, Dipartimento di Fisica, Via Pietro Giuria 1, 10125 Torino (Italy); Istituto Nazionale di Fisica Nucleare—Sezione di Torino, Via Pietro Giuria 1, 10125 Torino (Italy); Dughera, G. [Istituto Nazionale di Fisica Nucleare—Sezione di Torino, Via Pietro Giuria 1, 10125 Torino (Italy); Ferrarese, W. [Università di Torino, Dipartimento di Fisica, Via Pietro Giuria 1, 10125 Torino (Italy); Istituto Nazionale di Fisica Nucleare—Sezione di Torino, Via Pietro Giuria 1, 10125 Torino (Italy); Giovagnoli, A.; Grassi, N. [Fondazione Centro per la Conservazione ed il Restauro dei Beni Culturali “La Venaria Reale”, Piazza della Repubblica, 10078 Venaria Reale, Torino (Italy); Grazzi, F. [Consiglio Nazionale delle Ricerche, Istituto dei Sistemi Complessi, Via Madonna del Piano 10, 50019 Sesto Fiorentino, Firenze (Italy); Lo Giudice, A.; Mila, G. [Università di Torino, Dipartimento di Fisica, Via Pietro Giuria 1, 10125 Torino (Italy); Istituto Nazionale di Fisica Nucleare—Sezione di Torino, Via Pietro Giuria 1, 10125 Torino (Italy); and others

    2013-10-21

    The Italian Neutron Experimental Station (INES) located at the ISIS pulsed neutron source (Didcot, United Kingdom) provides a thermal neutron beam mainly used for diffraction analysis. A neutron transmission imaging system was also developed for beam monitoring and for aligning the sample under investigation. Although the time-of-flight neutron diffraction is a consolidated technique, the neutron imaging setup is not yet completely characterized and optimized. In this paper the performance for neutron radiography and tomography at INES of two scintillator screens read out by two different commercial CCD cameras is compared in terms of linearity, signal-to-noise ratio, effective dynamic range and spatial resolution. In addition, the results of neutron radiographies and a tomography of metal alloy test structures are presented to better characterize the INES imaging capabilities of metal artifacts in the cultural heritage field. -- Highlights: A full characterization of the present INES imaging set-up was carried out. Two CCD cameras and two scintillators (ZnS/{sup 6}LiF) of different thicknesses were tested. Linearity, effective dynamic range and spatial resolution were determined. Radiographies of steep wedges were performed using the highest dynamic range setup. Tomography of a bronze cube was performed using the best spatial resolution setup.

  7. HEROICA: A fast screening facility for the characterization of germanium detectors

    Energy Technology Data Exchange (ETDEWEB)

    Andreotti, Erica [Universität Tübingen, Auf der Morgenstelle 14, 72076 Tübingen (Germany); Collaboration: GERDA Collaboration

    2013-08-08

    In the course of 2012, a facility for the fast screening of germanium detectors called HEROICA (Hades Experimental Research Of Intrinsic Crystal Appliances) has been installed at the HADES underground laboratory in the premises of the Belgian Nuclear Research Centre SCK•CEN, in Mol (Belgium). The facility allows performing a complete characterization of the critical germanium detectors' operational parameters with a rate of about two detectors per week.

  8. Characterization of emergency preparedness at DOE contractor facilities

    International Nuclear Information System (INIS)

    A study of emergency preparedness capabilities at DOE facilities was initiated following the incident at the Three Mile Island (TMI) Nuclear Power Station. It was designed to parallel but expand on a study on emergency preparedness instrumentation that was conducted in 1970 by Pacific Northwest Laboratory. The 1970 survey findings led to the publication of four reports on performance criteria for radiological emergency instrumentation. Three of these reports - BNWL-1635 (Selby et al. 1972), BNWL-1742 (Anderson et al. 1974) and BNWL-1857 (Andersen et al. 1976) - addressed the criteria for emergency instrumentation at reactors, mixed oxide fuel fabrication plants, and fuel reprocessing plants, respectively. The fourth report, BNWL-1991 (Bramson et al. 1976), addressed evaluation testing and calibration methodology for these instruments. This report is presented in three parts. Part One is a review of the BNWL documents to determine whether they are applicable to state-of-the-art instrument capabilities. The Appendix to Part One provides a comparison between the instrument performance criteria established in BNWL-1991 to applicable American National Standards Institute (ANSI) standards for portable survey and contamination meters, installed radiation and area monitors, effluent monitors, calibration techniques, criticality detection systems, alarm systems, and direct reading dosimeters. Part Two compares the 1970 survey results with the 1980 survey results to identify trends in emergency preparedness. Part Three is a discussion of the results of the 1980 emergency preparedness survey and the supporting data for each of the 15 modules. 8 references

  9. CHARACTERIZATION OF CORE SAMPLE COLLECTED FROM THE SALTSTONE DISPOSAL FACILITY

    Energy Technology Data Exchange (ETDEWEB)

    Cozzi, A.; Duncan, A.

    2010-01-28

    During the month of September 2008, grout core samples were collected from the Saltstone Disposal Facility, Vault 4, cell E. This grout was placed during processing campaigns in December 2007 from Deliquification, Dissolution and Adjustment Batch 2 salt solution. The 4QCY07 Waste Acceptance Criteria sample collected on 11/16/07 represents the salt solution in the core samples. Core samples were retrieved to initiate the historical database of properties of emplaced Saltstone and to demonstrate the correlation between field collected and laboratory prepared samples. Three samples were collected from three different locations. Samples were collected using a two-inch diameter concrete coring bit. In April 2009, the core samples were removed from the evacuated sample container, inspected, transferred to PVC containers, and backfilled with nitrogen. Samples furthest from the wall were the most intact cylindrically shaped cored samples. The shade of the core samples darkened as the depth of coring increased. Based on the visual inspection, sample 3-3 was selected for all subsequent analysis. The density and porosity of the Vault 4 core sample, 1.90 g/cm{sup 3} and 59.90% respectively, were comparable to values achieved for laboratory prepared samples. X-ray diffraction analysis identified phases consistent with the expectations for hydrated Saltstone. Microscopic analysis revealed morphology features characteristic of cementitious materials with fly ash and calcium silicate hydrate gel. When taken together, the results of the density, porosity, x-ray diffraction analysis and microscopic analysis support the conclusion that the Vault 4, Cell E core sample is representative of the expected waste form.

  10. Nerva fuel nondestructive evaluation and characterization equipment and facilities

    Science.gov (United States)

    Caputo, Anthony J.

    1993-01-01

    Nuclear Thermal Propulsion (NTP) is one of the technologies that the Space Exploration Initiative (SEI) has identified as essential for a manned mission to Mars. A base or prior work is available upon which to build in the development of nuclear rockets. From 1955 to 1973, the U.S Atomic Energy Commission (AEC) sponsored development and testing of a nuclear rocket engine under Project Rover. The rocket engine, called the Nuclear Engine for Rocket Vehicle Application (NERVA), used a graphite fuel element incorporating coated particle fuel. Much of the NERVA development and manufacturing work was performed at the Oak Ridge Y-12 Plant. This paper gives a general review of that work in the area of nondestructive evaluation and characterization. Emphasis is placed on two key characteristics: uranium content and distribution and thickness profile of metal carbide coatings deposited in the gas passage holes.

  11. Characterization of decontamination and decommissioning wastes expected from the major processing facilities in the 200 Areas

    Energy Technology Data Exchange (ETDEWEB)

    Amato, L.C.; Franklin, J.D.; Hyre, R.A.; Lowy, R.M.; Millar, J.S.; Pottmeyer, J.A. [Los Alamos Technical Associates, Kennewick, WA (United States); Duncan, D.R. [Westinghouse Hanford Co., Richland, WA (United States)

    1994-08-01

    This study was intended to characterize and estimate the amounts of equipment and other materials that are candidates for removal and subsequent processing in a solid waste facility when the major processing and handling facilities in the 200 Areas of the Hanford Site are decontaminated and decommissioned. The facilities in this study were selected based on processing history and on the magnitude of the estimated decommissioning cost cited in the Surplus Facilities Program Plan; Fiscal Year 1993 (Winship and Hughes 1992). The facilities chosen for this study include B Plant (221-B), T Plant (221-T), U Plant (221-U), the Uranium Trioxide (UO{sub 3}) Plant (224-U and 224-UA), the Reduction Oxidation (REDOX) or S Plant (202-S), the Plutonium Concentration Facility for B Plant (224-B), and the Concentration Facility for the Plutonium Finishing Plant (PFP) and REDOX (233-S). This information is required to support planning activities for current and future solid waste treatment, storage, and disposal operations and facilities.

  12. Characterization of Iraq's remote nuclear facilities for decommissioning and waste management - 59167

    International Nuclear Information System (INIS)

    The Government of Iraq (GOI) has undertaken efforts to decommission and dismantle former nuclear facilities. The GOI has only preliminary information on some of the former nuclear facilities. This paper will highlight the challenges involved in conducting inspections of the outlying former nuclear facilities in Iraq and present a brief summary of the results of those inspections. The facilities discussed in this paper are located at various sites throughout Iraq, from locations close to Baghdad to those in the north and far western desert areas. Some of the facilities, such as those at the Al Tuwaitha Nuclear Research Center have been visited and characterized. Other facilities, including the following, have not been visited or thoroughly characterized. - Al Jesira, Uranium feed stock production facility; - Adaya, Burial location for contaminated equipment; - Djerf al Naddah, Spent fuel storage facility; - Rashdiya, Centrifuge development center; - Al Qa'im, Uranium (yellowcake) production facility. The visits were conducted to develop an inventory of the buildings/structures that need to be included in decommissioning/dismantlement efforts. The number of buildings, type of construction, size and general condition of the buildings were noted. In addition, attempts were made to determine contamination levels on surfaces, equipment, rubble, etc. This information will be used to support the Iraqi decommissioning and dismantlement project. Because the facilities are scattered throughout the country of Iraq, significant planning and coordination was required to ensure personnel security. Teams consisting of individuals from the Iraqi Ministry of Science and Technology (MoST) and Americans were under military escort when traveling to and visiting the sites. Because of the security issues, time on the ground at each site was limited. This paper will highlight the challenges involved in conducting the inspections of the outlying former nuclear facilities In Iraq and

  13. THACO, a Test Facility for Characterizing the Noise Performance of Active Antenna Arrays

    CERN Document Server

    Woestenburg, E E M; Ruiter, M; Ivashina, M V; Witvers, R H

    2011-01-01

    This paper discusses an outdoor test facility for the noise characterization of active antenna arrays, using measurement results of array noise temperatures in the order of 50 K for a number of small aperture arrays. The measurement results are obtained by a Y-factor method with hot and a cold noise sources, with an absorber at room temperature as the hot load and the cold sky as the cold load. The effect of shielding the arrays by the test facility, with respect to noise and RFI from the environment, will also be discussed.

  14. Characterization and optimization of the R A-6 s on-line neutron radiography facility

    International Nuclear Information System (INIS)

    With the objective of characterizing and optimizing the radiation-field filters behavior in the beam of the R A-6 on-line Neutron Radiography facility, some improvements have been done to the facility devices.We studied the camera sensibility, the best camera acquisition software configuration, the best depth of field, we increased the system tuning efficiency.We also studied the linearity of the facility vs the reactor core neutron fluence and finally we constructed a device that ensure the repeatability of the measurements.The main parameters chosen to represent the best radiation-field set-up are the thermal neutron flux and dose in the position of the camera.Finally, a camera shield optimization haven been done in function of its position

  15. Neutron Beam Characterization for Neutron Radiography Facility at the Thai Research Reactor TRR-1/M1

    International Nuclear Information System (INIS)

    The aim of this research is to characterize the present status of neutron beam coming out from the reactor core of Thai Research Reactor TRR-1/M1 through neutron radiography facility. In this study, the neutron beam profiles at different positions along the beam exit were recorded using digital imaging devices. In addition, thin foil activation technique, with and without cadmium cover, was employed to determine thermal neutron flux and Cd ratio. An acrylic step wedge was exposed to neutron at different time. In parallel to image construction, neutron detection was carried out using a BF3 gas-filled detector. Then, the image intensities at particular thicknesses were normalized by neutron counts from the BF3 detector to determine relative neutron intensity. The obtained information of neutron beam characterization will be useful not only for monitoring the present status of neutron radiography facility but also for determining the optimum exposure conditions for particular samples in the future.

  16. Final characterization report for the non-process areas of the 233-S Plutonium Concentration Facility

    International Nuclear Information System (INIS)

    This report addresses the 233-S Plutonium Concentration Facility characterization survey data collected from January 21, 1997 through February 3, 1997. The characterization activities evaluated the radiological status and identified the hazardous materials locations. The scope of this report is limited to the nonprocess areas in the facility, which include the special work permit (SWP) change room, toilet, equipment room, electrical cubicle, control room, and pipe gallery. A portion of the roof (excluding the roof over the process hood and viewing room) was also included. Information in this report will be used to identify waste streams, provide specific chemical and radiological data to aid in planning decontamination and demolition activities, and allow proper disposal of the demolition debris, as required by the Comprehensive Environmental Response, Compensation, and Liability Act of 1980

  17. Characterization and reclamation assessment for the central shops diesel storage facility at Savannah River Site

    Energy Technology Data Exchange (ETDEWEB)

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

    1994-12-31

    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 cleanups. Using innovative approaches, the central Shops Diesel Storage Facility at the Savannah River Site (SRS) was characterized to determine the extent of subsurface diesel fuel contamination. Effective bioremediation techniques for cleaning up of the contaminant plume were established.

  18. Characterization and adjustment of the neutron radiography facility of the RP-10 nuclear reactor

    International Nuclear Information System (INIS)

    The main aim of this work was to characterize and adjust the neutron radiography facility of the RP-10 nuclear reactor, and therefore be able to offer with this technique services to the industry and research centers in general. This technique will be complemented with others such as x-rays and gamma radiography. First, the shielding capacity of the facility was analyzed, proving that it complies with the radiological safety requirements established by the radiological safety code. Then gamma filtration tests were conducted in order to implement the direct method for image formation, optical density curves were built according to the thickness of the gamma filter, the type of film and the type of irradiation. Also, the indirect method for image formation was implemented for two types of converters: indium and dysprosium. Growth curves for optical density were also made according to contact time between converter-film, for different types of films. The resolution of the facility was also analyzed using two methods: Klasens (1946) and Harms (1986). Harms method came closer to the resolution of the human eye when compared to the Klasens method. Finally, the application fields of neutron radiography are presented, including those conducted at the neutron radiography facility of the RP-10 nuclear reactor. With this work, the RP-10 neutron radiography facility is ready to offer inspection and research services

  19. Redesign, construction and characterization of the new neutron radiography facility of the RA-6

    International Nuclear Information System (INIS)

    Neutron radiography is a non-destructive test in which it is registered an image of the attenuation experienced by a collimated neutron beam while it passes through a sample. The image is generated by using a neutron-sensitive screen. The applications of this technique are wide, some of them include: services to industries, study of explosives, study of pieces belonging to cultural heritage and studies of the distribution of hydrogen. The actual neutron radiography facility is placed in the RA-6 reactor at the Centro Atomico Bariloche. Due to the reactor's nucleus change and the subsequent power raise, it has been necessary to redesign the facility. During the last year the pieces that constitute it had been designed and built. In April 2012 the facility has been mounted. The system employed is of on-line neutron radiographies. The maximum area of study is of 20 cm x 20 cm. The images obtained are registered by a CCD camera, whose maximum resolution is of 2776 x 2074 pixels and 65536 gray levels. In this work the initial steps towards characterization of the facility are presented, these include neutron fluxes and dose rates levels determinations. Also, in order to evaluate the functionality, images of several objects have been taken, as the one shown in Fig. 7. The results obtained reveal the good performance of the facility and its wide potential (author)

  20. A methodological approach for the geostatistical characterization of radiological contaminations in nuclear facilities

    International Nuclear Information System (INIS)

    The decommissioning of nuclear sites represents huge industrial and financial challenges. At the end of process equipment dismantling, the complete decontamination of nuclear facilities requires the radiological assessment of residual activity levels of the building structures (waste zoning). From this point of view, the set up of an appropriate evaluation methodology is of prime importance. The developed radiological characterization is divided into three steps: historical and functional analysis, radiation mapping and in-depth investigations. Combined with relevant data analysis and processing tools, this methodology aims at optimizing the investigation costs and the radiological waste volumes. In a former CEA nuclear facility, a substantial radiation survey was performed at the beginning of the thesis in order to try and test the methodology. The relevance of geo-statistics was also illustrated: exploratory data analysis, spatial structure analysis through the variogram, mapping, risk analysis results, iso-factorial modeling to take the structuring of extreme values into account. Destructive concrete samples are then integrated to complete the characterization in addition to radiation data through the geostatistical multivariate approach. Finally, waste segregation results from the risk of exceeding given radiological thresholds. An inventory of the spatial structures of radiological contaminations in nuclear facilities is provided within the geostatistical framework. It leads to sampling recommendations in order to improve the overall characterization strategy and optimize the investigation costs. (author)

  1. Data Sharing Report Characterization of Isotope Row Facilities Oak Ridge National Laboratory Oak Ridge TN

    Energy Technology Data Exchange (ETDEWEB)

    Weaver, Phyllis C

    2013-12-12

    The U.S. Department of Energy (DOE) Oak Ridge Office of Environmental Management (EM-OR) requested that Oak Ridge Associated Universities (ORAU), working under the Oak Ridge Institute for Science and Education (ORISE) contract, provide technical and independent waste management planning support using funds provided by the American Recovery and Reinvestment Act (ARRA). Specifically, DOE EM-OR requested ORAU to plan and implement a survey approach, focused on characterizing the Isotope Row Facilities located at the Oak Ridge National Laboratory (ORNL) for future determination of an appropriate disposition pathway for building debris and systems, should the buildings be demolished. The characterization effort was designed to identify and quantify radiological and chemical contamination associated with building structures and process systems. The Isotope Row Facilities discussed in this report include Bldgs. 3030, 3031, 3032, 3033, 3033A, 3034, 3036, 3093, and 3118, and are located in the northeast quadrant of the main ORNL campus area, between Hillside and Central Avenues. Construction of the isotope production facilities was initiated in the late 1940s, with the exception of Bldgs. 3033A and 3118, which were enclosed in the early 1960s. The Isotope Row facilities were intended for the purpose of light industrial use for the processing, assemblage, and storage of radionuclides used for a variety of applications (ORNL 1952 and ORAU 2013). The Isotope Row Facilities provided laboratory and support services as part of the Isotopes Production and Distribution Program until 1989 when DOE mandated their shutdown (ORNL 1990). These facilities performed diverse research and developmental experiments in support of isotopes production. As a result of the many years of operations, various projects, and final cessation of operations, production was followed by inclusion into the surveillance and maintenance (S&M) project for eventual decontamination and decommissioning (D&D). The

  2. Design and characterization of an irradiation facility with real-time monitoring

    Science.gov (United States)

    Braisted, Jonathan David

    Radiation causes performance degradation in electronics by inducing atomic displacements and ionizations. While radiation hardened components are available, non-radiation hardened electronics can be preferable because they are generally more compact, require less power, and less expensive than radiation tolerant equivalents. It is therefore important to characterize the performance of electronics, both hardened and non-hardened, to prevent costly system or mission failures. Radiation effects tests for electronics generally involve a handful of step irradiations, leading to poorly-resolved data. Step irradiations also introduce uncertainties in electrical measurements due to temperature annealing effects. This effect may be intensified if the time between exposure and measurement is significant. Induced activity in test samples also complicates data collection of step irradiated test samples. The University of Texas at Austin operates a 1.1 MW Mark II TRIGA research reactor. An in-core irradiation facility for radiation effects testing with a real-time monitoring capability has been designed for the UT TRIGA reactor. The facility is larger than any currently available non-central location in a TRIGA, supporting testing of larger electronic components as well as other in-core irradiation applications requiring significant volume such as isotope production or neutron transmutation doping of silicon. This dissertation describes the design and testing of the large in-core irradiation facility and the experimental campaign developed to test the real-time monitoring capability. This irradiation campaign was performed to test the real-time monitoring capability at various reactor power levels. The device chosen for characterization was the 4N25 general-purpose optocoupler. The current transfer ratio, which is an important electrical parameter for optocouplers, was calculated as a function of neutron fluence and gamma dose from the real-time voltage measurements. The

  3. Geotechnical characterization of the North Ramp of the Exploratory Studies Facility: Yucca Mountain Site Characterization Project. Volume 1, Data summary

    International Nuclear Information System (INIS)

    This report presents the results of geological and geotechnical characterization of the Miocene volcanic tuff rocks of the Timber Mountain and Paintbrush groups that the tunnel boring machine will encounter during excavation of the Exploratory Studies Facility (ESF) North Ramp. The is being constructed by the DOE as part of the Yucca Mountain Project site characterization activities. The purpose of these activities is to evaluate the feasibility of locating a potential high-level nuclear waste repository on lands adjacent to the Nevada Test Site, Nye County, Nevada. This report was prepared as part of the Soil and Rock Properties Studies in accordance with the 8.3.1.14.2 Study Plan. This report is volume 1 of the data summary

  4. Geotechnical characterization of the North Ramp of the Exploratory Studies Facility: Yucca Mountain Site Characterization Project. Volume 1, Data summary

    Energy Technology Data Exchange (ETDEWEB)

    Brechtel, C.E.; Lin, Ming; Martin, E. [Agapito Associates, Inc., Grand Junction, CO (United States); Kessel, D.S. [Sandia National Labs., Albuquerque, NM (United States)

    1995-05-01

    This report presents the results of geological and geotechnical characterization of the Miocene volcanic tuff rocks of the Timber Mountain and Paintbrush groups that the tunnel boring machine will encounter during excavation of the Exploratory Studies Facility (ESF) North Ramp. The is being constructed by the DOE as part of the Yucca Mountain Project site characterization activities. The purpose of these activities is to evaluate the feasibility of locating a potential high-level nuclear waste repository on lands adjacent to the Nevada Test Site, Nye County, Nevada. This report was prepared as part of the Soil and Rock Properties Studies in accordance with the 8.3.1.14.2 Study Plan. This report is volume 1 of the data summary.

  5. Site characterization report for the Old Hydrofracture Facility at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    Several Old Hydrofracture Facility (OHF) structures (i.e., Building 7852, the bulk storage bins, the pump house, water tank T-5, and pump P-3) are surplus facilities at Oak Ridge National Laboratory (ORNL) slated for decontamination and decommissioning (D and D). OHF was constructed in 1963 to allow experimentation and operations with an integrated solids storage, handling, mixing, and grout injection facility. It was shut down in 1980 and transferred to ORNL's Surveillance and Maintenance Program. The hydrofracture process was a unique disposal method that involved injecting waste materials mixed with grout and additives under pumping pressures of 2,000 psi or greater into a deep, low-permeability shale formation. The injected slurry spread along fractures and bedding planes for hundreds of feet from the injection points, forming thin grout sheets (often less than 1/8 in. thick). The grout ostensibly immobilized and solidified the liquid wastes. Site characterization activities were conducted in the winter and spring of 1994 to collect information necessary to plan the D and D of OHF structures. This site characterization report documents the results of the investigation of OHF D and D structures, presenting data from the field investigation and laboratory analyses in the form of a site description, as-built drawings, summary tables of radiological and chemical contaminant concentrations, and a waste volume estimate. 25 refs., 54 figs., 17 tabs

  6. Exploratory shaft facility: It`s role in the characterization of the Yucca Mountain site for a potential nuclear repository

    Energy Technology Data Exchange (ETDEWEB)

    Kalia, H.N.; Merson, T.J.

    1990-03-01

    The US Department of Energy is characterizing Yucca Mountain, Nevada, to assess its suitability as a potential site for the permanent disposal of high-level radioactive waste from nuclear power plants and defense related activities. The assessment activities include surface investigations, drill holes from the surface, and an underground facility for in situ characterization tests. This underground exploratory shaft facility is being designed to meet the criteria for characterizing the mountain as described in the Site Characterization Plan. 9 refs., 9 figs., 1 tab.

  7. Site characterization techniques used at a low-level waste shallow land burial field demonstration facility

    International Nuclear Information System (INIS)

    The Environmental Sciences Division of the Oak Ridge National Laboratory has been investigating improved shallow land burial technology for application in the humd eastern United States. As part of this effort, a field demonstration facility (Engineered Test Facility, or ETF) has been established in Solid Waste Storage Area 6 for purposes of investigatig the ability of two trench treatments (waste grouting prior to cover emplacement and waste isolation with trench liners) to prevent water-waste contact and thus minimize waste leaching. As part of the experimental plan, the ETF site has been characterized for purposes of constructing a hydrologic model. Site characterization is an extremely important component of the waste disposal site selection process; during these activities, potential problems, which might obviate the site from further consideration, may be found. This report describes the ETF site characterization program and identifies and, where appropriate, evaluates those tests that are of most value in model development. Specific areas covered include site geology, soils, and hydrology. Each of these areas is further divided into numerous subsections, making it easy for the reader to examine a single area of interest. Site characterization is a multidiscipliary endeavor with voluminous data, only portions of which are presented and analyzed here. The information in this report is similar to that which will be required of a low-level waste site developer in preparing a license application for a potential site in the humid East, (a discussion of licensing requirements is beyond its scope). Only data relevant to hydrologic model development are included, anticipating that many of these same characterization methods will be used at future disposal sites with similar water-related problems

  8. AVTA Federal Fleet PEV Readiness Data Logging and Characterization Study for NASA White Sands Test Facility

    Energy Technology Data Exchange (ETDEWEB)

    Stephen Schey; Jim Francfort

    2014-10-01

    This report focuses on the NASA White Sands Test Facility (WSTF) fleet to identify daily operational characteristics of select vehicles and report findings on vehicle and mission characterizations to support the successful introduction of plug-in electric vehicles (PEVs) into the agencies’ fleets. Individual observations of these selected vehicles provide the basis for recommendations related to electric vehicle adoption and whether a battery electric vehicle (BEV) or plug-in hybrid electric vehicle (PHEV) (collectively plug-in electric vehicles, or PEVs) can fulfill the mission requirements.

  9. Site Characterization Plan for the Old Hydrofracture Facility at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    The aboveground structures of the Old Hydrofracture Facility (OHF) at Oak Ridge National Laboratory (ORNL) are scheduled for decontamination and decommissioning (D ampersand D). This Site Characterization Plan presents the strategy and techniques to be used to characterize the OHF D ampersand D structures in support of D ampersand D planning, design, and implementation. OHF is located approximately 1 mile southwest of the main ORNL complex. From 1964 to 1979, OHF was used in the development and full-scale application of hydrofracture operations in which 969,000 gal of liquid low-level waste (LLLW) was mixed with grout and then injected under high pressure into a low-permeability shale formation approximately 1/6 mile underground

  10. Status of the TAMUTRAP facility and initial characterization of the RFQ cooler/buncher

    Energy Technology Data Exchange (ETDEWEB)

    Mehlman, M., E-mail: mehlmanmichael@tamu.edu; Shidling, P. D.; Burch, R.; Bennett, E.; Fenker, B.; Melconian, D. [Texas A& M University, Cyclotron Institute (United States)

    2015-11-15

    The Texas A&M University Penning Trap experiment (TAMUTRAP) is an upcoming ion trap facility that will be used to search for possible scalar currents in T = 2 superallowed pure Fermi decays (utilizing β-delayed proton emitters), which, if found, would be an indication of physics beyond the standard model. In addition, TAMUTRAP will provide a low-energy, point-like source of ions for various other applications at the Cyclotron Institute at Texas A&M University. The experiment is centered around a unique, compensated cylindrical Penning trap that employs a specially optimized length/radius ratio in the electrode structure that is not used by any other facility. The radioactive beam, provided by the Texas A&M University Re-accelerated Exotics (T-REX) program at the Cyclotron Institute, will be prepared for loading in the measurement trap via a specially designed Radio Frequency Quadrupole (RFQ) cooler/buncher. These proceedings will describe the current status of the TAMUTRAP facility, paying particular attention to the design and initial characterization of the RFQ cooler/buncher. Future plans will also be discussed.

  11. Characterization and adjustment of the neutron radiography facility of the RP-10 nuclear reactor

    CERN Document Server

    Ravello-R, Y R

    2001-01-01

    The main aim of this work was to characterize and adjust the neutron radiography facility of the RP-10 nuclear reactor, and therefore be able to offer with this technique services to the industry and research centers in general. This technique will be complemented with others such as x-rays and gamma radiography. First, the shielding capacity of the facility was analyzed, proving that it complies with the radiological safety requirements established by the radiological safety code. Then gamma filtration tests were conducted in order to implement the direct method for image formation, optical density curves were built according to the thickness of the gamma filter, the type of film and the type of irradiation. Also, the indirect method for image formation was implemented for two types of converters: indium and dysprosium. Growth curves for optical density were also made according to contact time between converter-film, for different types of films. The resolution of the facility was also analyzed using two met...

  12. A Laser Testing Facility for the Characterization of Silicon Strip Detectors

    Science.gov (United States)

    Phillips, Sarah

    2011-04-01

    Silicon strip detectors are used for high-precision tracking systems in particle physics experiments. During the 12 GeV upgrade to the accelerator at Jefferson Lab, a new spectrometer, CLAS12, will be built in Hall B. The University of New Hampshire is part of the collaboration designing and building CLAS12. Among the detector systems being developed for CLAS12 is a silicon vertex tracker that will be placed close to the target, providing excellent position resolution for vertex determination. It is vital to have the ability to perform quality assurance tests and to evaluate the performance of the individual silicon strip detectors before installation in CLAS12. UNH is designing and building a laser testing facility to perform this task. The design consists of an infrared laser system and a precision computer-controlled positioning system that scans the laser light on the detector. The detector signals are read out by a data acquisition system for analysis. The facility includes a cleanroom area and a dry storage containment system. The facility allows the characterization of the large number of detectors before the final assembly of the silicon vertex tracker.

  13. Using a university characterization facility to educate the public about microscopes: light microscopes to SEM

    Science.gov (United States)

    Healy, Nancy; Henderson, Walter

    2015-10-01

    The National Nanotechnology Infrastructure Network (NNIN)1is an integrated partnership of 14 universities across the US funded by NSF to support nanoscale researchers. The NNIN education office is located at the Institute of Electronics and Nanotechnology at the Georgia Institute of Technology. At Georgia Tech we offer programs that integrate the facility and its resources to educate the public about nanotechnology. One event that has proved highly successful involves using microscopes in our characterization suite to educate a diverse audience about a variety of imaging instruments. As part of the annual Atlanta Science Festival (ATLSF)2 we provided an event entitled: "What's all the Buzz about Nanotechnology?" which was open to the public and advertised through a variety of methods by the ATLSF. During the event, we provided hands-on demos, cleanroom tours, and activities with three of our microscopes in our recently opened Imaging and Characterization Facility: 1. Keyence VHX-600 Digital Microscope; 2. Hitachi SU823 FE-SEM; and 3. Hitachi TM 3000. During the two hour event we had approximately 150 visitors including many families with school-aged children. Visitors were invited to bring a sample for scanning with the TM-3000. This paper will discuss how to do such an event, lessons learned, and visitor survey results.

  14. A new laboratory-scale experimental facility for detailed aerothermal characterizations of volumetric absorbers

    Science.gov (United States)

    Gomez-Garcia, Fabrisio; Santiago, Sergio; Luque, Salvador; Romero, Manuel; Gonzalez-Aguilar, Jose

    2016-05-01

    This paper describes a new modular laboratory-scale experimental facility that was designed to conduct detailed aerothermal characterizations of volumetric absorbers for use in concentrating solar power plants. Absorbers are generally considered to be the element with the highest potential for efficiency gains in solar thermal energy systems. The configu-ration of volumetric absorbers enables concentrated solar radiation to penetrate deep into their solid structure, where it is progressively absorbed, prior to being transferred by convection to a working fluid flowing through the structure. Current design trends towards higher absorber outlet temperatures have led to the use of complex intricate geometries in novel ceramic and metallic elements to maximize the temperature deep inside the structure (thus reducing thermal emission losses at the front surface and increasing efficiency). Although numerical models simulate the conjugate heat transfer mechanisms along volumetric absorbers, they lack, in many cases, the accuracy that is required for precise aerothermal validations. The present work aims to aid this objective by the design, development, commissioning and operation of a new experimental facility which consists of a 7 kWe (1.2 kWth) high flux solar simulator, a radiation homogenizer, inlet and outlet collector modules and a working section that can accommodate volumetric absorbers up to 80 mm × 80 mm in cross-sectional area. Experimental measurements conducted in the facility include absorber solid temperature distributions along its depth, inlet and outlet air temperatures, air mass flow rate and pressure drop, incident radiative heat flux, and overall thermal efficiency. In addition, two windows allow for the direct visualization of the front and rear absorber surfaces, thus enabling full-coverage surface temperature measurements by thermal imaging cameras. This paper presents the results from the aerothermal characterization of a siliconized silicon

  15. Simulation of hydraulic disturbances caused by the underground rock characterization facility in Olkiluoto, Finland

    Science.gov (United States)

    Löfman, Jari; Mészáros, Ferenc

    A final repository for spent nuclear fuel is sought in Finland by Posiva (the company responsible for the construction and operation of the final nuclear-waste disposal facility in Finland, http://www.posiva.fi). A part of this project involves an underground rock characterization facility (ONKALO), which will consist of an 8,500 m long and 520 m deep system of tunnels, to be potentially extended with the drifts of the repository. The maximum hydraulic disturbance (water table drawdown, deep saline-water upconing and tunnel inflow) that might result from the construction and operation of the ONKALO facility were assessed by site-scale finite-element simulations. The drawdown was calculated by employing the free-surface approach. Tunnel inflows were obtained from the state of equilibrium, while the evolution of the salinity distribution was simulated using a time-dependent and coupled flow and salt transport model. The simulations showed that without engineering measures to limit inflow of groundwater into the ONKALO facility, the hydraulic disturbances would be significantly greater than with these measures implemented. Most of the inflow (330-1,100 L/min) would come from the conductive subhorizontal fracture zones intersected by the drifts. The water table could sink to a depth of about 200 m, and the depressed area could extend over the Olkiluoto Island. Groundwater salinity (expressed as total dissolved solids [TDS]) could locally rise from 22 g/L to over 50 g/L at the tunnel depth of 520 m. With tight grouting, the simulations showed that the depression in the water table can be confined to the immediate vicinity of the ONKALO, the maximum draw-down of the water table remained around 10 m, and the total inflow to the tunnels was about 20 L/min. Moreover, upconing of the saline water remained moderate.

  16. Characterization of seepage in the exploratory studies facility, Yucca Mountain, Nevada

    Science.gov (United States)

    Oliver, T.A.; Whelan, J.F.

    2006-01-01

    Following a 5-month period of above-average precipitation during the winter of 2004-2005, water was observed seeping into the South Ramp section of the Exploratory Studies Facility of the proposed repository for high-level radioactive waste at Yucca Mountain, Nevada. Samples of the seepage were collected and analyzed for major ions, trace metals, and delta deuterium and delta oxygen-18 values in an effort to characterize the water and assess the interaction of seepage with anthropogenic materials used in the construction of the proposed repository. As demonstrated by the changes in the chemistry of water dripping from a rock bolt, interaction of seepage with construction materials can alter solution chemistry and oxidation state.

  17. Preoperational baseline and site characterization report for the Environmental Restoration Disposal Facility

    International Nuclear Information System (INIS)

    This document Volume 2 in a two-volume series that comprise the site characterization report for the Environmental Restoration Disposal Facility. Volume 1 contains data interpretation and information supporting the conclusions in the main text. This document presents original data in support of Volume 1 of the report. The following types of data are presented: well construction reports; borehole logs; borehole geophysical data; well development and pump installation; survey reports; and preoperational baseline chemical data and aquifer test data. This does not represent the entire body of data available. Other types of information are archived at BHI Document Control. Five ground water monitoring wells were drilled at the Environmental Restoration Disposal Facility site to directly investigate site- specific hydrogeologic conditions. Well and borehole activity summaries are presented in Volume 1. Field borehole logs and geophysical data from the drilling are presented in this document. Well development and pump installation sheets are presented for the groundwater monitoring wells. Other data presented in this document include borehole geophysical logs from existing wells; chemical data from the sampling of soil, vegetation, and mammals from the ERDF to support the preoperational baseline; ERDF surface radiation surveys;a nd aquifer testing data for well 699-32-72B

  18. The pneumatic carrier facility in Dhruva reactor: commissioning, characterization and utilization

    International Nuclear Information System (INIS)

    The 100 MWt power Dhruva research reactor, BARC is provided with pneumatic carrier facility (PCF) to carry out R and D work using short-lived (seconds to minutes) radioisotopes in the fields like neutron activation analysis (NAA) and nuclear fission. The samples are kept inside a high density polypropylene capsule (rabbit), which is pneumatically sent to the irradiation position in the core and retrieved after a preset time of irradiation. After the irradiation, radioactivity assay is carried out using high resolution gamma ray spectrometry with HPGe detector coupled to PC based MCA. The availability of high neutron flux (∼ 5 x 10 13 cm-2s-1 at 50 MWt power) and shorter retrieval time (∼5 seconds) make it possible to measure short-lived isotopes with enhanced sensitivity. This report describes the salient features of this facility, characterization of the neutron spectrum at this irradiation position and its utilization. The PCF is being extensively utilized for analytical applications using NAA as well as nuclear fission studies. A brief description of analysis of some samples of geological, environmental and biological origin, nuclear materials as well as reference materials is included in this report. Protocol and check list for carrying out PCF irradiations and gamma spectrometric assay are also given at the end of the report. (author)

  19. HEROICA: a test facility for the characterization of BEGe detectors for the Gerda experiment

    Energy Technology Data Exchange (ETDEWEB)

    Falkenstein, Raphael [Eberhard Karls Universitaet Tuebingen (Germany); Collaboration: GERDA-Collaboration

    2013-07-01

    The Gerda experiment is designed to search for neutrinoless double beta (0νββ) decay of {sup 76}Ge. It uses bare, enriched Germanium diodes that are operated in liquid argon. Currently, Phase I is running at Laboratori Nazionali del Gran Sasso in Italy. For Phase II, ∝20 kg of Broad Energy Germanium (BEGe) detectors enriched in {sup 76}Ge at 86% level will be additionally deployed. These detectors allow for advanced pulse shape discrimination techniques, to suppress the background, which will be necessary to reach the goal of Phase II with a background index of 10{sup -3} cts/(keV.kg.yr) in the Region of Interest. The HEROICA project aims for acceptance tests and the characterization of the BEGe detectors. In this talk, the infrastructure of the Belgian HADES underground test facility, as well as the full test protocol for the characterization campaign of the enrBEGe detectors, is described. This test protocol includes the determination of important detector parameters, such as energy resolution, depletion voltage, dead-layer thickness and uniformity, active volume, as well as pulse shape discrimination parameters.

  20. HEROICA: a test facility for the characterization of BEGe detectors for the Gerda experiment

    International Nuclear Information System (INIS)

    The Gerda experiment is designed to search for neutrinoless double beta (0νββ) decay of 76Ge. It uses bare, enriched Germanium diodes that are operated in liquid argon. Currently, Phase I is running at Laboratori Nazionali del Gran Sasso in Italy. For Phase II, ∝20 kg of Broad Energy Germanium (BEGe) detectors enriched in 76Ge at 86% level will be additionally deployed. These detectors allow for advanced pulse shape discrimination techniques, to suppress the background, which will be necessary to reach the goal of Phase II with a background index of 10-3 cts/(keV.kg.yr) in the Region of Interest. The HEROICA project aims for acceptance tests and the characterization of the BEGe detectors. In this talk, the infrastructure of the Belgian HADES underground test facility, as well as the full test protocol for the characterization campaign of the enrBEGe detectors, is described. This test protocol includes the determination of important detector parameters, such as energy resolution, depletion voltage, dead-layer thickness and uniformity, active volume, as well as pulse shape discrimination parameters.

  1. Facile time-of-flight methods for characterizing pulsed superfluid helium droplet beams

    International Nuclear Information System (INIS)

    We present two facile time-of-flight (TOF) methods of detecting superfluid helium droplets and droplets with neutral dopants. Without an electron gun and with only a heated filament and pulsed electrodes, the electron impact ionization TOF mass spectrometer can resolve ionized helium clusters such as He2+ and He4+, which are signatures of superfluid helium droplets. Without ionizing any helium atoms, multiphoton non-resonant laser ionization of CCl4 doped in superfluid helium droplets at 266 nm generates complex cluster ions of dopant fragments with helium atoms, including (He)nC+, (He)nCl+, and (He)nCCl+. Using both methods, we have characterized our cryogenic pulsed valve—the Even-Lavie valve. We have observed a primary pulse with larger helium droplets traveling at a slower speed and a rebound pulse with smaller droplets at a faster speed. In addition, the pickup efficiency of dopant is higher for the primary pulse when the nozzle temperature is higher than 13 K, and the total time duration of the doped droplet pulse is only on the order of 20 μs. These results stress the importance of fast and easy characterization of the droplet beam for sensitive measurements such as electron diffraction of doped droplets

  2. Facile time-of-flight methods for characterizing pulsed superfluid helium droplet beams.

    Science.gov (United States)

    He, Yunteng; Zhang, Jie; Li, Yang; Freund, William M; Kong, Wei

    2015-08-01

    We present two facile time-of-flight (TOF) methods of detecting superfluid helium droplets and droplets with neutral dopants. Without an electron gun and with only a heated filament and pulsed electrodes, the electron impact ionization TOF mass spectrometer can resolve ionized helium clusters such as He2(+) and He4(+), which are signatures of superfluid helium droplets. Without ionizing any helium atoms, multiphoton non-resonant laser ionization of CCl4 doped in superfluid helium droplets at 266 nm generates complex cluster ions of dopant fragments with helium atoms, including (He)(n)C(+), (He)(n)Cl(+), and (He)(n)CCl(+). Using both methods, we have characterized our cryogenic pulsed valve—the Even-Lavie valve. We have observed a primary pulse with larger helium droplets traveling at a slower speed and a rebound pulse with smaller droplets at a faster speed. In addition, the pickup efficiency of dopant is higher for the primary pulse when the nozzle temperature is higher than 13 K, and the total time duration of the doped droplet pulse is only on the order of 20 μs. These results stress the importance of fast and easy characterization of the droplet beam for sensitive measurements such as electron diffraction of doped droplets. PMID:26329210

  3. Facile time-of-flight methods for characterizing pulsed superfluid helium droplet beams

    Energy Technology Data Exchange (ETDEWEB)

    He, Yunteng; Zhang, Jie; Li, Yang; Freund, William M.; Kong, Wei, E-mail: wei.kong@oregonstate.edu [Department of Chemistry, Oregon State University, Corvallis, Oregon 97331 (United States)

    2015-08-15

    We present two facile time-of-flight (TOF) methods of detecting superfluid helium droplets and droplets with neutral dopants. Without an electron gun and with only a heated filament and pulsed electrodes, the electron impact ionization TOF mass spectrometer can resolve ionized helium clusters such as He{sub 2}{sup +} and He{sub 4}{sup +}, which are signatures of superfluid helium droplets. Without ionizing any helium atoms, multiphoton non-resonant laser ionization of CCl{sub 4} doped in superfluid helium droplets at 266 nm generates complex cluster ions of dopant fragments with helium atoms, including (He){sub n}C{sup +}, (He){sub n}Cl{sup +}, and (He){sub n}CCl{sup +}. Using both methods, we have characterized our cryogenic pulsed valve—the Even-Lavie valve. We have observed a primary pulse with larger helium droplets traveling at a slower speed and a rebound pulse with smaller droplets at a faster speed. In addition, the pickup efficiency of dopant is higher for the primary pulse when the nozzle temperature is higher than 13 K, and the total time duration of the doped droplet pulse is only on the order of 20 μs. These results stress the importance of fast and easy characterization of the droplet beam for sensitive measurements such as electron diffraction of doped droplets.

  4. Guide for radiological characterization and measurements for decommissioning of US Department of Energy surplus facilities

    Energy Technology Data Exchange (ETDEWEB)

    Denahm, D. H.; Barnes, M. G.; Jaquish, R. E.; Corley, J. P.; Gilbert, R. O.; Hoenes, G. R.; Jamison, J. D.; McMurray, B. J.; Watson, E. C.

    1983-08-01

    This Guide describes the elements of radiological characterization at DOE excess facilities in preparation for, during, and subsequent to decommissioning operations. It is the intent of this Guide and accompanying appendices to provide the reader (user) with sufficient information to carry out that task with a minimum of confusion and to provide a uniform basis for evaluating site conditions and verifying that decommissioning operations are conducted according to a specific plan. Some areas of particular interest in this Guide are: the need to involve appropriate staff from the affected states in the early planning stages of decommissioning; the need for and suggested methods of radiological site characterization to complete a decommissioning project, including: historical surveys, environmental pathway analyses, statistical sampling design, and choosing appropriate instrumentation and measurements; the need for and emphasis on quality assurance, documentation and records retention; the establishment of a Design Objective approach to applying site-specific contamination limits based on the ALARA philosophy; the establishment of a ''de minimis'' or minimum dose level of concern for decommissioning operations based on existing standards, experience and ALARA considerations.

  5. Guide for radiological characterization and measurements for decommissioning of US Department of Energy surplus facilities

    International Nuclear Information System (INIS)

    This Guide describes the elements of radiological characterization at DOE excess facilities in preparation for, during, and subsequent to decommissioning operations. It is the intent of this Guide and accompanying appendices to provide the reader (user) with sufficient information to carry out that task with a minimum of confusion and to provide a uniform basis for evaluating site conditions and verifying that decommissioning operations are conducted according to a specific plan. Some areas of particular interest in this Guide are: the need to involve appropriate staff from the affected states in the early planning stages of decommissioning; the need for and suggested methods of radiological site characterization to complete a decommissioning project, including: historical surveys, environmental pathway analyses, statistical sampling design, and choosing appropriate instrumentation and measurements; the need for and emphasis on quality assurance, documentation and records retention; the establishment of a Design Objective approach to applying site-specific contamination limits based on the ALARA philosophy; the establishment of a ''de minimis'' or minimum dose level of concern for decommissioning operations based on existing standards, experience and ALARA considerations

  6. Characterization of the Old Hydrofracture Facility (OHF) waste tanks located at ORNL

    Energy Technology Data Exchange (ETDEWEB)

    Keller, J.M.; Giaquinto, J.M.; Meeks, A.M.

    1997-04-01

    The Old Hydrofracture Facility (OHF) is located in Melton Valley within Waste Area Grouping (WAG) 5 and includes five underground storage tanks (T1, T2, T3, T4, and T9) ranging from 13,000 to 25,000 gal. capacity. During the period of 1996--97 there was a major effort to re-sample and characterize the contents of these inactive waste tanks. The characterization data summarized in this report was needed to address waste processing options, examine concerns dealing with the performance assessment (PA) data for the Waste Isolation Pilot Plant (WIPP), evaluate the waste characteristics with respect to the waste acceptance criteria (WAC) for WIPP and Nevada Test Site (NTS), address criticality concerns, and to provide the data needed to meet DOT requirements for transporting the waste. This report discusses the analytical characterization data collected on both the supernatant and sludge samples taken from three different locations in each of the OHF tanks. The isotopic data presented in this report supports the position that fissile isotopes of uranium ({sup 233}U and {sup 235}U) do not satisfy the denature ratios required by the administrative controls stated in the ORNL LLLW waste acceptance criteria (WAC). The fissile isotope of plutonium ({sup 239}Pu and {sup 241}Pu) are diluted with thorium far above the WAC requirements. In general, the OHF sludge was found to be hazardous (RCRA) based on total metal content and the transuranic alpha activity was well above the 100 nCi/g limit for TRU waste. The characteristics of the OHF sludge relative to the WIPP WAC limits for fissile gram equivalent, plutonium equivalent activity, and thermal power from decay heat were estimated from the data in this report and found to be far below the upper boundary for any of the remote-handled transuranic waste (RH-TRU) requirements for disposal of the waste in WIPP.

  7. Characterization of the Old Hydrofracture Facility (OHF) waste tanks located at ORNL

    International Nuclear Information System (INIS)

    The Old Hydrofracture Facility (OHF) is located in Melton Valley within Waste Area Grouping (WAG) 5 and includes five underground storage tanks (T1, T2, T3, T4, and T9) ranging from 13,000 to 25,000 gal. capacity. During the period of 1996--97 there was a major effort to re-sample and characterize the contents of these inactive waste tanks. The characterization data summarized in this report was needed to address waste processing options, examine concerns dealing with the performance assessment (PA) data for the Waste Isolation Pilot Plant (WIPP), evaluate the waste characteristics with respect to the waste acceptance criteria (WAC) for WIPP and Nevada Test Site (NTS), address criticality concerns, and to provide the data needed to meet DOT requirements for transporting the waste. This report discusses the analytical characterization data collected on both the supernatant and sludge samples taken from three different locations in each of the OHF tanks. The isotopic data presented in this report supports the position that fissile isotopes of uranium (233U and 235U) do not satisfy the denature ratios required by the administrative controls stated in the ORNL LLLW waste acceptance criteria (WAC). The fissile isotope of plutonium (239Pu and 241Pu) are diluted with thorium far above the WAC requirements. In general, the OHF sludge was found to be hazardous (RCRA) based on total metal content and the transuranic alpha activity was well above the 100 nCi/g limit for TRU waste. The characteristics of the OHF sludge relative to the WIPP WAC limits for fissile gram equivalent, plutonium equivalent activity, and thermal power from decay heat were estimated from the data in this report and found to be far below the upper boundary for any of the remote-handled transuranic waste (RH-TRU) requirements for disposal of the waste in WIPP

  8. Facile synthesis and characterization of novel biodegradable amphiphilic block copolymers bearing pendant hydroxyl groups

    International Nuclear Information System (INIS)

    Novel amphiphilic block copolymers bearing pendant hydroxyl groups polylactide-b–poly(3,3-bis(Hydroxymethyl–triazolylmethyl) oxetane)-b–polylactide (PLA-b–PHMTYO-b–PLA) were synthesized via a facile and efficient method. First, the block copolymer intermediates polylactide-b–poly(3,3-Diazidomethyloxetane)-b–polylactide (PLA-b–PBAMO-b–PLA) were synthesized through ring-opening polymerization of lactide using PBAMO as a macroinitiator. Following “Click” reaction of PLA-b–PBAMO-b–PLA with propargyl alcohol provided the targeted amphiphilic block copolymers PLA-b–PHMTYO-b–PLA with pendant hydroxyl groups. The composition and structure of prepared copolymers were characterized by 1H nuclear magnetic resonance (1H NMR) spectroscopy, Fourier transform infrared (FT-IR) and gel permeation chromatography (GPC). The self-assembly behavior of the copolymers in water was investigated by transmission electron microscope (TEM), dynamic light scattering (DLS) and static light scattering (SLS). The results showed that the novel copolymers PLA-b–PHMTYO-b–PLA self-assembled into spherical micelles with diameters ranging from 100 nm to 200 nm in aqueous solution. These copolymers also exhibited low critical micellar concentrations (CMC: 6.9 × 10−4 mg/mL and 3.9 × 10−5 mg/mL, respectively). In addition, the in vitro cytotoxicity of these copolymers was determined in the presence of L929 cells. The results showed that the block copolymers PLA-b–PHMTYO-b–PLA exhibited better biocompatibility. Therefore, these well-defined copolymers are expected to find some applications in drug delivery or tissue engineering. - Highlights: • The method to synthesize PLA-b–PHMTYO-b–PLA is relatively facile and efficient. • PLA-b–PHMTYO-b–PLA self-assembles into spherical micelles with low CMC in water. • PLA-b–PHMTYO-b–PLA exhibits better biocompatibility and biodegradability

  9. Facile synthesis and characterization of novel biodegradable amphiphilic block copolymers bearing pendant hydroxyl groups

    Energy Technology Data Exchange (ETDEWEB)

    Hu, Gaicen; Fan, Xiaoshan; Xu, Bingcan; Zhang, Delong; Hu, Zhiguo, E-mail: zghu@htu.cn

    2014-10-01

    Novel amphiphilic block copolymers bearing pendant hydroxyl groups polylactide-b–poly(3,3-bis(Hydroxymethyl–triazolylmethyl) oxetane)-b–polylactide (PLA-b–PHMTYO-b–PLA) were synthesized via a facile and efficient method. First, the block copolymer intermediates polylactide-b–poly(3,3-Diazidomethyloxetane)-b–polylactide (PLA-b–PBAMO-b–PLA) were synthesized through ring-opening polymerization of lactide using PBAMO as a macroinitiator. Following “Click” reaction of PLA-b–PBAMO-b–PLA with propargyl alcohol provided the targeted amphiphilic block copolymers PLA-b–PHMTYO-b–PLA with pendant hydroxyl groups. The composition and structure of prepared copolymers were characterized by {sup 1}H nuclear magnetic resonance ({sup 1}H NMR) spectroscopy, Fourier transform infrared (FT-IR) and gel permeation chromatography (GPC). The self-assembly behavior of the copolymers in water was investigated by transmission electron microscope (TEM), dynamic light scattering (DLS) and static light scattering (SLS). The results showed that the novel copolymers PLA-b–PHMTYO-b–PLA self-assembled into spherical micelles with diameters ranging from 100 nm to 200 nm in aqueous solution. These copolymers also exhibited low critical micellar concentrations (CMC: 6.9 × 10{sup −4} mg/mL and 3.9 × 10{sup −5} mg/mL, respectively). In addition, the in vitro cytotoxicity of these copolymers was determined in the presence of L929 cells. The results showed that the block copolymers PLA-b–PHMTYO-b–PLA exhibited better biocompatibility. Therefore, these well-defined copolymers are expected to find some applications in drug delivery or tissue engineering. - Highlights: • The method to synthesize PLA-b–PHMTYO-b–PLA is relatively facile and efficient. • PLA-b–PHMTYO-b–PLA self-assembles into spherical micelles with low CMC in water. • PLA-b–PHMTYO-b–PLA exhibits better biocompatibility and biodegradability.

  10. Flow Characterization of a Detonation Gun Facility and First Coating Experiments

    Science.gov (United States)

    Henkes, C.; Olivier, H.

    2014-06-01

    A computer-controlled detonation gun based spraying device has been designed and tested to obtain particle velocities over 1200 m/s. The device is able to be operated in two modes based on different flow-physical principles. In one mode, the device functions like a conventional detonation gun in which the powder is accelerated in a blast wave. In the other mode, an extension of the facility with a nozzle uses the detonated gas for an intermittently operated shock tunnel process in which the particles are injected into and accelerated by a quasi-steady high enthalpy nozzle flow with high reservoir conditions. Presented are experimental results of the operation without nozzle in which the device generates moderate to high particle velocities in an intermittent process with a frequency of 5 Hz. A hydrogen/oxygen mixture and Cu and WC-Co (88/12) powders are used in the experiments. Operation performance and tube outflow are characterized by time-resolved Schlieren images and pressure measurements. The particle velocities in the outflow are obtained by laser Doppler anemometry. Different substrate/powder combinations (Al/Cu, Steel/Cu, Al/WC-Co, and Steel/WC-Co) have been investigated by light microscopy and measurements of microhardness.

  11. The external beam facility used to characterize corrosion products in metallic statuettes

    Energy Technology Data Exchange (ETDEWEB)

    Rizzutto, M.A. [Universidade de Sao Paulo, Instituto de Fisica, Rua do Matao Travessa R 187, 05508-900 Sao Paulo, SP (Brazil)]. E-mail: marcia.rizzutto@dfn.if.usp.br; Tabacniks, M.H. [Universidade de Sao Paulo, Instituto de Fisica, Rua do Matao Travessa R 187, 05508-900 Sao Paulo, SP (Brazil); Added, N. [Universidade de Sao Paulo, Instituto de Fisica, Rua do Matao Travessa R 187, 05508-900 Sao Paulo, SP (Brazil); Barbosa, M.D.L. [Universidade de Sao Paulo, Instituto de Fisica, Rua do Matao Travessa R 187, 05508-900 Sao Paulo, SP (Brazil); Curado, J.F. [Universidade de Sao Paulo, Instituto de Fisica, Rua do Matao Travessa R 187, 05508-900 Sao Paulo, SP (Brazil); Santos, W.A. [Universidade de Sao Paulo, Instituto de Fisica, Rua do Matao Travessa R 187, 05508-900 Sao Paulo, SP (Brazil); Lima, S.C. [Laboratorio de Conservacao e Restauracao, Museu de Arqueologia e Etnologia, Universidade de Sao Paulo, Av Prof. Almeida Prado, 1466, 05508-900 Sao Paulo, SP (Brazil); Melo, H.G. [Laboratorio de Eletroquimica e CorroSao, Departamento de Engenharia Quimica, Escola Politecnica, Universidade de Sao Paulo, Av. Luciano Gualberto, trav.3, n.380, 05508-900 Sao Paulo, SP (Brazil); Neiva, A.C. [Laboratorio de Eletroquimica e CorroSao, Departamento de Engenharia Quimica, Escola Politecnica, Universidade de Sao Paulo, Av. Luciano Gualberto, trav.3, n.380, 05508-900 Sao Paulo, SP (Brazil)

    2005-10-15

    To open new possibilities in nuclear applied physics research, mainly for the analysis of art objects in air, an external beam facility was installed at LAMFI (Laboratorio de Analise de Materiais por Feixes Ionicos) of University of Sao Paulo. PIXE measurements were made using an XR-100CR (Si-PIN) X-ray detector pointed to the sample mounted after an approximate 11 mm air path, hence with effective beam energy of 0.9 MeV. This setup was used to characterize the corrosion products of two ethnological metallic statuettes from the African collection of the Museum of Archaeology and Etnology. PIXE analysis of the corrosion free base of one statuette showed that Cu and Zn are the main components of the alloy, while Pb is present in smaller amount. The analysis of some corrosion products showed a Zn:Cu relationship higher than that of the base, evidencing selective corrosion. The main components of the other statuette were Cu and Pb, while S and Zn were found in smaller amounts.

  12. Facile synthesis and characterization of lanthanum (III) oxychloride nanoparticles using a natural polymeric matrix

    International Nuclear Information System (INIS)

    Plate-shape lanthanum oxychloride nanoparticles (LaOCl-NPs) were synthesized via a facile sol–gel method in gelatin media. The LaOCl-NPs were characterized by a number of techniques, including X-ray diffraction analysis (XRD), Fourier transform infrared spectroscopy (FTIR), Auger electron spectroscopy (AES), and high-magnification transmission electron microscopy (TEM). The LaOCl-NPs calcined at different temperatures exhibited a tetragonal structure. The influence of the calcination temperature on the morphology of LaOCl-NPs was also investigated. The TEM shows that the particles were grown in plate shape. The Auger result proved the purity of the final product. The results demonstrated that gelatin is an interesting material that can be used as a stabilizer in the sol–gel technique for preparing LaOCl-NPs. -- Highlights: ► LaOCl-NPs were synthesized using gelatin as a stabilizer via a simple sol-gel method. ► Gelatin was expanded during the calcinations and terminates the growth of LaOCl. ► The structure of the prepared nanoparticles were investigated. ► The results showed that, gelatin is good stabilizer to prepare uniform LaOCl nanoparticles.

  13. 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.

  14. Preoperational baseline and site characterization report for the Environmental Restoration Disposal Facility. Volume 1, Revision 2

    International Nuclear Information System (INIS)

    This document is the first in a two-volume series that comprise the site characterization report. Volume 1 contains data interpretation and information supporting the conclusions in the text (Appendices A through G). Volume 2 provides raw data. A site located between 200 East and 200 West Areas, in the central portion of the Hanford Site, was selected as the prime location for the ERDF. Modifications to the facility design minimize the footprint and have resulted in a significant reduction in the areal size. This change was initiated in part as a response to recommendations of the Hanford Future Site Uses Working Group to limit waste management activities to an exclusive zone within the squared-off boundary of the 200 Areas. Additionally, the reduction in size of the footprint was initiated to minimize impacts to ecology. The ERDF is designed for disposal of remediation wastes generated during the cleanup of Hanford Site and could be expanded to hold as much as 28 million yd3 (21.4 million m3) of solid waste

  15. Facile preparation and electrochemical characterization of cobalt oxide/multi-walled carbon nanotube composites for supercapacitors

    Science.gov (United States)

    Lang, Junwei; Yan, Xingbin; Xue, Qunji

    A series of cobalt oxide/multi-walled carbon nanotube (Co 3O 4/MWCNT) composites are successfully synthesized by a facile chemical co-precipitation method followed by a simple thermal treatment process. The morphology and structure of as-obtained composites are characterized by X-ray diffraction, scanning electron microscopy, and N 2-adsorption/desorption measurements, and the electrochemical properties are investigated by cyclic voltammetry (CV), galvanostatic charge/discharge and electrochemical impedance spectroscopy (EIS). For all Co 3O 4/MWCNT composites, MWCNTs are well dispersed in the loosely packed Co 3O 4 nanoparticles. Among them, the Co 3O 4-5%MWCNT composite exhibits the highest specific surface area of 137 m 2 g -1 and a mesoporous structure with a narrow distribution of pore size from 2 to 10 nm. Because of the synergistic effects coming from Co 3O 4 nanoparticles and MWCNTs, the electrochemical performances of pure Co 3O 4 material are significantly improved after adding MWCNTs. The Co 3O 4-5%MWCNT composite shows the largest specific capacitance of 418 F g -1 at a current density of 0.625 A g -1 in 2 M KOH electrolyte. Furthermore, this composite exhibits good cycling stability and lifetime. Therefore, based on the above investigation, such Co 3O 4/MWCNT composite could be a potential candidate for supercapacitors.

  16. CHARACTERIZATION OF A PRECIPITATE REACTOR FEED TANK (PRFT) SAMPLE FROM THE DEFENSE WASTE PROCESSING FACILITY (DWPF)

    Energy Technology Data Exchange (ETDEWEB)

    Crawford, C.; Bannochie, C.

    2014-05-12

    A sample of from the Defense Waste Processing Facility (DWPF) Precipitate Reactor Feed Tank (PRFT) was pulled and sent to the Savannah River National Laboratory (SRNL) in June of 2013. The PRFT in DWPF receives Actinide Removal Process (ARP)/ Monosodium Titanate (MST) material from the 512-S Facility via the 511-S Facility. This 2.2 L sample was to be used in small-scale DWPF chemical process cell testing in the Shielded Cells Facility of SRNL. A 1L sub-sample portion was characterized to determine the physical properties such as weight percent solids, density, particle size distribution and crystalline phase identification. Further chemical analysis of the PRFT filtrate and dissolved slurry included metals and anions as well as carbon and base analysis. This technical report describes the characterization and analysis of the PRFT sample from DWPF. At SRNL, the 2.2 L PRFT sample was composited from eleven separate samples received from DWPF. The visible solids were observed to be relatively quick settling which allowed for the rinsing of the original shipping vials with PRFT supernate on the same day as compositing. Most analyses were performed in triplicate except for particle size distribution (PSD), X-ray diffraction (XRD), Scanning Electron Microscopy (SEM) and thermogravimetric analysis (TGA). PRFT slurry samples were dissolved using a mixed HNO3/HF acid for subsequent Inductively Coupled Plasma Atomic Emission Spectroscopy (ICPAES) and Inductively Coupled Plasma Mass Spectroscopy (ICP-MS) analyses performed by SRNL Analytical Development (AD). Per the task request for this work, analysis of the PRFT slurry and filtrate for metals, anions, carbon and base were primarily performed to support the planned chemical process cell testing and to provide additional component concentrations in addition to the limited data available from DWPF. Analysis of the insoluble solids portion of the PRFT slurry was aimed at detailed characterization of these solids (TGA, PSD

  17. Facile synthesis and characterization of novel biodegradable amphiphilic block copolymers bearing pendant hydroxyl groups.

    Science.gov (United States)

    Hu, Gaicen; Fan, Xiaoshan; Xu, Bingcan; Zhang, Delong; Hu, Zhiguo

    2014-10-01

    Novel amphiphilic block copolymers bearing pendant hydroxyl groups polylactide-b-poly(3,3-bis(Hydroxymethyl-triazolylmethyl) oxetane)-b-polylactide (PLA-b-PHMTYO-b-PLA) were synthesized via a facile and efficient method. First, the block copolymer intermediates polylactide-b-poly(3,3-Diazidomethyloxetane)-b-polylactide (PLA-b-PBAMO-b-PLA) were synthesized through ring-opening polymerization of lactide using PBAMO as a macroinitiator. Following "Click" reaction of PLA-b-PBAMO-b-PLA with propargyl alcohol provided the targeted amphiphilic block copolymers PLA-b-PHMTYO-b-PLA with pendant hydroxyl groups. The composition and structure of prepared copolymers were characterized by (1)H nuclear magnetic resonance ((1)H NMR) spectroscopy, Fourier transform infrared (FT-IR) and gel permeation chromatography (GPC). The self-assembly behavior of the copolymers in water was investigated by transmission electron microscope (TEM), dynamic light scattering (DLS) and static light scattering (SLS). The results showed that the novel copolymers PLA-b-PHMTYO-b-PLA self-assembled into spherical micelles with diameters ranging from 100 nm to 200 nm in aqueous solution. These copolymers also exhibited low critical micellar concentrations (CMC: 6.9 × 10(-4)mg/mL and 3.9 × 10(-5)mg/mL, respectively). In addition, the in vitro cytotoxicity of these copolymers was determined in the presence of L929 cells. The results showed that the block copolymers PLA-b-PHMTYO-b-PLA exhibited better biocompatibility. Therefore, these well-defined copolymers are expected to find some applications in drug delivery or tissue engineering. PMID:25175206

  18. Geological site characterization for the proposed Mixed Waste Disposal Facility, Los Alamos National Laboratory

    International Nuclear Information System (INIS)

    This report presents the results of geological site characterization studies conducted from 1992 to 1994 on Pajarito Mesa for a proposed Los Alamos National Laboratory Mixed Waste Disposal Facility (MWDF). The MWDF is being designed to receive mixed waste (waste containing both hazardous and radioactive components) generated during Environmental Restoration Project cleanup activities at Los Alamos. As of 1995, there is no Resource Conservation and Recovery Act (RCRA) permitted disposal site for mixed waste at the Laboratory, and construction of the MWDF would provide an alternative to transport of this material to an off-site location. A 2.5 km long part of Pajarito Mesa was originally considered for the MWDF, extending from an elevation of about 2150 to 2225 m (7060 to 7300 ft) in Technical Areas (TAs) 15, 36, and 67 in the central part of the Laboratory, and planning was later concentrated on the western area in TA-67. The mesa top lies about 60 to 75 m (200 to 250 ft) above the floor of Pajarito Canyon on the north, and about 30 m (100 ft) above the floor of Threemile Canyon on the south. The main aquifer used as a water supply for the Laboratory and for Los Alamos County lies at an estimated depth of about 335 m (1100 ft) below the mesa. The chapters of this report focus on surface and near-surface geological studies that provide a basic framework for siting of the MWDF and for conducting future performance assessments, including fulfillment of specific regulatory requirements. This work includes detailed studies of the stratigraphy, mineralogy, and chemistry of the bedrock at Pajarito Mesa by Broxton and others, studies of the geological structure and of mesa-top soils and surficial deposits by Reneau and others, geologic mapping and studies of fracture characteristics by Vaniman and Chipera, and studies of potential landsliding and rockfall along the mesa-edge by Reneau

  19. Central and Eastern United States (CEUS) Seismic Source Characterization (SSC) for Nuclear Facilities Project

    Energy Technology Data Exchange (ETDEWEB)

    Kevin J. Coppersmith; Lawrence A. Salomone; Chris W. Fuller; Laura L. Glaser; Kathryn L. Hanson; Ross D. Hartleb; William R. Lettis; Scott C. Lindvall; Stephen M. McDuffie; Robin K. McGuire; Gerry L. Stirewalt; Gabriel R. Toro; Robert R. Youngs; David L. Slayter; Serkan B. Bozkurt; Randolph J. Cumbest; Valentina Montaldo Falero; Roseanne C. Perman' Allison M. Shumway; Frank H. Syms; Martitia (Tish) P. Tuttle

    2012-01-31

    Seismic Hazard Analysis: Guidance on Uncertainty and Use of Experts. The model will be used to assess the present-day composite distribution for seismic sources along with their characterization in the CEUS and uncertainty. In addition, this model is in a form suitable for use in PSHA evaluations for regulatory activities, such as Early Site Permit (ESPs) and Combined Operating License Applications (COLAs). Applications, Values, and Use Development of a regional CEUS seismic source model will provide value to those who (1) have submitted an ESP or COLA for Nuclear Regulatory Commission (NRC) review before 2011; (2) will submit an ESP or COLA for NRC review after 2011; (3) must respond to safety issues resulting from NRC Generic Issue 199 (GI-199) for existing plants and (4) will prepare PSHAs to meet design and periodic review requirements for current and future nuclear facilities. This work replaces a previous study performed approximately 25 years ago. Since that study was completed, substantial work has been done to improve the understanding of seismic sources and their characterization in the CEUS. Thus, a new regional SSC model provides a consistent, stable basis for computing PSHA for a future time span. Use of a new SSC model reduces the risk of delays in new plant licensing due to more conservative interpretations in the existing and future literature. Perspective The purpose of this study, jointly sponsored by EPRI, the U.S. Department of Energy (DOE), and the NRC was to develop a new CEUS SSC model. The team assembled to accomplish this purpose was composed of distinguished subject matter experts from industry, government, and academia. The resulting model is unique, and because this project has solicited input from the present-day larger technical community, it is not likely that there will be a need for significant revision for a number of years. See also Sponsors Perspective for more details. The goal of this project was to implement the CEUS SSC work plan

  20. Site characterization summary report for the Old Hydrofracture Facility, Waste Area Grouping 5, at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-04-01

    This site characterization summary report summarizes the operational history and other information on the Old Hydrofracture Facility located in the Waste Area Grouping 5 at the Oak Ridge National Laboratory. The Old Hydrofracture Facility was a waste disposal facility that operated from the 1960s until 1979. Intermediate-level radioactive waste was mixed with grout and injected deep underground for permanent disposal. Facilities at the site include various buildings, pipes, waste pits, and five underground storage tanks that contain liquid and sludge that have been characterized as low-level, hazardous, and mixed wastes.

  1. Automation of statistical analysis in the WIPP hazardous waste facility permit for analytical results from characterization

    International Nuclear Information System (INIS)

    One goal of characterizing, processing, and shipping waste to the Waste Isolation Pilot Plant (WIPP) is to make all activities as efficient as possible. Data management and repetitive calculations are a critical part of the process that can be automated, thereby increasing the accuracy and rate at which work is completed and reducing costs. This paper presents the tools developed to automate statistical analysis and other calculations required by the WIPP Hazardous Waste Facility Permit (HWFP). Statistical analyses are performed on the analytical results on gas samples from the headspace of waste containers and solid samples from the core of the waste container. The calculations include determining the number of samples, test for the shape of the distribution of the analytical results, mean, standard deviation, upper 90-percent confidence limit of the mean, and the minimum required Waste Acceptance Plan (WAP) sample size. The input data for these calculations are from the batch data reports for headspace gas analytical results and solids analysis, which must also be obtained and collated for proper use. The most challenging component of the statistical analysis, if performed manually, is the determination of the distribution shape; therefore, the distribution testing is typically performed using a certified software tool. All other calculations can be completed manually, with a spreadsheet, custom developed software, and/or certified software tool. Out of the options available, manually performing the calculations or using a spreadsheet are the least desirable. These methods rely heavily on the availability of an expert, such as a statistician, to perform the calculation. These methods are also more open to human error such as transcription or 'cut and paste' errors. A SAS program is in the process of being developed to perform the calculations. Due to the potential size of the data input files and the need to archive the data in an accessible format, the SAS

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

    International Nuclear Information System (INIS)

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

  3. Resource Conservation and Recovery Act industrial site environmental restoration site characterization plan. Area 6 Decontamination Pond Facility. Revision 1

    International Nuclear Information System (INIS)

    This plan presents the strategy for the characterization of the Area 6 Decontamination Pond Facility at the Nevada Test Site which will be conducted for the US Department of Energy, Nevada Operations Office, Environmental Restoration Division. The objectives of the planned activities are to: obtain sufficient, sample analytical data from which further assessment, remediation, and/or closure strategies may be developed for the site; obtain sufficient, sample analytical data for management of investigation-derived waste. The scope of the characterization may include surface radiation survey(s), surface soil sampling, subsurface soil boring (i.e., drilling), and sampling of soil in and around the pond; in situ sampling of the soil within subsurface soil borings; and sample analysis for both site characterization and waste management purposes

  4. Initial electron-beam characterizations for the Los Alamos APEX Facility

    Energy Technology Data Exchange (ETDEWEB)

    Lumpkin, A.H.; Feldman, R.B.; Apgar, S.A.; Feldman, D.W.; O`Shea, P.G. [Los Alamos National Lab., NM (United States); Fiorito, R.B.; Rule, D.W. [Naval Surface Warfare Center, Silver Spring, MD (United States)

    1991-12-31

    The ongoing upgrade of the Los Alamos Free-Electron Laser (FEL) Facility involves the addition of a photoelectric injector (PEI) and acceleration capability to about 40 MeV. The electron-beam and high-speed diagnostics provide key measurements of charge, beam position and profile, divergence emittance, energy (centroid, spread, slew, and extraction efficiency), micropulse duration, and phase stability. Preliminary results on the facility include optical transition radiation interferometer measurements of divergence (1 to 2 mrad), FEL extraction efficiency (0.6 {plus_minus} 0.2%), and drive laser phase stability (< 2 ps [rms]). 10 refs.

  5. Initial electron-beam characterizations for the Los Alamos APEX Facility

    Energy Technology Data Exchange (ETDEWEB)

    Lumpkin, A.H.; Feldman, R.B.; Apgar, S.A.; Feldman, D.W.; O' Shea, P.G. (Los Alamos National Lab., NM (United States)); Fiorito, R.B.; Rule, D.W. (Naval Surface Warfare Center, Silver Spring, MD (United States))

    1991-01-01

    The ongoing upgrade of the Los Alamos Free-Electron Laser (FEL) Facility involves the addition of a photoelectric injector (PEI) and acceleration capability to about 40 MeV. The electron-beam and high-speed diagnostics provide key measurements of charge, beam position and profile, divergence emittance, energy (centroid, spread, slew, and extraction efficiency), micropulse duration, and phase stability. Preliminary results on the facility include optical transition radiation interferometer measurements of divergence (1 to 2 mrad), FEL extraction efficiency (0.6 {plus minus} 0.2%), and drive laser phase stability (< 2 ps (rms)). 10 refs.

  6. Brayton-Cycle Heat Recovery System Characterization Program. Glass-furnace facility test plan

    Energy Technology Data Exchange (ETDEWEB)

    1980-08-29

    The test plan for development of a system to recover waste heat and produce electricity and preheated combustion air from the exhaust gases of an industrial glass furnace is described. The approach is to use a subatmospheric turbocompressor in a Brayton-cycle system. The operational furnace test requirements, the operational furnace environment, and the facility design approach are discussed. (MCW)

  7. Evaluation of the effects of underground water usage and spillage in the Exploratory Studies Facility; Yucca Mountain Site Characterization Project

    Energy Technology Data Exchange (ETDEWEB)

    Dunn, E.; Sobolik, S.R.

    1993-12-01

    The Yucca Mountain Site Characterization Project is studying Yucca Mountain in southwestern Nevada as a potential site for a high-level radioactive waste repository. Analyses reported herein were performed to support the design of site characterization activities so that these activities will have a minimal impact on the ability of the site to isolate waste and a minimal impact on underground tests performed as part of the characterization process. These analyses examine the effect of water to be used in the underground construction and testing activities for the Exploratory Studies Facility on in situ conditions. Underground activities and events where water will be used include construction, expected but unplanned spills, and fire protection. The models used predict that, if the current requirements in the Exploratory Studies Facility Design Requirements are observed, water that is imbibed into the tunnel wall rock in the Topopah Springs welded tuff can be removed over the preclosure time period by routine or corrective ventilation, and also that water imbibed into the Paintbrush Tuff nonwelded tuff will not reach the potential waste storage area.

  8. Geotechnical characterization of the North Ramp of the Exploratory Studies Facility: Yucca Mountain Site Characterization Project. Volume 2, NRG corehole data appendices

    Energy Technology Data Exchange (ETDEWEB)

    Brechtel, C.E.; Lin, Ming; Martin, E. [Agapito Associates, Inc., Grand Junction, CO (United States); Kessel, D.S. [Sandia National Labs., Albuquerque, NM (United States)

    1995-05-01

    This report presents the results of the geological and geotechnical characterization of the Miocene volcanic tuff rocks of the Timber Mountain and Paintbrush groups that the tunnel boring machine will encounter during excavations of the Exploratory Studies Facility (ESF) North Ramp. The information in this report was developed to support the design of the ESF North Ramp. The ESF is being constructed by the DOE as part of the Yucca Mountain Project site characterization activities. The purpose of these activities is to evaluate the potential to locate the national high-level nuclear waste repository on land within and adjacent to the Nevada Test Site (NTS), Nye County, Nevada. This report was prepared as part of the Soil and Rock Properties Studies in accordance with the 8.3.1.14.2 Study Plan to Provide Soil and Rock Properties. This is volume 2 which contains NRG Corehole Data for each of the NRG Holes.

  9. Construction and characterization of the redesigned PGAA facility at The University of Texas at Austin

    Energy Technology Data Exchange (ETDEWEB)

    Revay, Zs. [Institute of Isotopes, Hungarian Academy of Sciences, Budapest (Hungary)]. E-mail: revay@iki.kfki.hu; Harrison, R.K. [Nuclear Engineering Teaching Laboratory, The University of Texas at Austin (United States); Alvarez, E. [Nuclear Engineering Teaching Laboratory, The University of Texas at Austin (United States); Biegalski, S.R. [Nuclear Engineering Teaching Laboratory, The University of Texas at Austin (United States); Landsberger, S. [Nuclear Engineering Teaching Laboratory, The University of Texas at Austin (United States)

    2007-07-11

    The prompt gamma activation analysis (PGAA) facility at The University of Texas at Austin (UT) has been redesigned and reconstructed. As a result of the new shielding of the system, the neutron (at all energies) and gamma-ray backgrounds have been reduced by more than an order of magnitude, considerably improving the signal-to-noise ratio for the characteristic peaks. The prompt gamma peaks from the construction materials have also been decreased, providing better detection limits for elements. The calibration of the new system is shown in detail. All these efforts significantly improved the sensitivity and reliability of the chemical analyses performed in the facility. The characteristics of the improved PGAA system are also presented.

  10. Characterization of two WESF [Waste Encapsulation and Storage Facility] capsules after five years of service

    International Nuclear Information System (INIS)

    Two Waste Encapsulation and Storage Facility (WESF) 137Cs capsules have been analyzed destructively after five years of service in the Sandia Irradiator for Dried Sewage Solids (SIDSS). The program concentrated on studies of the inner capsule, inner capsule weld areas, and analysis of the CsCl salt. No measurable corrosion was observed on the capsule wall or welds after the five years in the SIDSS Facility. The operating temperatures of the inner capsule wall were calculated to be between 140 and 180/degree/C. Radiochemistry and isotopic analyses provided data for specific activity calculations. There was good correlation between the measured calorimetry of the capsules before sectioning, 53 and 55 kCi, and the activity calculations, 54 and 59 kCi, respectively. 21 refs., 43 figs., 18 tabs

  11. Preclosure radiological safety analysis for the exploratory shaft facilities; Yucca Mountain Site Characterization Project

    Energy Technology Data Exchange (ETDEWEB)

    Ma, C.W.; Miller, D.D.; Jardine, L.J. [Bechtel National, Inc., San Francisco, CA (United States)

    1992-06-01

    This study assesses which structures, systems, and components of the exploratory shaft facility (ESF) are important to safety when the ESF is converted to become part of the operating waste repository. The assessment follows the methodology required by DOE Procedure AP-6.10Q. Failures of the converted ESF during the preclosure period have been evaluated, along with other underground accidents, to determine the potential offsite radiation doses and associated probabilities. The assessment indicates that failures of the ESF will not result in radiation doses greater than 0.5 rem at the nearest unrestricted area boundary. Furthermore, credible accidents in other underground facilities will not result in radiation doses larger than 0.5 rem, even if any structure, system, or component of the converted ESF fails at the same time. Therefore, no structure, system, or component of the converted ESF is important to safety.

  12. FFTF (FAST FLUX TEST FACILITY) REACTOR CHARACTERIZATION PROGRAM ABSOLUTE FISSION RATE MEASUREMENTS

    Energy Technology Data Exchange (ETDEWEB)

    FULLER JL; GILLIAM DM; GRUNDL JA; RAWLINS JA; DAUGHTRY JW

    1981-05-01

    Absolute fission rate measurements using modified National Bureau of Standards fission chambers were performed in the Fast Flux Test Facility at two core locations for isotopic deposits of {sup 232}Th, {sup 233}U, {sup 235}U, {sup 238}U, {sup 237}Np, {sup 239}Pu, {sup 240}Pu, and {sup 241}Pu. Monitor chamber results at a third location were analyzed to support other experiments involving passive dosimeter fission rate determinations.

  13. FFTF (Fast Flux Test Facility) Reactor Characterization Program: Absolute Fission-rate Measurements

    Energy Technology Data Exchange (ETDEWEB)

    Fuller, J.L.; Gilliam, D.M.; Grundl, J.A.; Rawlins, J.A.; Daughtry, J.W.

    1981-05-01

    Absolute fission rate measurements using modified National Bureau of Standards fission chambers were performed in the Fast Flux Test Facility at two core locations for isotopic deposits of {sup 232}Th, {sup 233}U, {sup 235}U, {sup 238}U, {sup 237}Np, {sup 239}Pu, {sup 240}Pu, and {sup 241}Pu. Monitor chamber results at a third location were analyzed to support other experiments involving passive dosimeter fission rate determinations.

  14. An Infrared Laser Testing Facility for the Characterization of the CLAS12 Silicon Detectors

    Science.gov (United States)

    Phillips, Sarah

    2011-04-01

    During the 12 GeV upgrade to the CEBAF accelerator at Jefferson Lab, a new spectrometer, CLAS12, will be built in Hall B. The Nuclear Physics Group at the University of New Hampshire is part of the collaboration working to design and build this new detector system. Among the new detector systems being developed for CLAS12 is a silicon vertex tracker that will be placed close to the target, providing excellent position resolution for vertex determination. It is essential to have the ability to perform quality assurance tests and to evaluate the performance of the individual silicon strip detectors before their installation in the full detector system. The UNH Nuclear Physics Group is designing and building a laser testing facility at UNH to perform this task. The design for the testing facility consists of a 1064 nm infrared laser system and a precision positioning mechanism to scan the laser light on the detector by a computer controlled system designed to efficiently test the large number of detectors prior to installation. The detector signals are read out by a computer data acquisition system for analysis. The facility also includes a cleanroom area to house the test stand, and a dry storage containment system for the storage of the detectors.

  15. Solid state synthesis and characterization of sodium zirconium phosphate (NZP): A review of issues and characterization facilities

    International Nuclear Information System (INIS)

    Materials synthesis and characterization with a view to tailoring them for specific applications has the potential to assuage the enormous challenges besetting our socio-economic lives and resolve our energy crises. This is possible through the identification and development of materials that have potential to complement our dependence on fossil fuels and that are most appropriate in alleviating the recurrent and persistent fuel crises in the energy sector. At the moment there is an avalanche of research activities taking place in the various alternative energy options to develop renewable sources of energy with enormous implications for our revenue base. The study of NASICON materials for potential energy applications in diverse fields such as fuel cells for transportation, rechargeable lithium batteries, biomaterials, nuclear waste demobilization and environmental concerns, among others has been actively pursued by different groups of researchers. However, the synthesi s and characterization of these materials is challenging and presents its peculiar problems in terms of material and human resources and the irreconcilable atmosphere for research with the existing institutional policy framework within which researchers have to operate in general. The paper reviews the relevant issues and instrumental readiness of some surveyed institutions in carrying out research within the Nigerian context based on the ongoing research on Sodium Zirconium Phosphate (NZP), a member of NASICON family and proffers solutions to them.

  16. Fracture characterization at the Conoco Borehole Test Facility using shear-wave anisotropy

    Energy Technology Data Exchange (ETDEWEB)

    Horne, S.A. [Univ. of Edinburgh (United Kingdom); MacBeth, C.D.; Queen, J.; Rizer, W.D.

    1995-12-31

    Two multi-component near-offset VSP experiments are used, in conjunction with borehole data, to characterise the subsurface fracture system at the Conoco Borehole Test Facility, Oklahoma. Time delays between the fast and slow split shear-waves are observed to correlate with the heavily fractured sandstone formations. Inversion of the shear-wave splitting estimates is achieved using a Genetic Algorithm which incorporates an anisotropic ray tracing scheme. The inversion results suggest that the fracture orientation is sub-vertical. A method of determining fracture dip using an opposite azimuth VSP method is suggested.

  17. Radiation field characterization of a BNCT research facility using Monte Carlo method - code MCNP-4B

    International Nuclear Information System (INIS)

    Boron Neutron Capture Therapy - BNCT - is a selective cancer treatment and arises as an alternative therapy to treat cancer when usual techniques - surgery, chemotherapy or radiotherapy - show no satisfactory results. The main proposal of this work is to project a facility to BNCT studies. This facility relies on the use of an Am Be neutron source and on a set of moderators, filters and shielding which will provide the best neutron/gamma beam characteristic for these Becton studies, i.e., high intensity thermal and/or epithermal neutron fluxes and with the minimum feasible gamma rays and fast neutrons contaminants. A computational model of the experiment was used to obtain the radiation field in the sample irradiation position. The calculations have been performed with the MCNP 4B Monte Carlo Code and the results obtained can be regarded as satisfactory, i.e., a thermal neutron fluencyNT = 1,35x108 n/cm , a fast neutron dose of 5,86x10-10 Gy/NT and a gamma ray dose of 8,30x10-14 Gy/NT. (author)

  18. Microalgae from domestic wastewater facility's high rate algal pond: Lipids extraction, characterization and biodiesel production.

    Science.gov (United States)

    Drira, Neila; Piras, Alessandra; Rosa, Antonella; Porcedda, Silvia; Dhaouadi, Hatem

    2016-04-01

    In this study, the harvesting of a biomass from a high rate algal pond (HRAP) of a real-scale domestic wastewater treatment facility and its potential as a biomaterial for the production of biodiesel were investigated. Increasing the medium pH to 12 induced high flocculation efficiency of up to 96% of the biomass through both sweep flocculation and charge neutralization. Lipids extracted by ultrasounds from this biomass contained around 70% of fatty acids, with palmitic and stearic acids being the most abundant. The extract obtained by supercritical CO2 contained 86% of fatty acids. Both conventional solvents extracts contained only around 10% of unsaturated fats, whereas supercritical CO2 extract contained more than 40% of unsaturated fatty acids. This same biomass was also subject to direct extractive-transesterification in a microwave reactor to produce fatty acid methyl esters, also known as, raw biodiesel. PMID:26866759

  19. ISRU Soil Mechanics Vacuum Facility: Soil Bin Preparation and Simulant Strength Characterization

    Science.gov (United States)

    Kleinhenz, Julie; Wilkinson, Allen

    2012-01-01

    Testing in relevant environments is key to exploration mission hardware development. This is true on both the component level (in early development) and system level (in late development stages). During ISRU missions the hardware will interface with the soil (digging, roving, etc) in a vacuum environment. A relevant test environment will therefore involve a vacuum chamber with a controlled, conditioned simulant bed. However, in earth-based granular media, such as lunar soil simulant, gases trapped within the material pore structures and water adsorbed to all particle surfaces will release when exposed to vacuum. Early vacuum testing has shown that this gas release can occur violently, which loosens and weakens the simulant, altering the consolidation state. The Vacuum Facility #13, a mid-size chamber (3.66m tall, 1.5m inner diameter) at the NASA Glenn Research Center has been modified to create a soil mechanics test facility. A 0.64m deep by 0.914m square metric ton bed of lunar simulant was placed under vacuum using a variety of pumping techniques. Both GRC-3 and LHT-3M simulant types have been used. An electric cone penetrometer was used to measure simulant strength properties at vacuum including: cohesion, friction angle, bulk density and shear modulus. Simulant disruptions, caused by off gassing, affected the strength properties, but could be mitigated by reducing pump rate. No disruptions were observed at pressures below 2.5Torr, regardless of the pump rate. However, slow off gassing of the soil lead to long test times, a full week, to reach 10-5Torr. This work highlights the need for robotic machine-simulant hardware and operations in vacuum to expeditiously perform (sub-)systems tests.

  20. Characterization of spent fuel assemblies for storage facilities using non destructive assay

    International Nuclear Information System (INIS)

    Many non destructive assay (NDA) techniques have been developed by the French Atomic Energy Commission (CEA) for spent fuel characterization and management. Passive and active neutron methods as well as gamma spectrometric methods have been carried out and applied to industrial devices like PYTHONTM and NAJA. Many existing NDA methods can be successfully applied to storage, but the most promising are the neutron methods combined with on line evolution codes. For dry storage applications, active neutron measurements require further R and D to achieve accurate results. Characterization data given by NDA instruments can now be linked to automatic fuel recognition. Both information can feed the storage management software in order to meet the storage operation requirements like: fissile mass inventory, operators declaration consistency or automatic selection of proper storage conditions. (author)

  1. Health and safety plan for characterization sampling of ETR and MTR facilities

    International Nuclear Information System (INIS)

    This health and safety plan establishes the procedures and requirements that will be used to minimize health and safety risks to persons performing Engineering Test Reactor and Materials Test Reactor characterization sampling activities, as required by the Occupational Safety and Health Administration standard, 29 CFR 1910.120. It contains information about the hazards involved in performing the tasks, and the specific actions and equipment that will be used to protect persons working at the site

  2. Biosynthesis and characterization of silver nanoparticles prepared from two novel natural precursors by facile thermal decomposition methods

    Science.gov (United States)

    Goudarzi, Mojgan; Mir, Noshin; Mousavi-Kamazani, Mehdi; Bagheri, Samira; Salavati-Niasari, Masoud

    2016-01-01

    In this work, two natural sources, including pomegranate peel extract and cochineal dye were employed for the synthesis of silver nanoparticles. The natural silver complex from pomegranate peel extract resulted in nano-sized structures through solution-phase method, but this method was not efficient for cochineal dye-silver precursor and the as-formed products were highly agglomerated. Therefore, an alternative facile solid-state approach was investigated as for both natural precursors and the results showed successful production of well-dispersed nanoparticles with narrow size distribution for cochineal dye-silver precursor. The products were characterized by X-ray diffraction (XRD), Scanning Electron Microscopy (SEM), Energy dispersive X-ray microanalysis (EDX), and Transmission Electron Microscopy (TEM). PMID:27581681

  3. Characterization of gaseous detectors at the CERN Gamma Irradiation Facility: GEM performance in presence of high background radiation

    CERN Document Server

    AUTHOR|(CDS)2097588

    Muon detection is an efficient tool to recognize interesting physics events over the high background rate expected at the Large Hadron Collider (LHC) at CERN. The muon systems of the LHC experiments are based on gaseous ionization detectors. In view of the High-Luminosity LHC (HL-LHC) upgrade program, the increasing of background radiation could affect the gaseous detector performance, especially decreasing the efficiency and shortening the lifetime through ageing processes. The effects of charge multiplication, materials and gas composition on the ageing of gaseous detectors have been studied for decades, but the future upgrade of LHC requires additional studies on this topic. At the CERN Gamma Irradiation Facility (GIF++), a radioactive source of cesium-137 with an activity of 14 TBq is used to reproduce reasonably well the expected background radiation at HL-LHC. A muon beam has been made available to study detector performance. The characterization of the beam trigger will be discussed in the present w...

  4. Biosynthesis and characterization of silver nanoparticles prepared from two novel natural precursors by facile thermal decomposition methods

    Science.gov (United States)

    Goudarzi, Mojgan; Mir, Noshin; Mousavi-Kamazani, Mehdi; Bagheri, Samira; Salavati-Niasari, Masoud

    2016-09-01

    In this work, two natural sources, including pomegranate peel extract and cochineal dye were employed for the synthesis of silver nanoparticles. The natural silver complex from pomegranate peel extract resulted in nano-sized structures through solution-phase method, but this method was not efficient for cochineal dye-silver precursor and the as-formed products were highly agglomerated. Therefore, an alternative facile solid-state approach was investigated as for both natural precursors and the results showed successful production of well-dispersed nanoparticles with narrow size distribution for cochineal dye-silver precursor. The products were characterized by X-ray diffraction (XRD), Scanning Electron Microscopy (SEM), Energy dispersive X-ray microanalysis (EDX), and Transmission Electron Microscopy (TEM).

  5. Design and characterization of a neutron calibration facility for the study of sub-keV nuclear recoils

    Science.gov (United States)

    Barbeau, P. S.; Collar, J. I.; Whaley, P. M.

    2007-05-01

    We have designed and built a highly monochromatic 24 keV neutron beam at the Kansas State University Triga Mark-II reactor, as part of an experimental effort to demonstrate sensitivity in a large-mass detector to the ultra-low energy recoils expected from coherent neutrino-nucleus elastic scattering. The beam characteristics were chosen so as to mimic the soft recoil energies expected from reactor antineutrinos in a variety of targets, allowing to understand the response of dedicated detector technologies in this yet unexplored sub-keV recoil range. A full characterization of the beam properties (intensity, monochromaticity, contaminations, beam profile) is presented, together with first tests of the calibration facility using proton recoils in organic scintillator.

  6. Isolation and characterization of rhamnolipid-producing bacterial strains from a biodiesel facility.

    Science.gov (United States)

    Rooney, Alejandro P; Price, Neil P J; Ray, Karen J; Kuo, Tsung-Min

    2009-06-01

    Novel strains of rhamnolipid-producing bacteria were isolated from soils at a biodiesel facility on the basis of their ability to grow on glycerol as a sole carbon source. Strains were identified as Acinetobacter calcoaceticus, Enterobacter asburiae, Enterobacter hormaechei, Pantoea stewartii, and Pseudomonas aeruginosa. The strains of the former five species were found to produce rhamnolipids in quantities the same as, or similar to, coisolated strains of P. aeruginosa. Measurements of surface tension revealed that that emulsifying properties of these strains were similar to levels displayed by rhamnolipids produced by P. aeruginosa. Results of matrix-assisted laser desorption/ionization time-of-flight MS analyses revealed that the predominant compounds made by all strains were C10-C10 mono- and dirhamnolipids. Notably, E. hormaechei and one strain of A. calcoaceticus produced rhamnolipids in amounts similar to the pseudomonads. As all strains examined were from the same taxonomic class of Proteobacteria, further examination of this group may reveal many additional species not previously known to produce rhamnolipids in addition to novel strains of species currently known to produce rhamnolipids. PMID:19473254

  7. Characterizations of new ΔE detectors for single-ion hit facility

    Science.gov (United States)

    Abdel, Naseem S.; Pallon, Jan; Ros, Linus; Borysiuk, Maciek; Elfman, Mikael; Kristiansson, Per; Nilsson, E. J. Charlotta

    2014-01-01

    This paper describes the performance evaluation of new ΔE detectors to be used as pre-cell hit detectors in living cell irradiation experiments at the Lund Ion Beam Analysis facility (LIBAF). Using these detectors with a thickness down to 4.15 μm fabricated at Lund University, an experiment was setup in which ΔE-detectors were used together with a stop E-detector in a telescope system under coincidence measurements. The characteristics of ΔE detectors were based on the optimal detection of the passage of 2.55 MeV protons. The results of these tests demonstrate that the detector telescope clearly separates the protons, this due to high signal-to-noise ratio and good energy resolution of the ΔE-detectors. The best performing detector was shown to have a detection efficiency of 95% at thickness of 9.7 μm. This type of high-performing detector is suitable for the planned role of the ΔE-detector in the future cell irradiation experiments.

  8. Preclosure radiological safety evaluation: Exploratory Studies Facility; Yucca Mountain Site Characterization Project

    Energy Technology Data Exchange (ETDEWEB)

    Schelling, F.J. [Sandia National Labs., Albuquerque, NM (US); Smith, J.D. [GRAM, Inc., Albuquerque, NM (US)

    1993-07-01

    A radiological safety evaluation is performed to determine the impacts of Exploratory Studies Facility (ESF) design changes on the preclosure public radiological safety for a potential nuclear waste repository at Yucca Mountain, Nevada. Although the ESF design has undergone significant modification, incorporation of the modified design requires only modest changes to the conceptual repository configuration. To the extent feasible, the results of earlier safety evaluations presented in SAND84-2641, SAND88-7061, and SAND89-7024, which were based on the original ESF configuration, are compared with the results for the modified configuration. This comparison provides an estimate of the range of analysis uncertainty. This preliminary analysis indicates that there are no Q-scenarios, which are defined as those scenarios with a net occurrence probability of greater than 10{sup {minus}6}/yr and produce a radiological dose at the 5-km controlled area boundary of greater than 0.5 rem. The analysis yielded estimates for an underground accident of a probability of 3.8 {times} 10{sup {minus}15}/yr and a dose of 1.5 rem. For a surface-initiated accident, a probability of 1.5 {times} 10{sup {minus}12}/yr and a dose of 0.6 rem was estimated.

  9. A facile synthesis and spectral characterization of Cu2+ doped CdO/ZnS nanocomposite

    Science.gov (United States)

    Joyce Stella, R.; Thirumala Rao, G.; Babu, B.; Pushpa Manjari, V.; Reddy, Ch. Venkata; Shim, Jaesool; Ravikumar, R. V. S. S. N.

    2015-06-01

    A facile two-step method is demonstrated for the preparation of Cu2+ doped CdO/ZnS nanocomposite. Systematic investigations like X-ray diffraction (XRD), Scanning electron microscopy (SEM) with EDS, transmission electron microscopy (TEM), FT-IR, electron paramagnetic resonance (EPR), optical absorption, photoluminescence (PL) and magnetic studies are carried out for the prepared material. From powder XRD, the nanocomposites are comprised for cubic phase of both CdO and ZnS in a close contact with each other. The ground state wave function of dopant ions has been estimated from EPR studies. Optical and EPR data confirm that doped Cu2+ions occupy rhombically distorted octahedral sites with the host material. Due to doping, band gap has been changed and blue shifts occurred in PL. Magnetic measurements indicate a possible ferromagnetic response, associated to the exchange interaction between local spin-polarized electrons of Cu2+ ions and conductive electrons. The magnetic properties of Cu2+ doped CdO/ZnS nanocomposite has been investigated using vibrating sample magnetometer given as magnetization and hysteresis (M-H) curve. The magnetization curve with noticeable coercivity of M-H loop clearly indicate the existence of ferromagnetic ordering in Cu2+ doped CdO/ZnS nanocomposite at room temperature. According to the Ruderman-Kittel-Kasuya-Yosida (RKKY) theory, the exchange interaction between local spin-polarized electrons (such as the electrons of Cu2+ ions) and conductive electrons is the main cause that leads to the ferromagnetism. Coercivity (Hc) of the field is about 98 Oe, saturationmagnetization (Ms) and remnant magnetization (Mr) of present sample is estimated to be 15.8×10-3 and 1.43×10-3 emu/g respectively. The ferromagnetism observed in the prepared material is not commencing with other impurities but expected to be intrinsic.

  10. Concrete material characterization reinforced concrete tank structure Multi-Function Waste Tank Facility

    International Nuclear Information System (INIS)

    The purpose of this report is to document the Multi-Function Waste Tank Facility (MWTF) Project position on the concrete mechanical properties needed to perform design/analysis calculations for the MWTF secondary concrete structure. This report provides a position on MWTF concrete properties for the Title 1 and Title 2 calculations. The scope of the report is limited to mechanical properties and does not include the thermophysical properties of concrete needed to perform heat transfer calculations. In the 1970's, a comprehensive series of tests were performed at Construction Technology Laboratories (CTL) on two different Hanford concrete mix designs. Statistical correlations of the CTL data were later generated by Pacific Northwest Laboratories (PNL). These test results and property correlations have been utilized in various design/analysis efforts of Hanford waste tanks. However, due to changes in the concrete design mix and the lower range of MWTF operating temperatures, plus uncertainties in the CTL data and PNL correlations, it was prudent to evaluate the CTL data base and PNL correlations, relative to the MWTF application, and develop a defendable position. The CTL test program for Hanford concrete involved two different mix designs: a 3 kip/in2 mix and a 4.5 kip/in2 mix. The proposed 28-day design strength for the MWTF tanks is 5 kip/in2. In addition to this design strength difference, there are also differences between the CTL and MWTF mix design details. Also of interest, are the appropriate application of the MWTF concrete properties in performing calculations demonstrating ACI Code compliance. Mix design details and ACI Code issues are addressed in Sections 3.0 and 5.0, respectively. The CTL test program and PNL data correlations focused on a temperature range of 250 to 450 F. The temperature range of interest for the MWTF tank concrete application is 70 to 200 F

  11. Concrete material characterization reinforced concrete tank structure Multi-Function Waste Tank Facility

    Science.gov (United States)

    Winkel, B. V.

    1995-03-01

    The purpose of this report is to document the Multi-Function Waste Tank Facility (MWTF) Project position on the concrete mechanical properties needed to perform design/analysis calculations for the MWTF secondary concrete structure. This report provides a position on MWTF concrete properties for the Title 1 and Title 2 calculations. The scope of the report is limited to mechanical properties and does not include the thermophysical properties of concrete needed to perform heat transfer calculations. In the 1970's, a comprehensive series of tests were performed at Construction Technology Laboratories (CTL) on two different Hanford concrete mix designs. Statistical correlations of the CTL data were later generated by Pacific Northwest Laboratories (PNL). These test results and property correlations have been utilized in various design/analysis efforts of Hanford waste tanks. However, due to changes in the concrete design mix and the lower range of MWTF operating temperatures, plus uncertainties in the CTL data and PNL correlations, it was prudent to evaluate the CTL data base and PNL correlations, relative to the MWTF application, and develop a defendable position. The CTL test program for Hanford concrete involved two different mix designs: a 3 kip/sq in mix and a 4.5 kip/sq in mix. The proposed 28-day design strength for the MWTF tanks is 5 kip/sq in. In addition to this design strength difference, there are also differences between the CTL and MWTF mix design details. Also of interest, are the appropriate application of the MWTF concrete properties in performing calculations demonstrating ACI Code compliance. Mix design details and ACI Code issues are addressed in Sections 3.0 and 5.0, respectively. The CTL test program and PNL data correlations focused on a temperature range of 250 to 450 F. The temperature range of interest for the MWTF tank concrete application is 70 to 200 F.

  12. Characterization of cobalt oxide thin films prepared by a facile spray pyrolysis technique using perfume atomizer

    Energy Technology Data Exchange (ETDEWEB)

    Louardi, A.; Rmili, A.; Ouachtari, F.; Bouaoud, A. [Laboratoire des Hautes Energies, Sciences de l' Ingenierie et Reacteurs (LHESIR), Equipe Ingenierie et Materiaux (INMA), Departement de Physique, Faculte des Sciences, Kenitra (Morocco); Elidrissi, B., E-mail: e.bachir@mailcity.com [Laboratoire des Hautes Energies, Sciences de l' Ingenierie et Reacteurs (LHESIR), Equipe Ingenierie et Materiaux (INMA), Departement de Physique, Faculte des Sciences, Kenitra (Morocco); Erguig, H. [Laboratoire des Hautes Energies, Sciences de l' Ingenierie et Reacteurs (LHESIR), Equipe Ingenierie et Materiaux (INMA), Departement de Physique, Faculte des Sciences, Kenitra (Morocco)

    2011-09-15

    Highlights: > Co{sub 3}O{sub 4} thin films show a micro porous structure. > Co{sub 3}O{sub 4} thin films are formed with spherical grains less than 50 nm in diameter. > The porous structure of Co{sub 3}O{sub 4} films is expected to have promising application in electrochromism. - Abstract: Cobalt oxide (Co{sub 3}O{sub 4}) thin films were prepared by a facile spray pyrolysis technique using perfume atomizer from aqueous solution of hydrated cobalt chloride salt (CoCl{sub 2}.6H{sub 2}O) as source of cobalt. The films were deposited onto the amorphous glass substrates kept at different temperatures (300-500 deg. C). The influences of molar concentration of the starting solution and substrate temperature on the structural, morphological and optical properties of (Co{sub 3}O{sub 4}) thin films were studied. It was found from X-ray diffraction (XRD) analysis that the films prepared with molar concentration greater than 0.025 M/L were polycrystalline spinel type cubic structure. The preferred orientation of the crystallites of these films changes gradually from (6 2 2) to (1 1 1) when the substrate temperature increases. By Raman spectroscopy, five Raman active modes characteristic of Co{sub 3}O{sub 4} spinel type cubic structure were found and identified at 194, 484, 522, 620 and 691 cm{sup -1}. The scanning electron microscopy (SEM) images showed micro porous structure with very fine grains less than 50 nm in diameter. These films exhibited also a transmittance value of about 70% in the visible and infra red range.

  13. Facile synthesis of mesoporous nanocrystalline ZnO bipyramids and spheres: Characterization, and photocatalytic activity

    Energy Technology Data Exchange (ETDEWEB)

    Srinivasan, Priya; Subramanian, Balaji [Laboratoire de recherche en matériaux et Micro-spectroscopies Raman et FTIR, Université de Moncton, Campus de Shippagan, Shippagan, NB, E8S 1P6 Canada (Canada); Djaoued, Yahia, E-mail: yahia.djaoued@umoncton.ca [Laboratoire de recherche en matériaux et Micro-spectroscopies Raman et FTIR, Université de Moncton, Campus de Shippagan, Shippagan, NB, E8S 1P6 Canada (Canada); Robichaud, Jacques [Laboratoire de recherche en matériaux et Micro-spectroscopies Raman et FTIR, Université de Moncton, Campus de Shippagan, Shippagan, NB, E8S 1P6 Canada (Canada); Sharma, Tanu; Bruning, Ralf [Department of Physcis, Mount Alison University, Sackville, NB, E4L 1E6 Canada (Canada)

    2015-04-01

    A facile and versatile polyol mediated solvo-thermal process using zinc acetate has been adopted for the synthesis of mesoporous ZnO nanomaterials having novel morphologies. Polyols used in this study, i.e. ethylene glycol (EG) and polyethylene glycols (PEG) of molecular weight 200 and 400, not only act as solvents but also as structure directing agents. The synthesis using EG leads to the formation of novel square bipyramidal zinc glycolate intermediate, which upon thermal treatment is converted into a nanocrystalline (NC) wurtzite ZnO structure, preserving the square bipyramidal morphology. Zinc glycolate upon hot water treatment (∼85 °C), results in the formation of NC wurtzite ZnO having a bicone morphology. However, when the synthesis is carried out by replacing EG with PEG-200 or 400, NC wurtzite ZnO having spherical morphologies have been directly isolated. In the case of PEG-200, the NC ZnO spheres displayed radially oriented nanorod features on the surface. A mechanism of formation of these ZnO morphologies is proposed. The synthesized ZnO materials have been used as catalysts for the photodegradation of crystal violet dye under UV-B and UV-C irradiation. The catalytic behavior of the ZnO samples is explained based on their porosity, crystallinity, and microstructure. - Highlights: • A polyol facilitated process using zinc acetate was used to obtain mesoporous ZnO. • These mesoporous ZnO materials exhibited square bipyramids and spheres morphologies. • Ethylene glycol and PEG-200 mediated ZnO samples presented higher degradation rates. • Crystallinity takes precedence over surface area in photodegradation.

  14. Characterization of 618-11 solid waste burial ground, disposed waste, and description of the waste generating facilities

    Energy Technology Data Exchange (ETDEWEB)

    Hladek, K.L.

    1997-10-07

    The 618-11 (Wye or 318-11) burial ground received transuranic (TRTJ) and mixed fission solid waste from March 9, 1962, through October 2, 1962. It was then closed for 11 months so additional burial facilities could be added. The burial ground was reopened on September 16, 1963, and continued operating until it was closed permanently on December 31, 1967. The burial ground received wastes from all of the 300 Area radioactive material handling facilities. The purpose of this document is to characterize the 618-11 solid waste burial ground by describing the site, burial practices, the disposed wastes, and the waste generating facilities. This document provides information showing that kilogram quantities of plutonium were disposed to the drum storage units and caissons, making them transuranic (TRU). Also, kilogram quantities of plutonium and other TRU wastes were disposed to the three trenches, which were previously thought to contain non-TRU wastes. The site burial facilities (trenches, caissons, and drum storage units) should be classified as TRU and the site plutonium inventory maintained at five kilograms. Other fissile wastes were also disposed to the site. Additionally, thousands of curies of mixed fission products were also disposed to the trenches, caissons, and drum storage units. Most of the fission products have decayed over several half-lives, and are at more tolerable levels. Of greater concern, because of their release potential, are TRU radionuclides, Pu-238, Pu-240, and Np-237. TRU radionuclides also included slightly enriched 0.95 and 1.25% U-231 from N-Reactor fuel, which add to the fissile content. The 618-11 burial ground is located approximately 100 meters due west of Washington Nuclear Plant No. 2. The burial ground consists of three trenches, approximately 900 feet long, 25 feet deep, and 50 feet wide, running east-west. The trenches constitute 75% of the site area. There are 50 drum storage units (five 55-gallon steel drums welded together

  15. Characterization of 618-11 solid waste burial ground, disposed waste, and description of the waste generating facilities

    International Nuclear Information System (INIS)

    The 618-11 (Wye or 318-11) burial ground received transuranic (TRTJ) and mixed fission solid waste from March 9, 1962, through October 2, 1962. It was then closed for 11 months so additional burial facilities could be added. The burial ground was reopened on September 16, 1963, and continued operating until it was closed permanently on December 31, 1967. The burial ground received wastes from all of the 300 Area radioactive material handling facilities. The purpose of this document is to characterize the 618-11 solid waste burial ground by describing the site, burial practices, the disposed wastes, and the waste generating facilities. This document provides information showing that kilogram quantities of plutonium were disposed to the drum storage units and caissons, making them transuranic (TRU). Also, kilogram quantities of plutonium and other TRU wastes were disposed to the three trenches, which were previously thought to contain non-TRU wastes. The site burial facilities (trenches, caissons, and drum storage units) should be classified as TRU and the site plutonium inventory maintained at five kilograms. Other fissile wastes were also disposed to the site. Additionally, thousands of curies of mixed fission products were also disposed to the trenches, caissons, and drum storage units. Most of the fission products have decayed over several half-lives, and are at more tolerable levels. Of greater concern, because of their release potential, are TRU radionuclides, Pu-238, Pu-240, and Np-237. TRU radionuclides also included slightly enriched 0.95 and 1.25% U-231 from N-Reactor fuel, which add to the fissile content. The 618-11 burial ground is located approximately 100 meters due west of Washington Nuclear Plant No. 2. The burial ground consists of three trenches, approximately 900 feet long, 25 feet deep, and 50 feet wide, running east-west. The trenches constitute 75% of the site area. There are 50 drum storage units (five 55-gallon steel drums welded together

  16. Facile Synthesis and Characterization of Au Nanoclusters-Silica Fluorescent Composite Nanospheres

    Directory of Open Access Journals (Sweden)

    Huiping Wang

    2013-01-01

    Full Text Available We developed a novel method for the synthesis of Au nanoclusters (NCs silica fluorescent composite nanospheres by mixing the as-prepared bovine serum albumin (BSA protected Au NCs with amino-modified silica spheres in acetate buffer solution. The products were characterized by high-resolution transmission electron microscopy (HRTEM, X-ray photoelectron spectroscopy (XPS, fluorescent microscope imaging (FLMI, and dynamic light scattering (DLS measurements. The proposed method was simple, efficient, and inexpensive. In addition, the composite nanospheres exhibited favorable water-dispersible, stable, and fluorescent properties, potentially leading to further applications in chemical and biological sensors. A reasonable mechanism was also proposed for the formation of composite nanospheres.

  17. Characterization and environmental studies of Pompano Beach anaerobic digestion facility. Semi-annual report

    Energy Technology Data Exchange (ETDEWEB)

    Sengupta, S; Farooq, S; Gerrish, H P; Wong, K F; Daly, Jr, E L; Chriswell, C

    1980-02-01

    Anaerobic digestion of municipal waste has been demonstrated to be feasible in bench scale experiments by Pfeffer (1974). Approximately, 50% reduction in mass and production of 6000 ft/sup 3/ of gas/ton have been estimated. The gas composition is estimated to be 50% methane and 50% carbon monoxide. The technical and economic feasibility of anaerobic digestion with an ultimate objective of commercialization are discussed. A plant has been built at Pompano Beach, Florida on an existing shredding and landfill operation site. The plant design capacity is 100 tons/day. Two digesters have been constructed to be used in parallel. The process consists of primary shredding, metal separation, secondary shredding, air classification and digestion of light fraction. Sewage sludge was used to seed the initial mixture in the digester. The output slurry is vacuum filtered and the filter cake disposed on an existing landfill. The filtrate is recycled. Excess filtrate is sprayed on the landfill. At present the output gas is being flared. A flow chart for the plant is presented. It is imperative that environmental investigations be conducted on new energy technology prior to commercialization. A project was initiated to characterize all input and output streams and to assess the potential for ground water contamination by landfill disposal of effluents. Detailed chemical, biological and physical characterization efforts supported by leaching and modelling studies are being conducted to achieve the stated objectives. Some mutagenic studies were also conducted. The environmental investigations were started in August 1978. Sengupta et al (1979a) reported the first year's efforts.

  18. Characterization of the neutron irradiation system for use in the Low-Dose-Rate Irradiation Facility at Sandia National Laboratories.

    Energy Technology Data Exchange (ETDEWEB)

    Franco, Manuel,

    2014-08-01

    The objective of this work was to characterize the neutron irradiation system consisting of americium-241 beryllium (241AmBe) neutron sources placed in a polyethylene shielding for use at Sandia National Laboratories (SNL) Low Dose Rate Irradiation Facility (LDRIF). With a total activity of 0.3 TBq (9 Ci), the source consisted of three recycled 241AmBe sources of different activities that had been combined into a single source. The source in its polyethylene shielding will be used in neutron irradiation testing of components. The characterization of the source-shielding system was necessary to evaluate the radiation environment for future experiments. Characterization of the source was also necessary because the documentation for the three component sources and their relative alignment within the Special Form Capsule (SFC) was inadequate. The system consisting of the source and shielding was modeled using Monte Carlo N-Particle transport code (MCNP). The model was validated by benchmarking it against measurements using multiple techniques. To characterize the radiation fields over the full spatial geometry of the irradiation system, it was necessary to use a number of instruments of varying sensitivities. First, the computed photon radiography assisted in determining orientation of the component sources. With the capsule properly oriented inside the shielding, the neutron spectra were measured using a variety of techniques. A N-probe Microspec and a neutron Bubble Dosimeter Spectrometer (BDS) set were used to characterize the neutron spectra/field in several locations. In the third technique, neutron foil activation was used to ascertain the neutron spectra. A high purity germanium (HPGe) detector was used to characterize the photon spectrum. The experimentally measured spectra and the MCNP results compared well. Once the MCNP model was validated to an adequate level of confidence, parametric analyses was performed on the model to optimize for potential

  19. A facile synthesis and spectral characterization of Cu2+ doped CdO/ZnS nanocomposite

    International Nuclear Information System (INIS)

    A facile two-step method is demonstrated for the preparation of Cu2+ doped CdO/ZnS nanocomposite. Systematic investigations like X-ray diffraction (XRD), Scanning electron microscopy (SEM) with EDS, transmission electron microscopy (TEM), FT-IR, electron paramagnetic resonance (EPR), optical absorption, photoluminescence (PL) and magnetic studies are carried out for the prepared material. From powder XRD, the nanocomposites are comprised for cubic phase of both CdO and ZnS in a close contact with each other. The ground state wave function of dopant ions has been estimated from EPR studies. Optical and EPR data confirm that doped Cu2+ions occupy rhombically distorted octahedral sites with the host material. Due to doping, band gap has been changed and blue shifts occurred in PL. Magnetic measurements indicate a possible ferromagnetic response, associated to the exchange interaction between local spin-polarized electrons of Cu2+ ions and conductive electrons. - Graphical abstract: M–H curve of Cu2+ doped CdO–ZnS nanocomposites. The magnetic properties of Cu2+ doped CdO/ZnS nanocomposite has been investigated using vibrating sample magnetometer given as magnetization and hysteresis (M–H) curve. The magnetization curve with noticeable coercivity of M–H loop clearly indicate the existence of ferromagnetic ordering in Cu2+ doped CdO/ZnS nanocomposite at room temperature. According to the Ruderman–Kittel–Kasuya–Yosida (RKKY) theory, the exchange interaction between local spin-polarized electrons (such as the electrons of Cu2+ ions) and conductive electrons is the main cause that leads to the ferromagnetism. Coercivity (Hc) of the field is about 98 Oe, saturation magnetization (Ms) and remnant magnetization (Mr) of present sample is estimated to be 15.8×10−3 and 1.43×10−3 emu/g respectively. The ferromagnetism observed in the prepared material is not commencing with other impurities but expected to be intrinsic. - Highlights: • Cu2+ doped Cd

  20. Facile fabrication and characterization of chitosan-based zinc oxide nanoparticles and evaluation of their antimicrobial and antibiofilm activity

    Science.gov (United States)

    Dhillon, Gurpreet Singh; Kaur, Surinder; Brar, Satinder Kaur

    2014-06-01

    The present investigation deals with the facile synthesis and characterization of chitosan (CTS)-based zinc oxide (ZnO) nanoparticles (NPs) and their antimicrobial activities against pathogenic microorganisms. ZnO-CTS NPs were synthesized through two different methods: nano spray drying and precipitation, using various organic compounds (citric acid, glycerol, starch and whey powder) as stabilizers. Both the synthesis methods were simple and were devoid of any chemical usage. The detailed characterization of the NPs was carried out using UV-Vis spectroscopy, dynamic light scattering particle size analysis, zeta potential measurements and scanning electron microscopy, which confirmed the fabrication of NPs with different shapes and sizes. Antimicrobial assay of synthesized ZnO-CTS NPs was carried out against different pathogenic microbial strains ( Candida albicans, Micrococcus luteus and Staphylococcus aureus). The significant ( p aureus with ZnO-CTS NPs (with a concentration ranging from 0.625 to 0.156 mg/ml) as compared to control treatment. ZnO-CTS NPs also showed significant biofilm inhibition activity ( p aureus. The study demonstrated the potential of ZnO-CTS NPs as antimicrobial and antibiofilm agents.

  1. Facile synthesis and characterization of trimesic acid-Cu based metal organic frameworks

    Energy Technology Data Exchange (ETDEWEB)

    Sahiner, Nurettin, E-mail: sahiner71@gmail.com [Canakkale Onsekiz Mart University, Faculty of Sciences and Arts, Department of Chemistry, Terzioglu Campus, 17100 Canakkale (Turkey); Nanoscience and Technology Research and Application Center (NANORAC), Terzioglu Campus, 17100 Canakkale (Turkey); Sel, Kivanc [Canakkale Onsekiz Mart University, Faculty of Sciences and Arts, Department of Physics, Terzioglu Campus, 17100 Canakkale (Turkey); Nanoscience and Technology Research and Application Center (NANORAC), Terzioglu Campus, 17100 Canakkale (Turkey); Ozturk, Omer Faruk; Demirci, Sahin; Terzi, Gozde [Canakkale Onsekiz Mart University, Faculty of Sciences and Arts, Department of Chemistry, Terzioglu Campus, 17100 Canakkale (Turkey)

    2014-09-30

    Graphical abstract: - Highlights: • Various MOFs based on trimesic acid (TMA) and various Cu (II) salts. • Benign preparation of TMA-Cu based MOFs in DI water and ethanol. • TMA-Cu MOFs with the mole ratio of Cu(II) to TMA varying between 1.5 and 2. • TMA-Cu MOF with conductivity values were 8.26E−08–5.29E−11 (S/cm). - Abstract: Metal-organic frameworks based on trimesic acid (TMA) as organic linker and Cu (II) as metal ions from different metal salts such as CuCl{sub 2}, Cu(NO{sub 3}){sub 2}, CuSO{sub 4} and Cu(CH{sub 3}COOH){sub 2} were prepared in relatively environmentally friendly media e.g., at room temperature in DI water and at the boiling point of ethanol. The prepared TMA-Cu MOFs showed very interesting porosity and optical coloring based on the source of the used metal salts and preparation medium. The prepared MOFs were characterized in terms of their porosity with BET measurements and it was found that about 850 m{sup 2}/g for the MOF prepared from Cu(NO{sub 3}){sub 2} salt in ethanol. The amounts of metal ions connected to TMA were determined by atomic absorption spectroscopy measurements (AAS) after dissolution of TMA-Cu MOFs by concentrated HCl treatments. From AAS measurements the mole ratio of Cu(II) to TMA was found to vary between 1.5 and 2, depending on the source of metal ions and the solvent used during preparation. The structural analysis and thermal characterization of the prepared MOFs were done by using FT-IR and TGA analysis, respectively. Additionally, TMA-Cu based MOF disks were prepared and their conductivities were determined by I–V measurements. The conductivity of TMA-Cu MOFs was calculated to be between 8.26E−08 and 5.29E−11 S/cm.

  2. ZnCr2O4 Nanoparticles: Facile Synthesis, Characterization, and Photocatalytic Properties

    Science.gov (United States)

    Mousavi, Zahra; Soofivand, Faezeh; Esmaeili-Zare, Mahdiyeh; Salavati-Niasari, Masoud; Bagheri, Samira

    2016-02-01

    In this work, zinc chromite (ZnCr2O4) nanostructures have been synthesized through co-precipitation method. The effect of various parameters such as alkaline agent, pH value, and capping agent type was investigated on purity, particle size and morphology of samples. It was found that particle size and morphology of the products could be greatly influenced via these parameters. The synthesized products were characterized by field emission scanning electron microscopy (FESEM), X-ray diffraction (XRD), fourier transform infrared (FT-IR) spectra, X-ray energy dispersive spectroscopy (EDS), photoluminescence (PL) spectroscopy, diffuse reflectance spectroscopy (DRS) and vibrating sample magnetometry (VSM). The superhydrophilicity of the calcined oxides was investigated by wetting experiments and a sessile drop technique which carried out at room temperature in air to determine the surface and interfacial interactions. Furthermore, the photocatalytic activity of ZnCr2O4 nanoparticles was confirmed by degradation of anionic dyes such as Eosin-Y and phenol red under UV light irradiation. The obtained ZnCr2O4 nanoparticles exhibit a paramagnetic behavior although bulk ZnCr2O4 is antiferromagnetic, this change in magnetic property can be ascribed to finite size effects.

  3. Characterization and monitoring of 300 Area facility liquid waste streams: 1994 Annual report

    Energy Technology Data Exchange (ETDEWEB)

    Riley, R.G.; Ballinger, M.Y.; Damberg, E.G.; Evans, J.C.; Julya, J.L.; Olsen, K.B.; Ozanich, R.M.; Thompson, C.J.; Vogel, H.R.

    1995-04-01

    This report summarizes the results of characterizing and monitoring the following sources during calendar year 1994: liquid waste streams from Buildings 306, 320, 324, 326, 331, and 3720 in the 300 Area of Hanford Site and managed by the Pacific Northwest Laboratory; treated and untreated Columbia River water (influent); and water at the confluence of the waste streams (that is, end-of-pipe). Data were collected from March to December before the sampling system installation was completed. Data from this initial part of the program are considered tentative. Samples collected were analyzed for chemicals, radioactivity, and general parameters. In general, the concentrations of chemical and radiological constituents and parameters in building wastewaters which were sampled and analyzed during CY 1994 were similar to historical data. Exceptions were the occasional observances of high concentrations of chloride, nitrate, and sodium that are believed to be associated with excursions that were occurring when the samples were collected. Occasional observances of high concentrations of a few solvents also appeared to be associated with infrequent building r eases. During calendar year 1994, nitrate, aluminum, copper, lead, zinc, bis(2-ethylhexyl) phthalate, and gross beta exceeded US Environmental Protection Agency maximum contaminant levels.

  4. Characterization and monitoring of 300 Area facility liquid waste streams: 1994 Annual report

    International Nuclear Information System (INIS)

    This report summarizes the results of characterizing and monitoring the following sources during calendar year 1994: liquid waste streams from Buildings 306, 320, 324, 326, 331, and 3720 in the 300 Area of Hanford Site and managed by the Pacific Northwest Laboratory; treated and untreated Columbia River water (influent); and water at the confluence of the waste streams (that is, end-of-pipe). Data were collected from March to December before the sampling system installation was completed. Data from this initial part of the program are considered tentative. Samples collected were analyzed for chemicals, radioactivity, and general parameters. In general, the concentrations of chemical and radiological constituents and parameters in building wastewaters which were sampled and analyzed during CY 1994 were similar to historical data. Exceptions were the occasional observances of high concentrations of chloride, nitrate, and sodium that are believed to be associated with excursions that were occurring when the samples were collected. Occasional observances of high concentrations of a few solvents also appeared to be associated with infrequent building r eases. During calendar year 1994, nitrate, aluminum, copper, lead, zinc, bis(2-ethylhexyl) phthalate, and gross beta exceeded US Environmental Protection Agency maximum contaminant levels

  5. Modification and characterization of a high-energy photon irradiation facility using nitrogen-16

    Science.gov (United States)

    Roy, Tapash Kumar

    This work involves fabrication and characterization of a reactor source of high energy (˜7 MeV) nitrogen-16 photons for application in evaluation of dosimetric responses of personnel devices and portable instruments. The N-16 source has been established by continuously flowing coolant water from the core of a 1 MW research reactor through a cylindrical thin walled aluminium chamber. Dose measurements have been made at selected distances of interest along the depth axis both for with and without a near-air equilibrium wall of polymethyl methacrylate (PMMA) in place. Photon dose and exposure measurements were done using condenser-R ionization chambers with sufficiently thick walls to yield an approximate transient charged particle equilibrium (TCPE) condition. Field areal uniformity was defined using large area Kodak Readypack RP films along with lead foil radiators. Dosimetric quantities of interest include skin dose, eye (lens) dose, and 1 cm deep dose. Measurements were made at selected depths of 7, 300, and 1000 mg cm-2 for specific evaluation of these respective quantities. Photon spectral analysis was performed with a NaI(Tl) scintillation spectrometry system. Additionally, beta radiation measurements, and evaluation of neutron dose contributions to the radiation field were completed.

  6. Materials Characterization at Utah State University: Facilities and Knowledge-base of Electronic Properties of Materials Applicable to Spacecraft Charging

    Science.gov (United States)

    Dennison, J. R.; Thomson, C. D.; Kite, J.; Zavyalov, V.; Corbridge, Jodie

    2004-01-01

    In an effort to improve the reliability and versatility of spacecraft charging models designed to assist spacecraft designers in accommodating and mitigating the harmful effects of charging on spacecraft, the NASA Space Environments and Effects (SEE) Program has funded development of facilities at Utah State University for the measurement of the electronic properties of both conducting and insulating spacecraft materials. We present here an overview of our instrumentation and capabilities, which are particularly well suited to study electron emission as related to spacecraft charging. These measurements include electron-induced secondary and backscattered yields, spectra, and angular resolved measurements as a function of incident energy, species and angle, plus investigations of ion-induced electron yields, photoelectron yields, sample charging and dielectric breakdown. Extensive surface science characterization capabilities are also available to fully characterize the samples in situ. Our measurements for a wide array of conducting and insulating spacecraft materials have been incorporated into the SEE Charge Collector Knowledge-base as a Database of Electronic Properties of Materials Applicable to Spacecraft Charging. This Database provides an extensive compilation of electronic properties, together with parameterization of these properties in a format that can be easily used with existing spacecraft charging engineering tools and with next generation plasma, charging, and radiation models. Tabulated properties in the Database include: electron-induced secondary electron yield, backscattered yield and emitted electron spectra; He, Ar and Xe ion-induced electron yields and emitted electron spectra; photoyield and solar emittance spectra; and materials characterization including reflectivity, dielectric constant, resistivity, arcing, optical microscopy images, scanning electron micrographs, scanning tunneling microscopy images, and Auger electron spectra. Further

  7. Characterization of infectious aerosols in health care facilities: an aid to effective engineering controls and preventive strategies.

    Science.gov (United States)

    Cole, E C; Cook, C E

    1998-08-01

    Assessment of strategies for engineering controls for the prevention of airborne infectious disease transmission to patients and to health care and related workers requires consideration of the factors relevant to aerosol characterization. These factors include aerosol generation, particle size and concentrations, organism viability, infectivity and virulence, airflow and climate, and environmental sampling and analysis. The major focus on attention to engineering controls comes from recent increases in tuberculosis, particularly the multidrug-resistant varieties in the general hospital population, the severely immunocompromised, and those in at-risk and confined environments such as prisons, long-term care facilities, and shelters for the homeless. Many workers are in close contact with persons who have active, undiagnosed, or insufficiently treated tuberculosis. Additionally, patients and health care workers may be exposed to a variety of pathogenic human viruses, opportunistic fungi, and bacteria. This report therefore focuses on the nature of infectious aerosol transmission in an attempt to determine which factors can be systematically addressed to result in proven, applied engineering approaches to the control of infectious aerosols in hospital and health care facility environments. The infectious aerosols of consideration are those that are generated as particles of respirable size by both human and environmental sources and that have the capability of remaining viable and airborne for extended periods in the indoor environment. This definition precludes skin and mucous membrane exposures occurring from splashes (rather than true aerosols) of blood or body fluids containing infectious disease agents. There are no epidemiologic or laboratory studies documenting the transmission of bloodborne virus by way of aerosols. PMID:9721404

  8. Characterizing Hohlraum Plasma Conditions at the National Ignition Facility (NIF) Using X-ray Spectroscopy

    Science.gov (United States)

    Barrios, Maria Alejandra

    2015-11-01

    Improved hohlraums will have a significant impact on increasing the likelihood of indirect drive ignition at the NIF. In indirect-drive Inertial Confinement Fusion (ICF), a high-Z hohlraum converts laser power into a tailored x-ray flux that drives the implosion of a spherical capsule filled with D-T fuel. The x-radiation drive to capsule coupling sets the velocity, adiabat, and symmetry of the implosion. Previous experiments in gas-filled hohlraums determined that the laser-hohlraum energy coupling is 20-25% less than modeled, therefore identifying energy loss mechanisms that reduce the efficacy of the hohlraum drive is central to improving implosion performance. Characterizing the plasma conditions, particularly the plasma electron temperature (Te) , is critical to understanding mechanism that affect the energy coupling such as the laser plasma interactions (LPI), hohlraum x-ray conversion efficiency, and dynamic drive symmetry. The first Te measurements inside a NIF hohlraum, presented here, were achieved using K-shell X-ray spectroscopy of an Mn-Co tracer dot. The dot is deposited on a thin-walled CH capsule, centered on the hohlraum symmetry axis below the laser entrance hole (LEH) of a bottom-truncated hohlraum. The hohlraum x-ray drive ablates the dot and causes it to flow upward, towards the LEH, entering the hot laser deposition region. An absolutely calibrated streaked spectrometer with a line of sight into the LEH records the temporal history of the Mn and Co X-ray emission. The measured (interstage) Lyα/ Heα line ratios for Co and Mn and the Mn-Heα/Co-Heα isoelectronic line ratio are used to infer the local plasma Te from the atomic physics code SCRAM. Time resovled x-ray images perpendicular to the hohlraum axis record the dot expansion and trajectory into the LEH region. The temporal evolution of the measured Te and dot trajectory are compared with simulations from radiation-hydrodynamic codes. This work was performed under the auspices of the U

  9. CSER 94-013: Classification and access to PFP 232-Z Incinerator Facility and limits on characterization and disassembly activities in 232-Z burning hood

    International Nuclear Information System (INIS)

    This CSER justifies the Limited Control Facility designation for the closed Burning Hood in the PFP 232-Z Incinerator Facility. If the Burning Hood is opened to characterize the plutonium distribution and geometric integrity of the internals or for disassembly of the internals, then the more rigorous Fissionable Material Facility classification is required. Two sets of requirements apply for personnel access, criticality firefighting category for water use, and fissile material movement for the two states of the Burning Hood. The parameters used in the criticality analysis are listed to establish the limits under which this CSER is valid. Determination that the Burning Hood fissile material, moderation, or internal arrangements are outside these limits requires reevaluation of these parameter values and activities at the 232-Z Incinerator Facility. When the Burning Hood is open, water entry is to be prevented by two physical barriers for each water source

  10. 3D Seismic Characterization of the Research Facility for Geological Storage of CO2: Hontomín (Burgos, Spain)

    Science.gov (United States)

    Alcalde, J.; Martí, D.; Calahorrano, A.; Marzan, I.; Ayarza, P.; Carbonell, R.; Perez-Estaun, A.

    2011-12-01

    A technological research facility dedicated to the underground geological storage of CO2 is currently being developed by the Spanish research program on Carbon Capture and Storage (CCS) in Hontomin (Burgos, North of the Iberian Peninsula) This research program is being developed by the CIUDEN Foundation. CIUDEN is an initiative of 3 Spanish state departments (Science & Innovation, Environment and Industry). An extensive multidisciplinary site characterization phase has been carried out, including a multi-seismic data acquisition experiment. Within this effort a 36 km2 academic-oriented 3D seismic reflection survey was acquired in summer 2010. The aim of data acquisition effort are to provide high resolution images of the subsurface of the storage complex, constrain a baseline model for all the disciplines involved in the project. The main acquisition characteristics of this survey included: a mixed source (Vibroseis & explosive , 74% and 26% of the source points, respectively); 5000 shot points, distributed along 22 source lines (separated 250 m), 22 lines of receivers (separated 275 m); shot and receiver spacing along the source and receiver lines was of 25 m; this resulted in a nominal CDP-fold of 36 traces, with 13 m2 bins. This 3D-data was fully processed until migration. The main features within the processing sequence include static correction calculation, frequency filtering, trace amplitude equalization, rms velocity modeling, FK-domain filtering, 3D deconvolution, dip move-out corrections, residual static calculation and pre and post stack migration. The final high-resolution 3D-volume allowed to characterize the main tectonic structure of the dome complex, the fault system of the area and the feasibility of the reservoir for the storage. The target reservoir is a saline aquifer placed at 1400, approximately, within Lower Jurassic carbonates (Lias); the main seal is formed by inter-layered marls and marly limestones from Early to Middle Jurassic (Dogger

  11. Characterization of the transverse phase space at the photo-injector test facility in DESY, Zeuthen site

    Energy Technology Data Exchange (ETDEWEB)

    Staykov, Lazar

    2012-10-15

    High brightness electron beams with charge of 1 nC and low transverse emittance are necessary for the functioning of advanced light sources such as the Free-electron Laser in Hamburg (FLASH) and the European X-ray FEL (XFEL). The photo-injector test facility at DESY, Zeuthen site (PITZ) is dedicated to the optimization of such electron beams. At PITZ the electrons are produced using an RF gun cavity operated at accelerating gradients of up to 60 MV/m. The gun is equipped with a pair of solenoids for the compensation of the emittance growth due to linear space charge forces. This solenoid compensation scheme is enhanced with a properly matched TESLA type normal conducting booster cavity. The main tool for the characterization of the transverse phase space of the electron beam at PITZ is the emittance measurement system (EMSY). It employs the single slit method for the measurement of the transverse phase space distribution of the electron beam. In this thesis, the performance of the EMSY was optimized for measurement of low emittances in a wide range of photo-injector parameters including such that result in electron beams close to the XFEL specifications. First results on the characterization of the PITZ photo-injector with a gun operated at maximum accelerating gradient of 60 MV/m are presented. This includes scans of the solenoid focusing strength, the initial beam size and the booster gradient. A comparison between results obtained at lower accelerating gradients is made with emphasize on the benefit of higher accelerating gradient.

  12. Characterization of the transverse phase space at the photo-injector test facility in DESY, Zeuthen site

    International Nuclear Information System (INIS)

    High brightness electron beams with charge of 1 nC and low transverse emittance are necessary for the functioning of advanced light sources such as the Free-electron Laser in Hamburg (FLASH) and the European X-ray FEL (XFEL). The photo-injector test facility at DESY, Zeuthen site (PITZ) is dedicated to the optimization of such electron beams. At PITZ the electrons are produced using an RF gun cavity operated at accelerating gradients of up to 60 MV/m. The gun is equipped with a pair of solenoids for the compensation of the emittance growth due to linear space charge forces. This solenoid compensation scheme is enhanced with a properly matched TESLA type normal conducting booster cavity. The main tool for the characterization of the transverse phase space of the electron beam at PITZ is the emittance measurement system (EMSY). It employs the single slit method for the measurement of the transverse phase space distribution of the electron beam. In this thesis, the performance of the EMSY was optimized for measurement of low emittances in a wide range of photo-injector parameters including such that result in electron beams close to the XFEL specifications. First results on the characterization of the PITZ photo-injector with a gun operated at maximum accelerating gradient of 60 MV/m are presented. This includes scans of the solenoid focusing strength, the initial beam size and the booster gradient. A comparison between results obtained at lower accelerating gradients is made with emphasize on the benefit of higher accelerating gradient.

  13. Facile synthesis and characterization of water soluble ZnSe/ZnS quantum dots for cellar imaging

    Science.gov (United States)

    Shu, Chang; Huang, Bin; Chen, Xiangdong; Wang, Yan; Li, Xuequan; Ding, Li; Zhong, Wenying

    2013-03-01

    Strong fluorescence and low cytotoxicity ZnSe/ZnS quantum dots (QDs) were synthesized by a facile aqueous phase route. It overcame the defects such as instability and low quantum yield of the quantum dots synthesized by early aqueous phase route. L-Glutathione (GSH) and 3-mercaptopropaonic acid (MPA) were used as mixture stabilizers to synthesize high quality ZnSe/ZnS QDs. The samples were characterized by X-ray diffraction (XRD), high resolution transmission electron microscopy (HRTEM), X-ray photoelectron spectrometry (XPS) and their optical properties were investigated by using UV-vis spectrophotometer, fluorescence spectrophotometer (FL), IR spectrophotometer and confocal laser scanning microscope. The synthesized ZnSe/ZnS QDs illuminated blue fluorescence under ultraviolet lamp. Its water-soluble property is excellent and the fluorescence intensity of ZnSe/ZnS QDs almost did not change after 4 months at room temperature. The average diameter of ZnSe/ZnS nanocrystals is about 3 nm and quantum yield (QY) could reach to 70.6% after repeat determination. Low cytotoxicity was ensured by investigated SCG7901 and RAW264.7 cells. In comparison with cadmium based nanocrystals, ZnSe/ZnS QDs posed low cytotoxicity. The cells viability remained 96.7% when the QDs concentration was increased to 10 μmol/L. The results in vitro indicate that ZnSe/ZnS QDs-based probes have good stability, low toxicity and biocompatibility for fluorescence imaging in cancer model system.

  14. Ouellette Thermal Test Facility

    Data.gov (United States)

    Federal Laboratory Consortium — The Thermal Test Facility is a joint Army/Navy state-of-the-art facility (8,100 ft2) that was designed to: Evaluate and characterize the effect of flame and thermal...

  15. Site characterization summary report for the Old Hydrofracture Facility, Waste Area Grouping 5, at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-03-01

    The Old Hydrofracture (OHF) Facility was an experimental waste disposal test site located at the Oak Ridge National Laboratory (ORNL) in Oak Ridge, Tennessee. ORNL is a research facility owned by the U.S. Department of Energy (DOE) and managed by Lockheed Martin Energy Research Corp. Legacy environmental restoration sites, such as the OHF Facility, are managed for DOE by Lockheed Martin Energy Systems, Inc. This report summarizes the known conditions at the OHF Facility located in the southwest comer of Waste Area Grouping (WAG) 5 at ORNL. The facility covers about I acre within the approximate ORNL grid coordinates N17100-N17300 and E28500-E28700. The facility was used for the injection of liquid intermediate-level wastes (ILW) into a shale formation well below ground surface as a means of permanent disposal. Wastes remaining at the site after the last series of injections in 1980 can be found in buildings, waste pits, the retention pond, tanks, and piping. Based on a recent assessment of risk posed by these wastes, the contents of the tanks will be removed. Characterization data collected to date are provided in this report to facilitate waste removal activities.

  16. Characterization of the Hontomín Research Facility for Geological Storage of CO2: 3D Seismic Imaging Results

    Science.gov (United States)

    Alcalde, J.; Martí, D.; Juhlin, C.; Malehmir, A.; Calahorrano, A.; Ayarza, P.; Pérez-Estaún, A.; Carbonell, R.

    2012-04-01

    A technological research facility dedicated to the underground geological storage of CO2 is currently being developed by the Spanish research program on Carbon Capture and Storage (CCS) in Hontomin (Burgos). This research program is being developed by the CIUDEN Foundation, an initiative launched by 3 Spanish state departments (Science & Innovation, Environment and Industry). An extensive multidisciplinary site characterization phase has been carried out, including a multiseismic data acquisition experiment. Within this effort, a 36 km2 3D seismic reflection survey was acquired in the summer of 2010. Its aim was to provide high resolution images of the subsurface of the storage complex, as well as to provide a baseline model for all the disciplines involved in the project. The target reservoir is a saline aquifer located at 1400 m, approximately, within Lower Jurassic carbonates (Lias). The main seal is formed by inter-layered marls and marly limestones of Early to Middle Jurassic age (Dogger and Lias). The main acquisition characteristics of the survey included (1) a mixed source of vibroseis and explosives with 74% and 26% of each used, respectively, (2) 5000 source points distributed along 22 source lines (separated 250 m) and (3) 22 lines of receivers (separated 275 m). Shot and receiver spacing along the source and receiver lines was 25 m, resulting in a nominal CDP-fold of 36 for 13 m2 bins. The 3D-data have been fully processed to post stack migration. The most critical processing steps included static correction calculations, time variant frequency filtering, rms velocity analysis, F-XY deconvolution, dip move-out correction, residual statics calculations and post stack migration. The final high-resolution 3D-volume shows the shape and depth of the primary reservoir-seal system, the main faults of the area and the secondary reservoir-seal sequence. It allows us to characterize the main tectonic structure of the dome complex, the fault system of the area and

  17. Neutronic characterization and decay heat calculations in the in-vessel fuel storage facilities for MYRRHA/FASTEF

    OpenAIRE

    Di Maria, S.; Ottolini, M.; Malambu Mbala, E.; Sarotto, M.; Castelliti, D.

    2012-01-01

    The main objective of the Central Design Team (CDT) project is to establish an engineering design of a Fast Spectrum Transmutation Experimental Facility (FASTEF) that is the pilot plant of an experimental-scale of both an Accelerator Driven System (ADS) and a Lead Fast Reactor (LFR), based on the MYRRHA reactor concept, planned to be built during the next decade. The MYRRHA reactor concept is devoted to be a multi-purpose irradiation facility aimed at demonstrating the efficient transmutation...

  18. Characterization of the radiation environment at the UNLV accelerator facility during operation of the Varian M6 linac

    Science.gov (United States)

    Hodges, M.; Barzilov, A.; Chen, Y.; Lowe, D.

    2016-10-01

    The bremsstrahlung photon flux from the UNLV particle accelerator (Varian M6 model) was determined using MCNP5 code for 3 MeV and 6 MeV incident electrons. Human biological equivalent dose rates due to accelerator operation were evaluated using the photon flux with the flux-to-dose conversion factors. Dose rates were computed for the accelerator facility for M6 linac use under different operating conditions. The results showed that the use of collimators and linac internal shielding significantly reduced the dose rates throughout the facility. It was shown that the walls of the facility, in addition to the earthen berm enveloping the building, provide equivalent shielding to reduce dose rates outside to below the 2 mrem/h limit.

  19. Facile covalent immobilization of cadmium sulfide quantum dots on graphene oxide nanosheets : preparation, characterization, and optical properties

    NARCIS (Netherlands)

    Pham, Tuan Anh; Choi, Byung Choon; Jeong, Yeon Tae

    2010-01-01

    A facile approach for the preparation of a novel hybrid material containing graphene and an inorganic semiconducting material, cadmium sulfide quantum dots (CdS QDs), is demonstrated for the first time. First, amino-functionalized CdS QDs were prepared by modifications of the kinetic trapping method

  20. Design of a facility for the automated receipt inspection and characterization of LILW using integrated non-destructive examination and assay techniques

    International Nuclear Information System (INIS)

    KHNP is constructing two repositories, located in Bonggil-ri, Yangbukmyun, Gyeongju-si, Gyeongbuk, Korea, for Low and Intermediate Level radioactive waste (LILW). The waste received is required to be inspected and characterized prior to being placed into storage at the repository. This paper describes the design of an integrated system of non destructive examination (X-ray), and non destructive assay (radiometric) instrument systems, waste package integrity checking systems, waste handling mechanisms and data management and archival provisions, which comprise the Waste Receipt and Inspection Facility (WRIF). The WRIF is designed to uncap transport containers, unload waste drums from containers, safely examine the drums, to ensure they meet the waste acceptance criteria established by the LILW facility. The drums are then loaded into waste disposal containers for transfer to the repository. The WRIF also receives larger waste containers, which are characterized in a separate section of the WRIF, before being transferred to the repository. Remote control and handling of the waste is a design requirement, as well as the management, processing archival and retrieval system for all data generated during waste characterization. (authors)

  1. Neutronic characterization and decay heat calculations in the in-vessel fuel storage facilities for MYRRHA/FASTEF

    International Nuclear Information System (INIS)

    Highlights: ► Monte Carlo design of reactor facilities. ► Neutron coupling assessment between critical core and fresh fuel in the storage vessels. ► Power contribution by induced fission from neutrons leaving the core, spontaneous fission and (α, n) sources. ► Power decay heat estimation for different reactor fuel cycles scenarios. ► Material damage assessment in the storage vessels. - Abstract: The main objective of the Central Design Team (CDT) project is to establish an engineering design of a Fast Spectrum Transmutation Experimental Facility (FASTEF) that is the pilot plant of an experimental-scale of both an Accelerator Driven System (ADS) and a Lead Fast Reactor (LFR), based on the MYRRHA reactor concept, planned to be built during the next decade. The MYRRHA reactor concept is devoted to be a multi-purpose irradiation facility aimed at demonstrating the efficient transmutation of long-lived and high radiotoxicity minor actinides, fission products and the associated technology. An important issue regarding the reactor design of the MYRRHA/FASTEF experiment is the In-Vessel Fuel Storage Facilities (IVFSFs), both for fresh and spent fuel, as it might have an impact on the criticality of the overall system that must be quantified. In this work, the neutronic analysis of the in-vessel fuel storage facility and its coupling with the critical core was performed, using the state of the art Monte Carlo program MCNPX 2.6.0 and ORIGEN 2.2 computer code system for calculating the buildup and decay heat of spent fuel. Several parameters were analyzed, like the criticality behavior (namely the Keff), the neutron fluxes and their variations, the fission power production and the radiation damage (the displacements per atom). Finally, also the heat power generated by the fission products decay in the spent fuel was assessed.

  2. Characterization of stormwater at selected South Carolina Department of Transportation maintenance yard and section shed facilities in Ballentine, Conway, and North Charleston, South Carolina, 2010-2012

    Science.gov (United States)

    Journey, Celeste A.; Conlon, Kevin J.

    2013-01-01

    The South Carolina Department of Transportation operates section shed and maintenance yard facilities throughout the State. The U.S. Geological Survey conducted a cooperative investigation with the South Carolina Department of Transportation to characterize water-quality constituents that are transported in stormwater from representative maintenance yard and section shed facilities in South Carolina. At a section shed in Ballentine, S.C., stormwater discharges to a retention pond outfall (Ballentine). At the Conway maintenance yard, stormwater in the southernmost section discharges to a pipe outfall (Conway1), and stormwater in the remaining area discharges to a grass-lined ditch (Conway2). At the North Charleston maintenance yard, stormwater discharges from the yard to Turkey Creek through a combination of pipes, ditches, and overland flow; therefore, samples were collected from the main channel of Turkey Creek at the upstream (North Charleston1) and downstream (North Charleston2) limits of the North Charleston maintenance yard facility. The storms sampled during this study had a wide range of rainfall amounts, durations, and intensities at each of the facilities and, therefore, were considered to be reasonably representative of the potential for contaminant transport. At all facilities, stormwater discharge was significantly correlated to rainfall amount and intensity. Event-mean unit-area stormwater discharge increased with increasing impervious surface at the Conway and North Charleston maintenance yards. The Ballentine facility with 79 percent impervious surface had a mean unit-area discharge similar to that of the North Charleston maintenance yard (62 percent impervious surface). That similarity may be attributed, in part, to the effects of the retention pond on the stormwater runoff at the Ballentine facility and to the greater rainfall intensities and amounts at the North Charleston facility. Stormwater samples from the facilities were analyzed for multiple

  3. Performance and Facility Background Pressure Characterization Tests of NASAs 12.5-kW Hall Effect Rocket with Magnetic Shielding Thruster

    Science.gov (United States)

    Kamhawi, Hani; Huang, Wensheng; Haag, Thomas; Shastry, Rohit; Thomas, Robert; Yim, John; Herman, Daniel; Williams, George; Myers, James; Hofer, Richard; Mikellides, Ioannis; Sekerak, Michael; Polk, James

    2015-01-01

    NASA's Space Technology Mission Directorate (STMD) Solar Electric Propulsion Technology Demonstration Mission (SEP/TDM) project is funding the development of a 12.5-kW Hall thruster system to support future NASA missions. The thruster designated Hall Effect Rocket with Magnetic Shielding (HERMeS) is a 12.5-kW Hall thruster with magnetic shielding incorporating a centrally mounted cathode. HERMeS was designed and modeled by a NASA GRC and JPL team and was fabricated and tested in vacuum facility 5 (VF5) at NASA GRC. Tests at NASA GRC were performed with the Technology Development Unit 1 (TDU1) thruster. TDU1's magnetic shielding topology was confirmed by measurement of anode potential and low electron temperature along the discharge chamber walls. Thermal characterization tests indicated that during full power thruster operation at peak magnetic field strength, the various thruster component temperatures were below prescribed maximum allowable limits. Performance characterization tests demonstrated the thruster's wide throttling range and found that the thruster can achieve a peak thruster efficiency of 63% at 12.5 kW 500 V and can attain a specific impulse of 3,000 s at 12.5 kW and a discharge voltage of 800 V. Facility background pressure variation tests revealed that the performance, operational characteristics, and magnetic shielding effectiveness of the TDU1 design were mostly insensitive to increases in background pressure.

  4. Characterization of the extent of Mercury Contamination in the Androscoggin River from a former Chlor-alkali Facility, Berlin, New Hampshire

    Science.gov (United States)

    Chalmers, A.; Marvin-Dipasquale, M. C.; Rosiu, C.; Luce, D.; Coles, J.; Zimmerman, M.; Smith, T.

    2010-12-01

    From the late 1800s to the 1960s a chlor-alkali plant was used to produce chlorine gas for the papermaking industry in Berlin, New Hampshire. During operation of the chlor-alkali facility, elemental mercury (Hg) was released to the environment, contaminating soils and the underlying fractured rock. Investigations have revealed that elemental Hg continues to seep through bedrock fractures into the adjacent Androscoggin River. This study evaluates the extent and transformation of Hg contamination in the Androscoggin River by comparing a reference site 17 kilometers above the former chlor-alkali facility to 5 sites ranging from 1 to 16 km downstream from the facility. Total and methyl Hg (THg and MeHg, respectively), among other analytes, were characterized in surface water, pore water, sediment and biological tissue samples at each site. Bed sediment was also assessed for bio-available (tin-reducible) inorganic Hg (II) and microbial MeHg production potential rates. Acid extractable ferrous iron, crystalline and amorphous (poorly crystalline) ferric iron, total reduced sulfur, particle size, and organic content in bed sediment was analyzed to help explain spatial differences in MeHg production rates and bio-available Hg (II) among sites. The information provided by this study will help evaluate the extent of Hg contamination in the Androscoggin River, will improve our understanding of the controls on MeHg production in the Androscoggin River system, and will be used by the U.S. Environmental Protection Agency to support remediation of the chlor-alkali facility site.

  5. Description of work for vadose zone characterization of the 1301-N and 1325-N liquid waste disposal facilities

    International Nuclear Information System (INIS)

    This description of work (DOW) details the field activities associated with a limited field investigation (LFI) of soil contamination beneath the 1301-N and 1325-N Liquid Waste Disposal Facilities (LWDFs), and will serve as a field guide for those performing the work. These activities are undertaken pursuant to the Hanford Federal Facility Agreement and consent Order (Tri-Party Agreement) (Ecology et al. 1994a) Milestone M-16-94-01H-T1 and the June 30, 1994, Milestone Change Request M-16-94-02 (Ecology et al. 1994b). The scope of these activities was defined during a Streamlined Approach for Environmental Restoration (SAFER) workshop and a US Department of Energy, Richland Operations Office (RL) workshop where data quality objectives (DQOs) and technical criteria for the LFI were developed. Results of the SAFER workshop are discussed in Section 1.1. the locations of the 1301-N and 1325-N LWDFs (116-N-1 and 116-N-3) are shown in Figure 1. Both the 1301-N and 1325-N LWDFs consist o a crib and a trench. Both LWDFs were used to receive and dispose of the cooling water originating from the 100-N Reactor and are classified as RCRA treatment, storage, and/or disposal (TSD) units. The LWDFs are no longer receiving waste effluent. Although these facilities are classified as RCRA TSD units, the RL and regulatory agencies have determined that this LFI will be conducted as a past-practice investigation under the auspices of the Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA), in accordance with the Hanford Site Past-Practice Investigation Strategy (DOE-RL 1991) and the 100-NR-1 Operable Unit RFI/CMS Work Plan (DOE-RL 1994)

  6. Concept of operations for channel characterization and simulation of coaxial transmission channels at the National Ignition Facility (NIF)

    Energy Technology Data Exchange (ETDEWEB)

    Brown, Jr., Charles G. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

    2015-03-23

    The National Ignition Facility (NIF) at Lawrence Livermore National Laboratory (LLNL) executes experiments for inertial con nement fusion (ICF), world-class high energy density physics (HEDP), and critical national security missions. While the laser systems, target positioners, alignment systems, control systems, etc. enable the execution of such experiments, NIF’s utility would be greatly reduced without its suite of diagnostics. It would be e ectively “blind” to the incredible physics unleashed in its target chamber. Since NIF diagnostics are such an important part of its mission, the quality and reliability of the diagnostics, and of the data recorded from them, is crucial.

  7. Characterization of x-ray framing cameras for the National Ignition Facility using single photon pulse height analysis

    Science.gov (United States)

    Holder, J. P.; Benedetti, L. R.; Bradley, D. K.

    2016-11-01

    Single hit pulse height analysis is applied to National Ignition Facility x-ray framing cameras to quantify gain and gain variation in a single micro-channel plate-based instrument. This method allows the separation of gain from detectability in these photon-detecting devices. While pulse heights measured by standard-DC calibration methods follow the expected exponential distribution at the limit of a compound-Poisson process, gain-gated pulse heights follow a more complex distribution that may be approximated as a weighted sum of a few exponentials. We can reproduce this behavior with a simple statistical-sampling model.

  8. Facile synthesis and characterization of novel thermo-chromism cholesteryl-containing hydrogen-bonded liquid crystals

    Institute of Scientific and Technical Information of China (English)

    Wan Li He; Tao Liu; Zhou Yang; Dong Yu Zhao; Wei Huang; Hui Cao; Guo Jie Wang; Huai Yang

    2009-01-01

    Two series of novel cholesteryl-containing H-bonded liquid crystals were prepared through facile self-assembly between cholesteryl isonicotinate (proton acceptor) exhibiting a monotropic cholesteric phase, and the 4-alkoxy-benzoic acid or 4-alkoxy cinnamic acid (proton donor). It was found that the increase of the conjugate length as well as the terminal length can contribute to enhance the interaction of molecules and thus significantly influenced the thermal behaviors of H-bonded LCs. The cholesteric reflection spectra of the induced mesogenic complexes were located in the visible region with the color tuneable thermo-sensitivity, which could be used for display application.

  9. Study on the characterization of the neutron radiography facility in HANARO for two-phase flow research

    International Nuclear Information System (INIS)

    For the application of dynamic neutron radiography to the two-phase flow research using HANARO, several experimental items to which the radiography technique is beneficial were identified through the review of the outputs from the related researches and the discussions with experts. Also, the investigation of the equipments including the beam port, camera and converter was made and a hardware and a software for image processing were equipped. It was confirmed that the calibration curve for the attenuation of neutron beam in fluid which is required for the two-phase flow experiment could be obtained by the computer code calculation. Based on the investigation results on the equipment and the results from the measurement of BNCT beam characteristics, a high speed camera and an image intensifier will be purchased. Then, the high speed dynamic neutron radiography facility for two-phase flow experiments will be fully equipped

  10. Scope and dissolution studies and characterization of irradiated nuclear fuel in Atalante Hot Cell Facilities (abstract and presentation slides)

    Energy Technology Data Exchange (ETDEWEB)

    Dancausse, Jean-Philippe; Reynier Tronche, Nathalie; Ferlay, Gilles; Herlet, Nathalie; Eysseric, Cathrine; Esbelin, Eric

    2005-01-01

    Since 1999, several studies on nuclear fuels were realised in C11/C12 Atalante Hot Cell. This paper presents firstly an overview of the apparatus used for fuel dissolution and characterisation like reactor design, gas trapping flask and solid/liquid separation. Then, the general methodology is described as a function of fuel, temperature, reagents, showing for each step, the reachable experimental data: Dissolution rate, chemical and radiochemical fuel composition including volatile LLRN, insoluble mass, composition, morphology, cladding chemical, radiochemical and physical characterisation using SIMS (made in Cadarache/LECA facilities), MEB. To conclude, some of the obtained results on 129I and 14C composition of oxide fuels, rate of dissolution and first results on dissolution studies of RERTR UMo fuel will be detailed. (Author)

  11. Study on the characterization of the neutron radiography facility in HANARO for two-phase flow research

    Energy Technology Data Exchange (ETDEWEB)

    Lim, I. C.; Seo, C. G.; Jeong, J. H.; Lee, B. H.; Choi, Y. S

    2001-01-01

    For the application of dynamic neutron radiography to the two-phase flow research using HANARO, several experimental items to which the radiography technique is beneficial were identified through the review of the outputs from the related researches and the discussions with experts. Also, the investigation of the equipments including the beam port, camera and converter was made and a hardware and a software for image processing were equipped. It was confirmed that the calibration curve for the attenuation of neutron beam in fluid which is required for the two-phase flow experiment could be obtained by the computer code calculation. Based on the investigation results on the equipment and the results from the measurement of BNCT beam characteristics, a high speed camera and an image intensifier will be purchased. Then, the high speed dynamic neutron radiography facility for two-phase flow experiments will be fully equipped.

  12. Characterization of a tungsten/gas multislit collimator for microbeam radiation therapy at the European Synchrotron Radiation Facility

    Science.gov (United States)

    Bräuer-Krisch, E.; Bravin, A.; Zhang, L.; Siegbahn, E.; Stepanek, J.; Blattmann, H.; Slatkin, D. N.; Gebbers, J.-O.; Jasmin, M.; Laissue, J. A.

    2005-06-01

    Clinical microbeam radiation therapy (MRT) will require a multislit collimator with adjustable uniform slit widths to enable reliable Monte Carlo-based treatment planning. Such a collimator has been designed, fabricated of >99% tungsten [W] by Tecomet/Viasys (Woburn, Massachusetts, USA) and installed at the 6GeV electron-wiggler-generated hard x-ray ID17 beamline of the European Synchrotron Radiation Facility. Its pair of 125 parallel, 8mm deep, 0.100mm wide radiolucent slits, 0.400mm on center, are perfused with nitrogen gas [N2] to dissipate heat during irradiation. Major improvements in uniformity of microbeam widths and good peak/valley dose ratios combined with a very high dose rate in targeted tissues have been achieved.

  13. Selection of a Site for a Near-Surface Disposal Facility: A Joint Report on Characterization of Sites

    International Nuclear Information System (INIS)

    Report describes general and safety-relevant environmental conditions of investigated sites and provides an overview of information concerning wastes to be disposed of. Safety relevant design aspects are given in the Project Report on Reference Design for a Near-Surface Disposal Facility for Low-and Intermediate-Level Short-Lived Radioactive Waste in Lithuania. This Report summarizes results of investigations performed during 2003-2005 by a number of researchers and evaluated by RATA. The work was performed by the Institute of Geology and Geography, the Lithuanian Energy Institute, Vilnius University, the Institute of Chemistry, UAB Grota, the Lithuanian Geological Survey, Swedish consultants from Geodevelopment, SKB and SKI-ICP, and generalized by RATA

  14. Preclosure radiological safety analysis for accident conditions of the potential Yucca Mountain Repository: Underground facilities; Yucca Mountain Site Characterization Project

    Energy Technology Data Exchange (ETDEWEB)

    Ma, C.W.; Sit, R.C.; Zavoshy, S.J.; Jardine, L.J. [Bechtel National, Inc., San Francisco, CA (United States); Laub, T.W. [Sandia National Labs., Albuquerque, NM (United States)

    1992-06-01

    This preliminary preclosure radiological safety analysis assesses the scenarios, probabilities, and potential radiological consequences associated with postulated accidents in the underground facility of the potential Yucca Mountain repository. The analysis follows a probabilistic-risk-assessment approach. Twenty-one event trees resulting in 129 accident scenarios are developed. Most of the scenarios have estimated annual probabilities ranging from 10{sup {minus}11}/yr to 10{sup {minus}5}/yr. The study identifies 33 scenarios that could result in offsite doses over 50 mrem and that have annual probabilities greater than 10{sup {minus}9}/yr. The largest offsite dose is calculated to be 220 mrem, which is less than the 500 mrem value used to define items important to safety in 10 CFR 60. The study does not address an estimate of uncertainties, therefore conclusions or decisions made as a result of this report should be made with caution.

  15. Facile approach to synthesize magnesium oxide nanoparticles by using Clitoria ternatea—characterization and in vitro antioxidant studies

    Science.gov (United States)

    John Sushma, N.; Prathyusha, D.; Swathi, G.; Madhavi, T.; Deva Prasad Raju, B.; Mallikarjuna, K.; Kim, Hak-Sung

    2016-03-01

    Facile approach to synthesize the metal oxide nanoparticles is getting an increased attention in various biomedical applications such as, to treat antibiotic resistant diseases. Magnesium oxide nanoparticles (MgO·NPs) were synthesized by using Clitoria ternatea as the stabilizer in a green synthesis approach. The preliminary screening of MgO·NPs in the presence of C. ternatea extract was observed by UV-visible spectrophotometer. X-ray diffraction (XRD) pattern have proved the crystalline nature of the MgO·NPs; Photoluminescence (PL) measurement studies are used to identify the quality and defects in the crystal structure. FE-SEM with EDS has showed the size of 50-400 nm with specific binding energies. FT-IR has revealed the functional groups present in the plant extract and the peak at 521 cm-1 indicated the characteristic absorption bands of MgO·NPs. The DPPH activity and reducing power assay of biologically synthesized MgO·NPs could reach 65 % at a concentration of 150 µg/ml, respectively. From the results it was concluded that the biologically synthesized MgO·NPs exhibit good antioxidant activity.

  16. Low background infrared (LBIR) facility

    Data.gov (United States)

    Federal Laboratory Consortium — The Low background infrared (LBIR) facility was originally designed to calibrate user supplied blackbody sources and to characterize low-background IR detectors and...

  17. Final Report: Detection and Characterization of Underground Facilities by Stochastic Inversion and Modeling of Data from the New Generation of Synthetic Aperture Satellites

    Energy Technology Data Exchange (ETDEWEB)

    Foxall, W; Cunningham, C; Mellors, R; Templeton, D; Dyer, K; White, J

    2012-02-27

    Many clandestine development and production activities can be conducted underground to evade surveillance. The purpose of the study reported here was to develop a technique to detect underground facilities by broad-area search and then to characterize the facilities by inversion of the collected data. This would enable constraints to be placed on the types of activities that would be feasible at each underground site, providing a basis the design of targeted surveillance and analysis for more complete characterization. Excavation of underground cavities causes deformation in the host material and overburden that produces displacements at the ground surface. Such displacements are often measurable by a variety of surveying or geodetic techniques. One measurement technique, Interferometric Synthetic Aperture Radar (InSAR), uses data from satellite-borne (or airborne) synthetic aperture radars (SARs) and so is ideal for detecting and measuring surface displacements in denied access regions. Depending on the radar frequency and the acquisition mode and the surface conditions, displacement maps derived from SAR interferograms can provide millimeter- to centimeter-level measurement accuracy on regional and local scales at spatial resolution of {approx}1-10 m. Relatively low-resolution ({approx}20 m, say) maps covering large regions can be used for broad-area detection, while finer resolutions ({approx}1 m) can be used to image details of displacement fields over targeted small areas. Surface displacements are generally expected to be largest during or a relatively short time after active excavation, but, depending on the material properties, measurable displacement may continue at a decreasing rate for a considerable time after completion. For a given excavated volume in a given geological setting, the amplitude of the surface displacements decreases as the depth of excavation increases, while the area of the discernable displacement pattern increases. Therefore, the

  18. Design and Characterization of a Neutron Calibration Facility for the Study of sub-keV Nuclear Recoils

    CERN Document Server

    Barbeau, P S; Whaley, P M

    2007-01-01

    As part of an experimental effort to demonstrate sensitivity in a large-mass detector to the ultra-low energy recoils expected from coherent neutrino-nucleus elastic scattering, we have designed and built a highly monochromatic 24 keV neutron beam at the Kansas State University Triga Mark-II reactor. The beam characteristics were chosen so as to mimic the soft recoil energies expected from reactor antineutrinos in a variety of targets, allowing to understand the response of detector technologies in this yet unexplored sub-keV recoil range. A full characterization of the beam properties (intensity, monochromaticity, contaminations, beam profile) is presented, together with first tests of the calibration setup using proton recoils in organic scintillator.

  19. Preliminary examination of the impacts of repository site characterization activities and facility construction and operation activities on Hanford air quality

    Energy Technology Data Exchange (ETDEWEB)

    Glantz, C.S.; Ramsdell, J.V.

    1986-04-01

    Air quality impacts that would result from site characterization activities and from the construction and operation of a high-level nuclear wste repository at Hanford are estimated using two simple atmospheric dispersion models, HANCHI and CHISHORT. Model results indicate that pollutant concentrations would not exceed ambient air quality standards at any point outside the Hanford fenceline or at any publicly accessible location within the Hanford Site. The increase in pollutant concentrations in nearby communities due to site activities would be minimal. HANCHI and CHISHORT are documented in the appendices of this document. Further study of the repository's impact on air quality will be conducted when more detailed project plans and work schedules are available.

  20. CdS nanocrystals/TiO2/crosslinked chitosan composite: Facile preparation, characterization and adsorption-photocatalytic properties

    International Nuclear Information System (INIS)

    CdS nanocrystals deposited on TiO2/crosslinked chitosan composite (CdS/TiO2/CSC) were prepared in an attempt to photocatalyze decolorization of water soluble azo dye in aqueous solution under simulated solar light irradiation. CdS/TiO2/CSC was characterized by X-ray diffraction (XRD), energy-dispersive spectroscopy (EDS), and scanning electron microscopy (SEM). The characterization results proved that CdS nanocrystals has successfully been deposited on/in TiO2/crosslinked chitosan composite. The adsorption ability of CdS/TiO2/CSC was approximately 2.66 mg methyl orange (a typical water soluble azo dye) per gram. The photocatalytic decolorization of methyl orange solution reached 99.1% by CdS/TiO2/CSC after simulated solar light irradiation for 210 min. Kinetics analysis indicated that photocatalytic decolorization of methyl orange solution by CdS/TiO2/CSC obeyed first-order kinetic Langmuir-Hinshelwood mechanism (R2 > 0.997). CdS/TiO2/CSC exhibited enhanced photocatalytic activity under simulated solar light irradiation compared with photocatalysts reported before and the photocatalytic activity of CdS/TiO2/CSC maintained at 89.0% of initial decolorization rate after five batch reactions. The presence of NO3− accelerated the decolorization of methyl orange solution by CdS/TiO2/CSC, while SO42− and Cl− had an inhibitory effect on the decolorization of methyl orange. Therefore, present experimental results indicated to assess the applicability of CdS/TiO2/CSC as a suitable and promising photocatalyst for effective decolorization treatment of dye-containing effluents.

  1. CdS nanocrystals/TiO{sub 2}/crosslinked chitosan composite: Facile preparation, characterization and adsorption-photocatalytic properties

    Energy Technology Data Exchange (ETDEWEB)

    Zhu, Huayue [Key Laboratory for Biomass-Resource Chemistry and Environmental Biotechnology of Hubei Province, Colledge of Resource and Environment Science, Wuhan University, Wuhan 430072, Hubei (China); Laboratory of Resource Utilization and Pollution Control, College of Life Science, Taizhou University, Taizhou 318000, Zhejiang (China); Jiang, Ru [Laboratory of Resource Utilization and Pollution Control, College of Life Science, Taizhou University, Taizhou 318000, Zhejiang (China); Xiao, Ling, E-mail: xiaoling9119@yahoo.cn [Key Laboratory for Biomass-Resource Chemistry and Environmental Biotechnology of Hubei Province, Colledge of Resource and Environment Science, Wuhan University, Wuhan 430072, Hubei (China); Liu, Li; Cao, Chunhua [Key Laboratory for Biomass-Resource Chemistry and Environmental Biotechnology of Hubei Province, Colledge of Resource and Environment Science, Wuhan University, Wuhan 430072, Hubei (China); Zeng, Guangming [Key Laboratory of Environmental Biology and Pollution Control (Hunan University), Ministry of Education, Changsha 410082, Hunan (China)

    2013-05-15

    CdS nanocrystals deposited on TiO{sub 2}/crosslinked chitosan composite (CdS/TiO{sub 2}/CSC) were prepared in an attempt to photocatalyze decolorization of water soluble azo dye in aqueous solution under simulated solar light irradiation. CdS/TiO{sub 2}/CSC was characterized by X-ray diffraction (XRD), energy-dispersive spectroscopy (EDS), and scanning electron microscopy (SEM). The characterization results proved that CdS nanocrystals has successfully been deposited on/in TiO{sub 2}/crosslinked chitosan composite. The adsorption ability of CdS/TiO{sub 2}/CSC was approximately 2.66 mg methyl orange (a typical water soluble azo dye) per gram. The photocatalytic decolorization of methyl orange solution reached 99.1% by CdS/TiO{sub 2}/CSC after simulated solar light irradiation for 210 min. Kinetics analysis indicated that photocatalytic decolorization of methyl orange solution by CdS/TiO{sub 2}/CSC obeyed first-order kinetic Langmuir-Hinshelwood mechanism (R{sup 2} > 0.997). CdS/TiO{sub 2}/CSC exhibited enhanced photocatalytic activity under simulated solar light irradiation compared with photocatalysts reported before and the photocatalytic activity of CdS/TiO{sub 2}/CSC maintained at 89.0% of initial decolorization rate after five batch reactions. The presence of NO{sub 3}{sup −} accelerated the decolorization of methyl orange solution by CdS/TiO{sub 2}/CSC, while SO{sub 4}{sup 2−} and Cl{sup −} had an inhibitory effect on the decolorization of methyl orange. Therefore, present experimental results indicated to assess the applicability of CdS/TiO{sub 2}/CSC as a suitable and promising photocatalyst for effective decolorization treatment of dye-containing effluents.

  2. Error characterization of retrievals for active remote Sensing instruments in the ARM climate research facility at the Southern Great Plains site

    Science.gov (United States)

    Chandrasekar, C. V.; Hardin, J. C.; Jensen, M. P.

    2012-12-01

    The ARM Climate Research Facility deploys a network of highly instrumented ground stations, including both mobile and aerial facilities to support the study of global climate change by the national and international research community. The Southern Great Plains facility (SGP) hosts a network of C, X, and K band radars; some are in scanning mode and some are in vertically pointing mode. As an example, the Mid-Latitude Continental Convective Clouds Experiment (MC3E) (Jensen, et al. 2011), was a joint DOE Atmospheric Radiation Measurement (ARM) and NASA Global Precipitation Measurements (GPM) field campaign which took place from April - June 2011 in Central Oklahoma centered at the ARM SGP site. This paper presents retrieval methodologies for the ARM instrument suite with a focus on the error characterization for the radar measurements and the retrievals. There is extensive literature on retrieval algorithms for precipitation and cloud parameters from single frequency, dual-polarization radar systems. Multiple radar deployments are becoming more common, and the MC3E is a text book example of such a deployment. Additionally, networked deployments are becoming more common (Chandrasekar, et al. 2010), resulting in networked retrievals, initially used for attenuation mitigation. Since then, networked retrievals have expanded to include DSDs from networked X-band or Ku-band radars (Yoshikawa, et al., 2012). The above retrieval methodologies were for homogeneous, single frequency systems; the multi frequency nature of the deployment during the MC3E program is the motivation for the integrated formulation and error characterization presented in this paper. The set of radars consists of the NASA NPOL radar at S-band, as well as the C and X-band radars from the ARM program, namely the C-SAPR and X-SAPR family. This paper presents a comprehensive integrated retrieval methodology focusing on error characterization to obtain microphysical retrieval including drop size

  3. A facile synthesis and spectral characterization of Cu{sup 2+} doped CdO/ZnS nanocomposite

    Energy Technology Data Exchange (ETDEWEB)

    Joyce Stella, R.; Thirumala Rao, G.; Babu, B.; Pushpa Manjari, V. [Department of Physics, University College of Sciences, Acharya Nagarjuna University, Nagarjuna Nagar, AP 522510 (India); Reddy, Ch. Venkata; Shim, Jaesool [School of Mechanical Engineering, Yeungnam University, Gyeongsan 712-749 (Korea, Republic of); Ravikumar, R.V.S.S.N., E-mail: rvssn@yahoo.co.in [Department of Physics, University College of Sciences, Acharya Nagarjuna University, Nagarjuna Nagar, AP 522510 (India)

    2015-06-15

    A facile two-step method is demonstrated for the preparation of Cu{sup 2+} doped CdO/ZnS nanocomposite. Systematic investigations like X-ray diffraction (XRD), Scanning electron microscopy (SEM) with EDS, transmission electron microscopy (TEM), FT-IR, electron paramagnetic resonance (EPR), optical absorption, photoluminescence (PL) and magnetic studies are carried out for the prepared material. From powder XRD, the nanocomposites are comprised for cubic phase of both CdO and ZnS in a close contact with each other. The ground state wave function of dopant ions has been estimated from EPR studies. Optical and EPR data confirm that doped Cu{sup 2+}ions occupy rhombically distorted octahedral sites with the host material. Due to doping, band gap has been changed and blue shifts occurred in PL. Magnetic measurements indicate a possible ferromagnetic response, associated to the exchange interaction between local spin-polarized electrons of Cu{sup 2+} ions and conductive electrons. - Graphical abstract: M–H curve of Cu{sup 2+} doped CdO–ZnS nanocomposites. The magnetic properties of Cu{sup 2+} doped CdO/ZnS nanocomposite has been investigated using vibrating sample magnetometer given as magnetization and hysteresis (M–H) curve. The magnetization curve with noticeable coercivity of M–H loop clearly indicate the existence of ferromagnetic ordering in Cu{sup 2+} doped CdO/ZnS nanocomposite at room temperature. According to the Ruderman–Kittel–Kasuya–Yosida (RKKY) theory, the exchange interaction between local spin-polarized electrons (such as the electrons of Cu{sup 2+} ions) and conductive electrons is the main cause that leads to the ferromagnetism. Coercivity (Hc) of the field is about 98 Oe, saturation magnetization (Ms) and remnant magnetization (Mr) of present sample is estimated to be 15.8×10{sup −3} and 1.43×10{sup −3} emu/g respectively. The ferromagnetism observed in the prepared material is not commencing with other impurities but expected to

  4. Facilities & Leadership

    Data.gov (United States)

    Department of Veterans Affairs — The facilities web service provides VA facility information. The VA facilities locator is a feature that is available across the enterprise, on any webpage, for the...

  5. Facile synthesis, characterization, and antimicrobial activity of cellulose-chitosan-hydroxyapatite composite material: a potential material for bone tissue engineering.

    Science.gov (United States)

    Mututuvari, Tamutsiwa M; Harkins, April L; Tran, Chieu D

    2013-11-01

    Hydroxyapatite (HAp) is often used as a bone-implant material because it is biocompatible and osteoconductive. However, HAp possesses poor rheological properties and it is inactive against disease-causing microbes. To improve these properties, we developed a green method to synthesize multifunctional composites containing: (1) cellulose (CEL) to impart mechanical strength; (2) chitosan (CS) to induce antibacterial activity thereby maintaining a microbe-free wound site; and (3) HAp. In this method, CS and CEL were co-dissolved in an ionic liquid (IL) and then regenerated from water. HAp was subsequently formed in situ by alternately soaking [CEL+CS] composites in aqueous solutions of CaCl2 and Na2 HPO4 . At least 88% of IL used was recovered for reuse by distilling the aqueous washings of [CEL+CS]. The composites were characterized using FTIR, XRD, and SEM. These composites retained the desirable properties of their constituents. For example, the tensile strength of the composites was enhanced 1.9 times by increasing CEL loading from 20% to 80%. Incorporating CS in the composites resulted in composites which inhibited the growth of both Gram positive (MRSA, S. aureus and VRE) and Gram negative (E. coli and P. aeruginosa) bacteria. These findings highlight the potential use of [CEL+CS+HAp] composites as scaffolds in bone tissue engineering.

  6. A facile synthesis of poly(aniline-co-o-bromoaniline) copolymer: Characterization and application as semiconducting material

    Science.gov (United States)

    Mahudeswaran, A.; Vivekanandan, J.; Vijayanand, P. S.; Kojima, T.; Kato, S.

    2016-01-01

    Poly(aniline-co-o-bromoaniline) (p(an-co-o-BrAn)) copolymer has been synthesized using chemical oxidation method in the hydrochloric acid medium. Copolymerization of aniline with o-bromoaniline of different compositions, such as 1:1, 1:2, 2:1, 1:3 and 3:1 molar ratios were prepared. The synthesized copolymer is soluble in polar solvents like dimethyl sulphoxide (DMSO), dimethyl formamide (DMF), Tetrahydrofuran (THF) and 1-methyl 2-pyrrolidone (NMP). The copolymer is analyzed by various characterization techniques, such as FTIR, UV-Visible (UV-Vis) spectroscopy, X-ray diffraction (XRD), conductivity, Differential scanning calorimetry (DSC) and scanning electron microscopy (SEM). FTIR spectrum confirms the characteristic peaks of the copolymer containing benzenoid and quinoid ring stretching. UV spectrum reveals the formation of π-π∗ transition and n-π∗ transition between the energy levels. XRD peaks reveal that the copolymer possesses amorphous nature. Morphological study reveals that the agglomerated particles form globular structure and size of the each particle is about 100 nm. The electrical conductivity of the copolymers is found in the range of 10-5Scm-1. These organic semiconductor materials can be used to fabricate thinner and cheaper environmental friendly optoelectronic devices that will replace the conventional inorganic semiconductors.

  7. A neuron-in-capillary platform for facile collection and mass spectrometric characterization of a secreted neuropeptide

    Science.gov (United States)

    Lee, Chang Young; Fan, Yi; Rubakhin, Stanislav S.; Yoon, Sook; Sweedler, Jonathan V.

    2016-06-01

    The integration of microfluidic devices—which efficiently handle small liquid volumes—with separations/mass spectrometry (MS) is an effective approach for profiling the neurochemistry occurring in selected neurons. Interfacing the microfluidic cell culture to the mass spectrometer is challenging because of geometric and scaling issues. Here we demonstrate the hyphenation of a neuron-in-capillary platform to a solid phase extraction device and off-line MS. A primary neuronal culture of Aplysia californica neurons was established directly inside a cylindrical polyimide capillary. The approach also uses a particle-embedded monolith to condition neuropeptide releasates collected from several Aplysia neurons cultured in the capillary, with the subsequent characterization of released peptides via MS. This system presents a number of advances compared to more traditional microfluidic devices fabricated with polydimethylsiloxane. These include low cost, easy access to cell culture, rigidity, ease of transport, and minimal fluid handling. The cylindrical geometry of the platform allows convenient interface with a wide range of analytical tools that utilize capillary columns.

  8. Biochemistry Facility

    Data.gov (United States)

    Federal Laboratory Consortium — The Biochemistry Facility provides expert services and consultation in biochemical enzyme assays and protein purification. The facility currently features 1) Liquid...

  9. Characterization of the geochemical processes present in the radionuclides and metals mobilization in the tailing dam at the Uranium Mining and Milling Facilities - Pocos de Caldas, MG, Brazil

    International Nuclear Information System (INIS)

    In Brazil, the first step of nuclear fuel cycle - the mining and milling of the uranium ore - is developed at the Uranium Mining and Milling Facilities of Pocos de Caldas, Minas Gerais state. The wastes management is a very important aspect of the process. The understanding of the geochemical processes that occur in the tailings dam is a key question to define a plan of action concerning the decommissioning strategy of the facility. The objective of the present work was to give some issues to help in the adoption of the remedial actions concerning the decommissioning of the facility. It focused on the characterization of the most important geochemical processes regulating the mobilization of radionuclides and heavy metals in the tailings dam. Two cores from the tailings dam (uncovered area) were collected. Seepage and drainage waters were sampled, the same being true for the tailings dam lake. Groundwater form an aquifer bellow the tailings dam and superficial waters from a river that receives the effluents of the dam (Soberbo River) were also sampled. Data from the mining company were used to calculate the inventory of radionuclides and heavy metals deposited in the waste dam.The obtained results showed that pyrite oxidation is the key process in the mobilization of radionuclides and heavy metals from the wastes. Pyrite oxidation is a process regulated by oxygen diffusion and water. In the studied scenario it could be shown that the process was limited to a one meter deep layer in the uncovered part of the waste dam. Because of this, Fe, Al, Mn, Zn, Th and 238 U showed higher concentrations in the bottom layers of the cores in relation to the upper ones. 226 Ra and 210 Pb showed opposite patterns. The coprecipitation with Ca SO4 was the most relevant mechanism in both radionuclides immobilization in the wastes. Sulfate was the only chemical species that could be assigned as a contaminant in aquifer bellow the waste dam. As a conclusion, the target environmental

  10. Infrared Camera Characterization of Bi-Propellant Reaction Control Engines during Auxiliary Propulsion Systems Tests at NASA's White Sands Test Facility in Las Cruces, New Mexico

    Science.gov (United States)

    Holleman, Elizabeth; Sharp, David; Sheller, Richard; Styron, Jason

    2007-01-01

    This paper describes the application of a FUR Systems A40M infrared (IR) digital camera for thermal monitoring of a Liquid Oxygen (LOX) and Ethanol bi-propellant Reaction Control Engine (RCE) during Auxiliary Propulsion System (APS) testing at the National Aeronautics & Space Administration's (NASA) White Sands Test Facility (WSTF) near Las Cruces, New Mexico. Typically, NASA has relied mostly on the use of ThermoCouples (TC) for this type of thermal monitoring due to the variability of constraints required to accurately map rapidly changing temperatures from ambient to glowing hot chamber material. Obtaining accurate real-time temperatures in the JR spectrum is made even more elusive by the changing emissivity of the chamber material as it begins to glow. The parameters evaluated prior to APS testing included: (1) remote operation of the A40M camera using fiber optic Firewire signal sender and receiver units; (2) operation of the camera inside a Pelco explosion proof enclosure with a germanium window; (3) remote analog signal display for real-time monitoring; (4) remote digital data acquisition of the A40M's sensor information using FUR's ThermaCAM Researcher Pro 2.8 software; and (5) overall reliability of the system. An initial characterization report was prepared after the A40M characterization tests at Marshall Space Flight Center (MSFC) to document controlled heat source comparisons to calibrated TCs. Summary IR digital data recorded from WSTF's APS testing is included within this document along with findings, lessons learned, and recommendations for further usage as a monitoring tool for the development of rocket engines.

  11. Geophysical bed sediment characterization of the Androscoggin River from the former Chlor-Alkali Facility Superfund Site, Berlin, New Hampshire, to the state border with Maine, August 2009

    Science.gov (United States)

    Degnan, James R.; Teeple, Andrew P.; Johnston, Craig M.; Marvin-DiPasquale, Mark C.; Luce, Darryl

    2011-01-01

    The former Chlor-Alkali Facility in Berlin, New Hampshire, was listed on the U.S. Environmental Protection Agency National Priorities List in 2005 as a Superfund site. The Chlor-Alkali Facility lies on the east bank of the Androscoggin River. Elemental mercury currently discharges from that bank into the Androscoggin River. The nature, extent, and the speciation of mercury and the production of methyl mercury contamination in the adjacent Androscoggin River is the subject of continuing investigations. The U.S. Geological Survey, in cooperation with Region I of the U.S. Environmental Protection Agency, used geophysical methods to determine the distribution, thickness, and physical properties of sediments in the Androscoggin River channel at a small area of an upstream reference reach and downstream from the site to the New Hampshire–Maine State border. Separate reaches of the Androscoggin River in the study area were surveyed with surface geophysical methods including ground-penetrating radar and step-frequency electromagnetics. Results were processed to assess sediment characteristics including grain size, electrical conductivity, and pore-water specific conductance. Specific conductance measured during surface- and pore-water sampling was used to help interpret the results of the geophysical surveys. The electrical resistivity of sediment samples was measured in the laboratory with intact pore water for comparison with survey results. In some instances, anthropogenic features and land uses, such as roads and power lines affected the detection of riverbed properties using geophysical methods; when this occurred, the data were removed. Through combining results, detailed riverbed sediment characterizations were made. Results from ground-penetrating radar surveys were used to image and measure the depth to the riverbed, depth to buried riverbeds, riverbed thickness and to interpret material-type variations in terms of relative grain size. Fifty two percent of the

  12. Site characterization summary report for Waste Area Grouping 10 Wells at the Old Hydrofracture Facility, Oak Ridge National Laboratory, Oak Ridge, Tennessee

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-03-01

    The Oak Ridge National Laboratory (ORNL) in Oak Ridge, Tennessee, is operated for the Department of Energy (DOE) by Martin Marietta Energy Systems (Energy Systems). As part of its DOE mission, ORNL has pioneered waste disposal technologies throughout the years of site operations since World War II. In the late 1950s, efforts were made to develop a permanent disposal alternative to the surface impoundments at ORNL at the request of the National Academy of Sciences. One such technology, the hydrofracture process, involved forming fractures in an underlying geologic host formation (a low-permeability shale) at depths of up to 1000 ft and subsequently injecting a grout slurry containing low-level liquid waste, cement, and other additives at an injection pressure of about 2000 psi. The objective of the effort was to develop a grout slurry that could be injected as a liquid but would solidify after injection, thereby immobilizing the radioisotopes contained in the low-level liquid waste. The scope of this site characterization was the access, sampling, logging, and evaluation of observation wells near the Old Hydrofracture Facility (OHF) in preparation for plugging, recompletion, or other final disposition of the wells.

  13. Facile Synthesis and Characterization of N-Doped TiO2 Photocatalyst and Its Visible-Light Activity for Photo-Oxidation of Ethylene

    Directory of Open Access Journals (Sweden)

    Yu-Hao Lin

    2015-01-01

    Full Text Available A facile wet chemical method was adopted for preparing highly photoactive nitrogen doped TiO2 (N-TiO2 powders with visible responsive capability, which could be achieved by the hydrolysis of titanium isopropoxide (TTIP in the ammonium hydroxide precursor solution in various concentrations and then calcined at different temperatures. The N-TiO2 powders were characterized, and the photocatalytic activity was evaluated for the photocatalytic oxidation of ethylene gas under visible light irradiation to optimize the synthesizing conditions of N-TiO2 catalyst. The N-TiO2 photocatalytic powders were calcined in a range of temperatures from 300 to 600°C and obviously found to have greater photocatalytic activities than commercial TiO2 P25. The strong absorption in the visible light region could be ascribed to good crystallization and adapted sinter temperature of as prepared sample. XPS test demonstrated that the N was doped into TiO2 lattice and made an interstitial formation (Ti-O-N, and N doping also retarded the phase transformation from anatase to rutile as well. The N-TiO2 catalyst prepared with 150 mL ammonium hydroxide added and calcined at 500°C showed the best photocatalytic activity. The experimental results also proved the enhanced photoactivity of N-TiO2 material depends on the synthesizing conditions.

  14. Experimental facilities

    International Nuclear Information System (INIS)

    We have completed an engineering feasibility study of a major modification of the HFIR facility and are now beginning a similar study of an entirely new facility. The design of the reactor itself is common to both options. In this paper, a general description of the modified HFIR is presented with some indications of the additional facilities that might be available in an entirely new facility

  15. Facility Microgrids

    Energy Technology Data Exchange (ETDEWEB)

    Ye, Z.; Walling, R.; Miller, N.; Du, P.; Nelson, K.

    2005-05-01

    Microgrids are receiving a considerable interest from the power industry, partly because their business and technical structure shows promise as a means of taking full advantage of distributed generation. This report investigates three issues associated with facility microgrids: (1) Multiple-distributed generation facility microgrids' unintentional islanding protection, (2) Facility microgrids' response to bulk grid disturbances, and (3) Facility microgrids' intentional islanding.

  16. Microwave assisted facile hydrothermal synthesis and characterization of zinc oxide flower grown on graphene oxide sheets for enhanced photodegradation of dyes

    Science.gov (United States)

    Kashinath, L.; Namratha, K.; Byrappa, K.

    2015-12-01

    Microwave assisted hydrothermal process of synthesis of ZnO-GO nanocomposite by using ZnCl2 and NaOH as precursors is being reported first time. In this investigation, a novel route to study on synthesis, interaction, kinetics and mechanism of hybrid zinc oxide-graphene oxide (ZnO-GO) nanocomposite using microwave assisted facile hydrothermal method has been reported. The results shows that the ZnO-GO nanocomposite exhibits an enhancement and acts as stable photo-response degradation performance of Brilliant Yellow under the UV light radiation better than pure GO and ZnO nanoparticles. The microwave exposure played a vital role in the synthesis process, it facilitates with well define crystalline structure, porosity and fine morphology of ZnO/GO nanocomposite. Different molar concentrations of ZnO precursors doped to GO sheets were been synthesized, characterized and their photodegradation performances were investigated. The optical studies by UV-vis and Photo Luminescence shows an increase in band gap of nanocomposite, which added an advantage in photodegradation performance. The in situ flower like ZnO nano particles are were densely decorated and anchored on the surfaces of graphene oxide sheets which aids in the enhancement of the surface area, adsorption, mass transfer of dyes and evolution of oxygen species. The nanocomposite having high surface area and micro/mesoporous in nature. This structure and morphology supports significantly in increasing photo catalytic performance legitimate to the efficient photosensitized electron injection and repressed electron recombination due to electron transfer process with GO as electron collector and transporter dependent on the proportion of GO in ZnO/GO composite.

  17. Animal facilities

    International Nuclear Information System (INIS)

    The animal facilities in the Division are described. They consist of kennels, animal rooms, service areas, and technical areas (examining rooms, operating rooms, pathology labs, x-ray rooms, and 60Co exposure facilities). The computer support facility is also described. The advent of the Conversational Monitor System at Argonne has launched a new effort to set up conversational computing and graphics software for users. The existing LS-11 data acquisition systems have been further enhanced and expanded. The divisional radiation facilities include a number of gamma, neutron, and x-ray radiation sources with accompanying areas for related equipment. There are five 60Co irradiation facilities; a research reactor, Janus, is a source for fission-spectrum neutrons; two other neutron sources in the Chicago area are also available to the staff for cell biology studies. The electron microscope facilities are also described

  18. Experimental Component Characterization, Monte-Carlo-Based Image Generation and Source Reconstruction for the Neutron Imaging System of the National Ignition Facility

    Energy Technology Data Exchange (ETDEWEB)

    Barrera, C A; Moran, M J

    2007-08-21

    The Neutron Imaging System (NIS) is one of seven ignition target diagnostics under development for the National Ignition Facility. The NIS is required to record hot-spot (13-15 MeV) and downscattered (6-10 MeV) images with a resolution of 10 microns and a signal-to-noise ratio (SNR) of 10 at the 20% contour. The NIS is a valuable diagnostic since the downscattered neutrons reveal the spatial distribution of the cold fuel during an ignition attempt, providing important information in the case of a failed implosion. The present study explores the parameter space of several line-of-sight (LOS) configurations that could serve as the basis for the final design. Six commercially available organic scintillators were experimentally characterized for their light emission decay profile and neutron sensitivity. The samples showed a long lived decay component that makes direct recording of a downscattered image impossible. The two best candidates for the NIS detector material are: EJ232 (BC422) plastic fibers or capillaries filled with EJ399B. A Monte Carlo-based end-to-end model of the NIS was developed to study the imaging capabilities of several LOS configurations and verify that the recovered sources meet the design requirements. The model includes accurate neutron source distributions, aperture geometries (square pinhole, triangular wedge, mini-penumbral, annular and penumbral), their point spread functions, and a pixelated scintillator detector. The modeling results show that a useful downscattered image can be obtained by recording the primary peak and the downscattered images, and then subtracting a decayed version of the former from the latter. The difference images need to be deconvolved in order to obtain accurate source distributions. The images are processed using a frequency-space modified-regularization algorithm and low-pass filtering. The resolution and SNR of these sources are quantified by using two surrogate sources. The simulations show that all LOS

  19. Physical‐chemical and microbiological characterization, and mutagenic activity of airborne PM sampled in a biomass‐fueled electrical production facility

    DEFF Research Database (Denmark)

    Cohn, Corey A.; Lemieux, Christine L.; Long, Alexandra S.;

    2011-01-01

    Biomass combustion is used in heating and electric power generation in many areas of the world. Airborne particulate matter (PM) is released when biomass is brought to a facility, stored, and combusted. Occupational exposure to airborne PM within biomass‐fueled facilities may lead to health...... includes PM from biomass combustion as well as internal combustion vehicles, may contribute to an elevated risk of adverse health effects. Environ. Mol. Mutagen., 2011. © 2010 Wiley‐Liss, Inc....

  20. Facility effluent monitoring plan for the 327 Facility

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1994-11-01

    The 327 Facility [Post-Irradiation Testing Laboratory] provides office and laboratory space for Pacific Northwest Laboratory (PNL) scientific and engineering staff conducting multidisciplinary research in the areas of post-irradiated fuels and structural materials. The facility is designed to accommodate the use of radioactive and hazardous materials in the conduct of these activities. This report summarizes the airborne emissions and liquid effluents and the results of the Facility Effluent Monitoring Plan (FEMP) determination for the facility. The complete monitoring plan includes characterization of effluent streams, monitoring/sampling design criteria, a description of the monitoring systems and sample analysis, and quality assurance requirements.

  1. Mammography Facilities

    Data.gov (United States)

    U.S. Department of Health & Human Services — The Mammography Facility Database is updated periodically based on information received from the four FDA-approved accreditation bodies: the American College of...

  2. Health Facilities

    Science.gov (United States)

    Health facilities are places that provide health care. They include hospitals, clinics, outpatient care centers, and specialized care centers, such as birthing centers and psychiatric care centers. When you ...

  3. Canyon Facilities

    Data.gov (United States)

    Federal Laboratory Consortium — B Plant, T Plant, U Plant, PUREX, and REDOX (see their links) are the five facilities at Hanford where the original objective was plutonium removal from the uranium...

  4. Molecular characterization and drug resistance of Escherichia coli strains isolated from urine from long-term care facility residents in Cracow, Poland

    OpenAIRE

    Pobiega, Monika; Wojkowska-Mach, Jadwiga; Chmielarczyk, Agnieszka; Romaniszyn, Dorota; Adamski, Paweł; Heczko, Piort B.; Gryglewska, Barbara; Grodzicki, Tomasz

    2013-01-01

    Background The aim of this study was to assess the prevalence of multidrug-resistant Escherichia coli and extended-spectrum β-lactamases (ESBL) pathogens isolated from asymptomatic bacteriuria and urinary tract infections (UTIs), and the relationship between the phylogeny, antimicrobial resistance, and virulence among isolates in residents of 3 long-term care facilities (LTCF) in Krakow, Poland. Material/Methods This was point prevalence study and prospective infection control in a group of 2...

  5. Berkeley Low Background Facility

    Energy Technology Data Exchange (ETDEWEB)

    Thomas, K. J.; Norman, E. B. [Department of Nuclear Engineering, University of California-Berkeley, CA 94720 (United States); Nuclear Science Division, Lawrence Berkeley National Laboratory, CA 94720 (United States); Smith, A. R.; Poon, A. W. P.; Chan, Y. D. [Nuclear Science Division, Lawrence Berkeley National Laboratory, CA 94720 (United States); Lesko, K. T. [Physics Division, Lawrence Berkeley National Laboratory, CA 94720 (United States)

    2015-08-17

    The Berkeley Low Background Facility (BLBF) at Lawrence Berkeley National Laboratory (LBNL) in Berkeley, California provides low background gamma spectroscopy services to a wide array of experiments and projects. The analysis of samples takes place within two unique facilities; locally within a carefully-constructed, low background laboratory on the surface at LBNL and at the Sanford Underground Research Facility (SURF) in Lead, SD. These facilities provide a variety of gamma spectroscopy services to low background experiments primarily in the form of passive material screening for primordial radioisotopes (U, Th, K) or common cosmogenic/anthropogenic products; active screening via neutron activation analysis for U,Th, and K as well as a variety of stable isotopes; and neutron flux/beam characterization measurements through the use of monitors. A general overview of the facilities, services, and sensitivities will be presented. Recent activities and upgrades will also be described including an overview of the recently installed counting system at SURF (recently relocated from Oroville, CA in 2014), the installation of a second underground counting station at SURF in 2015, and future plans. The BLBF is open to any users for counting services or collaboration on a wide variety of experiments and projects.

  6. Berkeley Low Background Facility

    International Nuclear Information System (INIS)

    The Berkeley Low Background Facility (BLBF) at Lawrence Berkeley National Laboratory (LBNL) in Berkeley, California provides low background gamma spectroscopy services to a wide array of experiments and projects. The analysis of samples takes place within two unique facilities; locally within a carefully-constructed, low background laboratory on the surface at LBNL and at the Sanford Underground Research Facility (SURF) in Lead, SD. These facilities provide a variety of gamma spectroscopy services to low background experiments primarily in the form of passive material screening for primordial radioisotopes (U, Th, K) or common cosmogenic/anthropogenic products; active screening via neutron activation analysis for U,Th, and K as well as a variety of stable isotopes; and neutron flux/beam characterization measurements through the use of monitors. A general overview of the facilities, services, and sensitivities will be presented. Recent activities and upgrades will also be described including an overview of the recently installed counting system at SURF (recently relocated from Oroville, CA in 2014), the installation of a second underground counting station at SURF in 2015, and future plans. The BLBF is open to any users for counting services or collaboration on a wide variety of experiments and projects

  7. Facility Environmental Vulnerability Assessment

    International Nuclear Information System (INIS)

    From mid-April through the end of June 2001, a Facility Environmental Vulnerability Assessment (FEVA) was performed at Oak Ridge National Laboratory (ORNL). The primary goal of this FEVA was to establish an environmental vulnerability baseline at ORNL that could be used to support the Laboratory planning process and place environmental vulnerabilities in perspective. The information developed during the FEVA was intended to provide the basis for management to initiate immediate, near-term, and long-term actions to respond to the identified vulnerabilities. It was expected that further evaluation of the vulnerabilities identified during the FEVA could be carried out to support a more quantitative characterization of the sources, evaluation of contaminant pathways, and definition of risks. The FEVA was modeled after the Battelle-supported response to the problems identified at the High Flux Beam Reactor at Brookhaven National Laboratory. This FEVA report satisfies Corrective Action 3A1 contained in the Corrective Action Plan in Response to Independent Review of the High Flux Isotope Reactor Tritium Leak at the Oak Ridge National Laboratory, submitted to the Department of Energy (DOE) ORNL Site Office Manager on April 16, 2001. This assessment successfully achieved its primary goal as defined by Laboratory management. The assessment team was able to develop information about sources and pathway analyses although the following factors impacted the team's ability to provide additional quantitative information: the complexity and scope of the facilities, infrastructure, and programs; the significantly degraded physical condition of the facilities and infrastructure; the large number of known environmental vulnerabilities; the scope of legacy contamination issues [not currently addressed in the Environmental Management (EM) Program]; the lack of facility process and environmental pathway analysis performed by the accountable line management or facility owner; and poor

  8. Facility Environmental Vulnerability Assessment

    Energy Technology Data Exchange (ETDEWEB)

    Van Hoesen, S.D.

    2001-07-09

    From mid-April through the end of June 2001, a Facility Environmental Vulnerability Assessment (FEVA) was performed at Oak Ridge National Laboratory (ORNL). The primary goal of this FEVA was to establish an environmental vulnerability baseline at ORNL that could be used to support the Laboratory planning process and place environmental vulnerabilities in perspective. The information developed during the FEVA was intended to provide the basis for management to initiate immediate, near-term, and long-term actions to respond to the identified vulnerabilities. It was expected that further evaluation of the vulnerabilities identified during the FEVA could be carried out to support a more quantitative characterization of the sources, evaluation of contaminant pathways, and definition of risks. The FEVA was modeled after the Battelle-supported response to the problems identified at the High Flux Beam Reactor at Brookhaven National Laboratory. This FEVA report satisfies Corrective Action 3A1 contained in the Corrective Action Plan in Response to Independent Review of the High Flux Isotope Reactor Tritium Leak at the Oak Ridge National Laboratory, submitted to the Department of Energy (DOE) ORNL Site Office Manager on April 16, 2001. This assessment successfully achieved its primary goal as defined by Laboratory management. The assessment team was able to develop information about sources and pathway analyses although the following factors impacted the team's ability to provide additional quantitative information: the complexity and scope of the facilities, infrastructure, and programs; the significantly degraded physical condition of the facilities and infrastructure; the large number of known environmental vulnerabilities; the scope of legacy contamination issues [not currently addressed in the Environmental Management (EM) Program]; the lack of facility process and environmental pathway analysis performed by the accountable line management or facility owner; and

  9. Geohydrologic site characterization of the municipal solid waste landfill facility, US Army Air Defense Artillery Center and Fort Bliss, El Paso County, Texas

    Science.gov (United States)

    Abeyta, Cynthia G.

    1996-01-01

    Geohydrologic conditions of the Municipal Solid Waste Landfill Facility (MSWLF) on the U.S. Army Air Defense Artillery Center and Fort Bliss, El Paso County, Texas, were evaluated by the U.S. Geological Survey in cooperation with the U.S. Army. The 106.03-acre MSWLF has been in operation since January 1974. The landfill contains household refuse, Post solid wastes, bulky items, grass and tree trimmings from family housing, refuse from litter cans, construction debris, classified waste (dry), dead animals, asbestos, and empty oil cans. The MSWLF, located about 1,200 feet east of the nearest occupied structure, is estimated to receive an average of approximately 56 tons of municipal solid waste per day and, at a fill rate of 1-4 acres per year, is expected to reach its capacity by the year 2004. The MSWLF is located in the Hueco Bolson, 4 miles east of the Franklin Mountains. Elevations at the MSWLF range from 3,907 to 3,937 feet above sea level. The climate at the MSWLF and vicinity is arid continental, characterized by an abundance of sunny days, high summer temperatures, relatively cool winters typical of arid areas, scanty rainfall, and very low humidity throughout the year. Average annual temperature near the MSWLF and vicinity is 63.3 degrees Fahrenheit and annual precipitation is 7.8 inches. Potential evaporation in the El Paso area was estimated to be 65 inches per year. Soils at and adjacent to the MSWLF are nearly level to gently sloping, have a fine sandy loam subsoil, and are moderately deep over caliche. The MSWLF is underlain by Hueco Bolson deposits of Tertiary age and typically are composed of unconsolidated to slightly consolidated interbedded sands, clay, silt, gravel, and caliche. Individual beds are not well defined and range in thickness from a fraction of an inch to about 100 feet. The primary source of ground water in the MSWLF area is in the deposits of the Hueco Bolson. A relatively thick vadose zone of approximately 300 feet overlies the

  10. Marina Facilities

    OpenAIRE

    2014-01-01

    The CIRPAS main facility and headquarters are at Marina Municipal Airport (formerly Fritchie Field, Fort Ord) in Marina, California. CIRPAS has a 30,000 sq. ft. maintenance hanger there, which houses staff offices, an instrument and calibration laboratory, maintenance and payload integration shops, conference rooms, and flight planning and operations control center.

  11. Demonstration of persistent contamination of a cooked egg product production facility with Salmonella enterica serovar Tennessee and characterization of the persistent strain

    DEFF Research Database (Denmark)

    Jakociune, D.; Bisgaard, M.; Pedersen, Karl;

    2014-01-01

    Aims: The aim of this study was to investigate whether continuous contamination of light pasteurized egg products with Salmonella enterica serovar Tennessee (S. Tennessee) at a large European producer of industrial egg products was caused by persistent contamination of the production facility...... throughout the full period were shown to belong to one profile type. Isolates representing different PFGE profiles were all assigned to ST 319 by multilocus sequence typing (MLST). The case isolates did not show a higher ability to form biofilm on a plastic surface than noncase isolates. Characteristically...

  12. Characterization of a CsI(Tl) array coupled to avalanche photodiodes for the Barrel of the CALIFA calorimeter at the NEPTUN tagged gamma beam facility

    Science.gov (United States)

    Gascón, M.; Schnorrenberger, L.; Pietras, B.; Álvarez-Pol, H.; Cortina-Gil, D.; Díaz Fernández, P.; Duran, I.; Glorius, J.; González, D.; Perez-Loureiro, D.; Pietralla, N.; Savran, D.; Sonnabend, K.

    2013-10-01

    Among the variety of crystal calorimeters recently designed for several physics facilities, CALIFA (CALorimeter for In-Flight emitted gAmmas and light-charged particles) has especially demanding requirements since it must perform within a very complicated energy domain (gamma-ray energies from 0.1 to 20 MeV and up to 300 MeV protons). As part of the R&D program for the Barrel section of CALIFA, a reduced geometry prototype was constructed. This prototype consisted of a 3 × 5 array of CsI(Tl) crystals of varying dimensions, coupled to large area avalanche photodiodes. Here reported are the details regarding the construction of the prototype and the experimental results obtained at the NEPTUN tagged gamma beam facility, reconstructing gamma energies up to 10 MeV. Dedicated Monte Carlo simulations of the setup were also performed, enabling a deeper understanding of the experimental data. The experimental results demonstrate the effectiveness of the reconstruction method and helped to establish the most suitable crystal geometry to be employed within the forthcoming calorimeter.

  13. IDENTIFICATION AND CHARACTERIZATION OF FIVE NON- TRADITIONAL SOURCE CATEGORIES: CATASTROPHIC/ACCIDENTAL RELEASES, VEHICLE REPAIR FACILITIES, RECYCLING, PESTICIDE APPLICATION, AND AGRICULTURAL OPERATIONS

    Science.gov (United States)

    The report gives results of work that is part of EPA's program to identify and characterize emissions sources not currently accounted for by either the existing Aerometric Information Retrieval System (AIRS) or State Implementation Plan (SIP) area source methodologies and to deve...

  14. Main Facilities

    International Nuclear Information System (INIS)

    This chapter discuss on main nuclear facilities available in the Malaysian Institute for Nuclear Technology Research (MINT). As a national research institute whose core activities are nuclear science and technology, MINT are made up of main commercializable radiation irradiators, pilot plant and fully equipped laboratories. Well elaboration on its characteristics and functions explain for RTP (PUPSPATI TRIGA reactors), Cobalt-60 gamma irradiator, electron beam accelerators, and radioactive waste management center

  15. Nuclear facility

    International Nuclear Information System (INIS)

    In nuclear facilities with a fuel storage pool in a spent fuel pit building there is a filter to each pool through which the fuel pit water is pumped. According to the invention the filter is provided with an independently movable housing placed beneath the surface of the pool water and fixed to the lateral side of the pool by means of detachable fixtures. (orig./RW)

  16. Progress Report {number_sign}1 on the materials identification, characterization and evaluation activity: Acquisition of materials data from the Exploratory Studies Facility

    Energy Technology Data Exchange (ETDEWEB)

    Meike, A., LLNL

    1998-02-01

    This paper reports on the initial work within the Materials Identification, Characterization and Evaluation Sub-activity Integration Activity within the Introduced Materials Task (IMT) (WBS 1.2.3.12.5). The goals of this activity are twofold.: (1) to identify and characterize types and usage of materials that are most likely to be introduced into a potential High Level Radioactive Waste (HLW) repository at Yucca Mountain, Nevada, as a result of its construction and operation and (2) to provide tools for the Integration Activity to evaluate the chemical impact on the repository based on information gathered from sources external and internal to the Introduced Materials Task-by the Literature Survey Sub-activity (Integration Activity, IMT). Based on this information and assessment, the Integration Activity activates relevant activities within the Introduced Materials Task and provides information to other Tasks within the Yucca Mountain Project.

  17. Synthesis, characterization, and Fischer–Tropsch performance of cobalt/zinc aluminate nanocomposites via a facile and corrosion-free coprecipitation route

    International Nuclear Information System (INIS)

    Literature about ZnAl2O4-supported cobalt Fischer–Tropsch synthesis (FTS) catalytic materials is sparse. A series of cobalt-containing nanocomposites, supported by nanosized ZnAl2O4 spinel (i.e., a complex oxide of about 6.4 nm) or alumina (i.e., a simple oxide of about 6.2 nm), were prepared via urea-gelation, coprecipitation, or impregnation methods followed by stepwise reduction. These materials were examined by XRD, TGA, nitrogen sorption, FESEM, and EDS. Effects of corrosion and pore size distributions on materials preparation were also investigated. The “coprecipitation/stepwise reduction” route is facile and suitable to prepare nanosized ZnAl2O4-supported Co0 nanocomposites. At similar CO conversions, the coprecipitated Co/ZnAl2O4 exhibits significantly lower C1 hydrocarbon distribution, slightly lower C5+ hydrocarbon distribution, significantly higher C2–C4 hydrocarbon distribution, and significantly higher olefin/paraffin ratio of C2–C4 than Co/γ-Al2O3

  18. Synthesis, characterization, and Fischer–Tropsch performance of cobalt/zinc aluminate nanocomposites via a facile and corrosion-free coprecipitation route

    Energy Technology Data Exchange (ETDEWEB)

    Liu, Zhenxin; Xing, Yu, E-mail: yuxing@zzuli.edu.cn; Xue, Yingying; Wu, Depeng; Fang, Shaoming, E-mail: smfang@zzuli.edu.cn [Zhengzhou University of Light Industry, Henan Provincial Key Laboratory of Surface and Interface Science, School of Materials and Chemical Engineering (China)

    2015-02-15

    Literature about ZnAl{sub 2}O{sub 4}-supported cobalt Fischer–Tropsch synthesis (FTS) catalytic materials is sparse. A series of cobalt-containing nanocomposites, supported by nanosized ZnAl{sub 2}O{sub 4} spinel (i.e., a complex oxide of about 6.4 nm) or alumina (i.e., a simple oxide of about 6.2 nm), were prepared via urea-gelation, coprecipitation, or impregnation methods followed by stepwise reduction. These materials were examined by XRD, TGA, nitrogen sorption, FESEM, and EDS. Effects of corrosion and pore size distributions on materials preparation were also investigated. The “coprecipitation/stepwise reduction” route is facile and suitable to prepare nanosized ZnAl{sub 2}O{sub 4}-supported Co{sup 0} nanocomposites. At similar CO conversions, the coprecipitated Co/ZnAl{sub 2}O{sub 4} exhibits significantly lower C{sub 1} hydrocarbon distribution, slightly lower C{sub 5+} hydrocarbon distribution, significantly higher C{sub 2}–C{sub 4} hydrocarbon distribution, and significantly higher olefin/paraffin ratio of C{sub 2}–C{sub 4} than Co/γ-Al{sub 2}O{sub 3}.

  19. International Fusion Materials Irradiation Facility injector acceptance tests at CEA/Saclay: 140 mA/100 keV deuteron beam characterization

    Energy Technology Data Exchange (ETDEWEB)

    Gobin, R., E-mail: rjgobin@cea.fr; Bogard, D.; Chauvin, N.; Chel, S.; Delferrière, O.; Harrault, F.; Mattei, P.; Senée, F. [Commissariat à l’Energie Atomique et aux Energies Alternatives, CEA/Saclay, DSM/IRFU, 91191-Gif/Yvette (France); Cara, P. [Fusion for Energy, BFD Department, Garching (Germany); Mosnier, A. [Commissariat à l’Energie Atomique et aux Energies Alternatives, CEA/Saclay, DSM/IRFU, 91191-Gif/Yvette (France); Fusion for Energy, BFD Department, Garching (Germany); Shidara, H. [IFMIF/EVEDA Project Team, Obuchi-Omotedate 2-166, Rokkasho, Aomori (Japan); Okumura, Y. [JAEA, Division of Rokkasho BA Project, Obuchi-Omotedate 2-166, Rokkasho, Aomori (Japan)

    2014-02-15

    In the framework of the ITER broader approach, the International Fusion Materials Irradiation Facility (IFMIF) deuteron accelerator (2 × 125 mA at 40 MeV) is an irradiation tool dedicated to high neutron flux production for future nuclear plant material studies. During the validation phase, the Linear IFMIF Prototype Accelerator (LIPAc) machine will be tested on the Rokkasho site in Japan. This demonstrator aims to produce 125 mA/9 MeV deuteron beam. Involved in the LIPAc project for several years, specialists from CEA/Saclay designed the injector based on a SILHI type ECR source operating at 2.45 GHz and a 2 solenoid low energy beam line to produce such high intensity beam. The whole injector, equipped with its dedicated diagnostics, has been then installed and tested on the Saclay site. Before shipment from Europe to Japan, acceptance tests have been performed in November 2012 with 100 keV deuteron beam and intensity as high as 140 mA in continuous and pulsed mode. In this paper, the emittance measurements done for different duty cycles and different beam intensities will be presented as well as beam species fraction analysis. Then the reinstallation in Japan and commissioning plan on site will be reported.

  20. Facility Management

    OpenAIRE

    Král, David

    2012-01-01

    Tématem bakalářské práce je nalezení cesty ke zvýšení dlouhodobé efektivnosti a prosperity společnosti, která v rámci své podnikatelské činnosti spravuje a udržuje vlastní nemovitosti v centru Brna. Práce vychází z aktuálního stavu facility managementu společnosti a definování jejich silných a slabých stránek. Základem pro návrh efektivního řízení facility managementu je zpracování finanční analýzy společnosti a sledování nákladů včetně jejich optimalizace. Hlavním přínosem mé bakalářské prác...

  1. Theme: Laboratory Facilities Improvement.

    Science.gov (United States)

    Miller, Glen M.; And Others

    1993-01-01

    Includes "Laboratory Facilities Improvement" (Miller); "Remodeling Laboratories for Agriscience Instruction" (Newman, Johnson); "Planning for Change" (Mulcahy); "Laboratory Facilities Improvement for Technology Transfer" (Harper); "Facilities for Agriscience Instruction" (Agnew et al.); "Laboratory Facility Improvement" (Boren, Dwyer); and…

  2. The University of Minnesota aquifer thermal energy storage (ATES) field test facility -- system description, aquifer characterization, and results of short-term test cycles

    Energy Technology Data Exchange (ETDEWEB)

    Walton, M.; Hoyer, M.C.; Eisenreich, S.J.; Holm, N.L.; Holm, T.R.; Kanivetsky, R.; Jirsa, M.A.; Lee, H.C.; Lauer, J.L.; Miller, R.T.; Norton, J.L.; Runke, H. (Minnesota Geological Survey, St. Paul, MN (United States))

    1991-06-01

    Phase 1 of the Aquifer Thermal Energy Storage (ATES) Project at the University of Minnesota was to test the feasibility, and model, the ATES concept at temperatures above 100{degrees}C using a confined aquifer for the storage and recovery of hot water. Phase 1 included design, construction, and operation of a 5-MW thermal input/output field test facility (FTF) for four short-term ATES cycles (8 days each of heat injection, storage, and heat recover). Phase 1 was conducted from May 1980 to December 1983. This report describes the FTF, the Franconia-Ironton-Galesville (FIG) aquifer used for the test, and the four short-term ATES cycles. Heat recovery; operational experience; and thermal, chemical, hydrologic, and geologic effects are all included. The FTF consists of monitoring wells and the source and storage well doublet completed in the FIG aquifer with heat exchangers and a fixed-bed precipitator between the wells of the doublet. The FIG aquifer is highly layered and a really anisotropic. The upper Franconia and Ironton-Galesville parts of the aquifer, those parts screened, have hydraulic conductivities of {approximately}0.6 and {approximately}1.0 m/d, respectively. Primary ions in the ambient ground water are calcium and magnesium bicarbonate. Ambient temperature FIG ground water is saturated with respect to calcium/magnesium bicarbonate. Heating the ground water caused most of the dissolved calcium to precipitate out as calcium carbonate in the heat exchanger and precipitator. Silica, calcium, and magnesium were significantly higher in recovered water than in injected water, suggesting dissolution of some constituents of the aquifer during the cycles. Further work on the ground water chemistry is required to understand water-rock interactions.

  3. Facile preparation of PbS nanostructures and PbS/f-CNT nanocomposites using xanthate as sulfur source: Thermal and optical characterization

    Energy Technology Data Exchange (ETDEWEB)

    Golabi, Parisa; Akbarzadeh, Raziyeh; Dehghani, Hossein, E-mail: dehghani@kashanu.ac.ir

    2015-10-25

    PbS nanostructures with different morphologies were fabricated using a new sulfur source through a facile and low cost hydro(solvo)thermal method. The influence of different reaction factors such as sulfur source, temperature, reactant, solvent and surfactant on the size and morphology of the obtained PbS particles were investigated. Beside, a simple hydrothermal process at low temperature (60 °C) for little time (4 h), has been used for preparation of PbS nanoparticles (NPs)/functionalized multi wall carbon nanotubes (f-MWCNTs) nanocomposite. The as-prepared nanocomposite possesses excellent thermal and optical properties. Thermal stability increases by depositing PbS nanoparticles on the surface of CNT. The structure, morphology, thermal and optical properties of the as-prepared nanocompounds were studied by X-ray diffraction (XRD), Fourier transform infrared (FT-IR) spectroscopy, Scanning electron microscope (SEM), Energy-dispersive X-ray spectroscopy, Thermogravimetric analysis (TGA), Pl spectra and UV–Vis absorption spectra. Photoluminescence spectra of PbS NPs and nanocomposite are consist of two emission peaks which centered at around 402 and 423 nm, when excited at 350 nm. It was noteworthy that the blue luminescence intensity over PbS/f-CNT nanocomposite is very lower than that of pure PbS NPs. Remarkable blue-shift from bulk material was observed on the PbS nanoparticles using UV–Vis spectrum. Furthermore, possible growth mechanism of PbS nanostructures is presented. - Graphical abstract: PbS nanostructures with different morphologies were fabricated using xanthate as sulfide source. Also, PbS/f-CNT nanocomposites were synthesized by simple hydrothermal process at low temperature (60 °C) for little time (4 h). - Highlights: • Sodium tert-butyl xanthate was used as sulfur source for synthesis of PbS. • Pb(CH{sub 3}COO){sub 2}·3H{sub 2}O salt was used for synthesis of PbS. • PbS/CNT nanocomposite was synthesized in deionized water for 4 h at 60

  4. Employment of MCNP in the study of TLDS 600 and 700 seeking the implementation of radiation beam characterization of BNCT facility at IEA-R1

    International Nuclear Information System (INIS)

    Boron Neutron Capture Therapy, BNCT, is a bimodal radiotherapy procedure for cancer treatment. Its useful energy comes from a nuclear reaction driven by impinging thermal neutron upon Boron 10 atoms. A BNCT research facility has been constructed in IPEN at the IEA-R1 reactor, to develop studies in this area. One of its prime experimental parameter is the beam dosimetry which is nowadays made by using activation foils, for neutron measurements, and TLD 400, for gamma dosimetry. For mixed field dosimetry, the International Commission on Radiation Units and Measurements, ICRU, recommends the use of pair of detectors with distinct responses to the field components. The TLD 600/ TLD 700 pair meets this criteria, as the amount of 6Li, a nuclide with high thermal neutron cross section, greatly differs in their composition. This work presents a series of experiments and simulations performed in order to implement the mixed field dosimetry based on the use of TLD 600/TLD 700 pair. It also intended to compare this mixed field dosimetric methodology to the one so far used by the BNCT research group of IPEN. The response of all TLDs were studied under irradiations in different irradiation fields and simulations, underwent by MCNP, were run in order to evaluate the dose contribution from each field component. Series of repeated irradiations under pure gamma field and mixed field neutron/gamma field showed differences in the TLD individual responses which led to the adoption of a Normalization Factor. It has allowed to overcome TLD selection. TLD responses due to different field components and spectra were studied. It has shown to be possible to evaluate the relative gamma/neutron fluxes from the relative responses observed in the two Regions of Interest, ROIs, from TLD 600 and TLD 700. It has also been possible to observe the TLD 700 response to neutron, which leads to a gamma dose overestimation when one follows the ICRU recommended mixed field dosimetric procedure. Dose

  5. Site Characterization for CO{sub 2} Storage from Coal-fired Power Facilities in the Black Warrior Basin of Alabama

    Energy Technology Data Exchange (ETDEWEB)

    Clark, Peter; Pashin, Jack; Carlson, Eric; Goodliffe, Andrew; McIntyre-Redden, Marcella; Mann, Steven; Thompson, Mason

    2012-08-31

    Coal-fired power plants produce large quantities of carbon dioxide. In order to mitigate the greenhouse gas emissions from these power plants, it is necessary to separate and store the carbon dioxide. Saline formations provide a potential sink for carbon dioxide and delineating the capacity of the various known saline formations is a key part of building a storage inventory. As part of this effort, a project was undertaken to access the storage capacity of saline reservoirs in the Black Warrior Basin of Alabama. This basin has been a productive oil and gas reservoir that is well characterized to the west of the two major coal-fired power plants that are north of Birmingham. The saline zones were thought to extend as far east as the Sequatchie Anticline which is just east of the power plants. There is no oil or gas production in the area surrounding the power plants so little is known about the formations in that area. A geologic characterization well was drilled on the Gorgas Power Plant site, which is the farthest west of two power plants in the area. The well was planned to be drilled to approximately 8,000 feet, but drilling was halted at approximately 5,000 feet when a prolific freshwater zone was penetrated. During drilling, a complete set of cores through all of the potential injection zones and the seals above these zones were acquired. A complete set of openhole logs were run along with a vertical seismic profile (VSP). Before drilling started two approximately perpendicular seismic lines were run and later correlated with the VSP. While the zones that were expected were found at approximately the predicted depths, the zones that are typically saline through the reservoir were found to be saturated with a light crude oil. Unfortunately, both the porosity and permeability of these zones were small enough that no meaningful hydrocarbon production would be expected even with carbon dioxide flooding. iv While this part of the basin was found to be unsuitable

  6. Magnetic Resonance Facility (Fact Sheet)

    Energy Technology Data Exchange (ETDEWEB)

    2012-03-01

    This fact sheet provides information about Magnetic Resonance Facility capabilities and applications at NREL's National Bioenergy Center. Liquid and solid-state analysis capability for a variety of biomass, photovoltaic, and materials characterization applications across NREL. NREL scientists analyze solid and liquid samples on three nuclear magnetic resonance (NMR) spectrometers as well as an electron paramagnetic resonance (EPR) spectrometer.

  7. The synthesis and characterization of monodispersed chitosan-coated Fe3O4 nanoparticles via a facile one-step solvothermal process for adsorption of bovine serum albumin.

    Science.gov (United States)

    Shen, Mao; Yu, Yujing; Fan, Guodong; Chen, Guang; Jin, Ying Min; Tang, Wenyuan; Jia, Wenping

    2014-01-01

    Preparation of magnetic nanoparticles coated with chitosan (CS-coated Fe3O4 NPs) in one step by the solvothermal method in the presence of different amounts of added chitosan is reported here. The magnetic property of the obtained magnetic composite nanoparticles was confirmed by X-ray diffraction (XRD) and magnetic measurements (VSM). Scanning electron microscopy (SEM) and transmission electron microscopy (TEM) allowed the identification of spherical nanoparticles with about 150 nm in average diameter. Characterization of the products by Fourier transform infrared spectroscopy (FTIR) demonstrated that CS-coated Fe3O4 NPs were obtained. Chitosan content in the obtained nanocomposites was estimated by thermogravimetric analysis (TGA). The adsorption properties of the CS-coated Fe3O4 NPs for bovine serum albumin (BSA) were investigated under different concentrations of BSA. Compared with naked Fe3O4 nanoparticles, the CS-coated Fe3O4 NPs showed a higher BSA adsorption capacity (96.5 mg/g) and a fast adsorption rate (45 min) in aqueous solutions. This work demonstrates that the prepared magnetic nanoparticles have promising applications in enzyme and protein immobilization. PMID:24994954

  8. Technical Basis for the Determination that Current Characterization Data and Processes are Sufficient to Ensure Safe Storage and to Design Waste Disposal Facilities

    International Nuclear Information System (INIS)

    This appendix summarizes condensed phase sampling and uses a logical approach to determine whether the sampling was sufficient to meet the DNFSB Recommendation 93-5 Implementation Plan milestone 5.6.3.U. Milestone 5.6.3.1j states ''Core sample all tanks by 2002'' (DOE/RL 1996). The milestone was based on the need for characterization data for safe storage of the waste, to operate the tanks and their infrastructure safely, and to plan and implement retrieval and processing of the waste. From 1989 through October 1998,295 core, auger, and grab samples of the condensed phase tank waste have been obtained. The logic used to determine if the sampling was sufficient is presented in Section A2.0. In Section A3.0 the tanks that met the criteria for being considered core-sampled are presented. In total, 138 tanks had been sampled. Sampling from six tanks did not contain sufficient material to meet the criteria. There are 132 tanks that met the criteria. Section A4.0 presents results of the sampling analysis as it applies to safety screening criteria. Very few individual data points approach the Basis for Interim Operation (BIO) safety limits. The few data points which had elevated total organic carbon also had greater than 20 percent water, thus putting all waste samples within the safety limits. The data is graphically portrayed in Section A4.0

  9. Facile Synthesis, Characterization, and In Vitro Antimicrobial Screening of a New Series of 2,4,6-Trisubstituted-s-triazine Based Compounds

    Directory of Open Access Journals (Sweden)

    Ravi Bhushan Singh

    2015-01-01

    Full Text Available A series of new 2,4,6-trisubstituted-s-triazine was synthesized, assessed for antimicrobial activity, and characterized by FTIR, 1HNMR, 13CNMR, and elemental analysis. The tested compounds, 4d, 4g, 4h, 4k, and 4n, have shown considerable in vitro antibacterial efficacy with reference to the standard drug ciprofloxacin (MIC 3.125 μgmL−1 against B. subtilis, E. coli, and K. pneumoniae. It was observed that compounds 4d and 4h displayed equipotent antibacterial efficacy against B. subtilis (MIC 3.125 μgmL−1 and S. aureus (MIC 6.25 μgmL−1. The studies demonstrated that the para-fluorophenylpiperazine substituted s-triazine (4n was potent and exhibited broad spectrum antibacterial activity against S. epidermidis, K. pneumoniae, and P. aeruginosa with MIC of 6.25 μgmL−1 and for E. coli, it showed an MIC of 3.125 μgmL−1 equipotent with reference to the standard drug. Among all the compounds under investigation, compound 4g also demonstrated significant antifungal activity (3.125 μgmL−1 against C. albicans.

  10. Facile synthesis, characterization of a MnFe2O4/activated carbon magnetic composite and its effectiveness in tetracycline removal

    International Nuclear Information System (INIS)

    In this study, MnFe2O4/activated carbon magnetic composites with mass ratio of 1:1, 1:1.5 and 1:2 were synthesized using a simple chemical coprecipitation procedure. A variety of techniques such as X-ray diffractometer, scanning electron microscope, magnetization measurements, BET surface area measurements were used to characterize the structure, morphology and magnetic performance of the prepared composite adsorbents. The results showed that the composites had good magnetic properties, which allowed their convenient magnetic separation from water. Spinel manganese ferrite was found to occur in the magnetic phase and the presence of magnetic particles of MnFe2O4 did not significantly affect the surface area and pore structure of the activated carbon. The magnetic composites were effective for tetracycline (TC) removal from water and the maximal adsorption capacity was 590.5 mmol kg−1 at pH 5.0. The TC adsorption followed pseudo-second-order kinetic model and its removal decreases gradually with an increase in pH value, whereas the removal rate was over 60% even at pH 9.0. The TC adsorption process is endothermic and the increase of temperature is favoring its removal. All these results indicated that the prepared composites had the potential to be used as adsorbents for the removal of TC from water or wastewater. - Highlights: ► The MnFe2O4/activated carbon can be easily separated from water using a magnet. ► The MnFe2O4 did not significantly affect the sorption ability of activated carbon. ► The magnetic composite was effective for tetracycline removal from water.

  11. Facile synthesis, characterization of a MnFe{sub 2}O{sub 4}/activated carbon magnetic composite and its effectiveness in tetracycline removal

    Energy Technology Data Exchange (ETDEWEB)

    Shao Lina [Key Laboratory of Coastal Environment Processes, Yantai Institute of Coastal Zone Research, Chinese Academy of Sciences, Yantai 264003 (China); School of Environmental and Municipal Engineering, Lanzhou Jiaotong University, Lanzhou 730070 (China); Ren Zongming [Key Laboratory of Coastal Environment Processes, Yantai Institute of Coastal Zone Research, Chinese Academy of Sciences, Yantai 264003 (China); Zhang Gaosheng, E-mail: gszhang@yic.ac.cn [Key Laboratory of Coastal Environment Processes, Yantai Institute of Coastal Zone Research, Chinese Academy of Sciences, Yantai 264003 (China); Chen Linlin [Key Laboratory of Coastal Environment Processes, Yantai Institute of Coastal Zone Research, Chinese Academy of Sciences, Yantai 264003 (China)

    2012-07-16

    In this study, MnFe{sub 2}O{sub 4}/activated carbon magnetic composites with mass ratio of 1:1, 1:1.5 and 1:2 were synthesized using a simple chemical coprecipitation procedure. A variety of techniques such as X-ray diffractometer, scanning electron microscope, magnetization measurements, BET surface area measurements were used to characterize the structure, morphology and magnetic performance of the prepared composite adsorbents. The results showed that the composites had good magnetic properties, which allowed their convenient magnetic separation from water. Spinel manganese ferrite was found to occur in the magnetic phase and the presence of magnetic particles of MnFe{sub 2}O{sub 4} did not significantly affect the surface area and pore structure of the activated carbon. The magnetic composites were effective for tetracycline (TC) removal from water and the maximal adsorption capacity was 590.5 mmol kg{sup -1} at pH 5.0. The TC adsorption followed pseudo-second-order kinetic model and its removal decreases gradually with an increase in pH value, whereas the removal rate was over 60% even at pH 9.0. The TC adsorption process is endothermic and the increase of temperature is favoring its removal. All these results indicated that the prepared composites had the potential to be used as adsorbents for the removal of TC from water or wastewater. - Highlights: Black-Right-Pointing-Pointer The MnFe{sub 2}O{sub 4}/activated carbon can be easily separated from water using a magnet. Black-Right-Pointing-Pointer The MnFe{sub 2}O{sub 4} did not significantly affect the sorption ability of activated carbon. Black-Right-Pointing-Pointer The magnetic composite was effective for tetracycline removal from water.

  12. Precision Munition Electro-Sciences Facility

    Data.gov (United States)

    Federal Laboratory Consortium — This facility allows the characterization of the electro-magnetic environment produced by a precision weapon in free flight. It can measure the radiofrequency (RF)...

  13. North Slope, Alaska ESI: FACILITY (Facility Points)

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — This data set contains data for oil field facilities for the North Slope of Alaska. Vector points in this data set represent oil field facility locations. This data...

  14. The Radiological Research Accelerator Facility

    International Nuclear Information System (INIS)

    The Radiological Research Accelerator Facility (RARAF) is based on a 4-MV Van de Graaff accelerator, which is used to generate a variety of well-characterized radiation beams for research in radiobiology, radiological physics, and radiation chemistry. It is part of the Center for Radiological Research (CRR) -- formerly the Radiological Research Laboratory (RRL) -- of Columbia University, and its operation is supported as a National Facility by the US Department of Energy (DOE). Fifteen different experiments were run during these 12 months, approximately the same as the previous two years. Brief summaries of each experiment are included. Accelerator usage is summarized and development activities are discussed. 7 refs., 4 tabs

  15. Site maps and facilities listings

    Energy Technology Data Exchange (ETDEWEB)

    1993-11-01

    In September 1989, a Memorandum of Agreement among DOE offices regarding the environmental management of DOE facilities was signed by appropriate Assistant Secretaries and Directors. This Memorandum of Agreement established the criteria for EM line responsibility. It stated that EM would be responsible for all DOE facilities, operations, or sites (1) that have been assigned to DOE for environmental restoration and serve or will serve no future production need; (2) that are used for the storage, treatment, or disposal of hazardous, radioactive, and mixed hazardous waste materials that have been properly characterized, packaged, and labelled, but are not used for production; (3) that have been formally transferred to EM by another DOE office for the purpose of environmental restoration and the eventual return to service as a DOE production facility; or (4) that are used exclusively for long-term storage of DOE waste material and are not actively used for production, with the exception of facilities, operations, or sites under the direction of the DOE Office of Civilian Radioactive Waste Management. As part of the implementation of the Memorandum of Agreement, Field Offices within DOE submitted their listings of facilities, systems, operation, and sites for which EM would have line responsibility. It is intended that EM facility listings will be revised on a yearly basis so that managers at all levels will have a valid reference for the planning, programming, budgeting and execution of EM activities.

  16. Site maps and facilities listings

    International Nuclear Information System (INIS)

    In September 1989, a Memorandum of Agreement among DOE offices regarding the environmental management of DOE facilities was signed by appropriate Assistant Secretaries and Directors. This Memorandum of Agreement established the criteria for EM line responsibility. It stated that EM would be responsible for all DOE facilities, operations, or sites (1) that have been assigned to DOE for environmental restoration and serve or will serve no future production need; (2) that are used for the storage, treatment, or disposal of hazardous, radioactive, and mixed hazardous waste materials that have been properly characterized, packaged, and labelled, but are not used for production; (3) that have been formally transferred to EM by another DOE office for the purpose of environmental restoration and the eventual return to service as a DOE production facility; or (4) that are used exclusively for long-term storage of DOE waste material and are not actively used for production, with the exception of facilities, operations, or sites under the direction of the DOE Office of Civilian Radioactive Waste Management. As part of the implementation of the Memorandum of Agreement, Field Offices within DOE submitted their listings of facilities, systems, operation, and sites for which EM would have line responsibility. It is intended that EM facility listings will be revised on a yearly basis so that managers at all levels will have a valid reference for the planning, programming, budgeting and execution of EM activities

  17. Air Quality Facilities

    Data.gov (United States)

    Iowa State University GIS Support and Research FacilityFacilities with operating permits for Title V of the Federal Clean Air Act, as well as facilities required to submit an air emissions inventory, and other...

  18. Basic Research Firing Facility

    Data.gov (United States)

    Federal Laboratory Consortium — The Basic Research Firing Facility is an indoor ballistic test facility that has recently transitioned from a customer-based facility to a dedicated basic research...

  19. Facility Registry Service (FRS)

    Data.gov (United States)

    U.S. Environmental Protection Agency — The Facility Registry Service (FRS) provides an integrated source of comprehensive (air, water, and waste) environmental information about facilities across EPA,...

  20. Licensed Healthcare Facilities

    Data.gov (United States)

    California Department of Resources — The Licensed Healthcare Facilities point layer represents the locations of all healthcare facilities licensed by the State of California, Department of Health...

  1. High Throughput Facility

    Data.gov (United States)

    Federal Laboratory Consortium — Argonne?s high throughput facility provides highly automated and parallel approaches to material and materials chemistry development. The facility allows scientists...

  2. Laser solenoid radiation test facility

    International Nuclear Information System (INIS)

    The Laser Solenoid Radiation Test Facility (LSRTF) is a concept based on a pulsed plasma source of neutrons, alpha particles, and bremsstrahlung and is characterized by a moderate radiation flux and a large test sample volume. The LSRTF is intermediate in its size, technology, and availability (1985-1990), and consequently has potential for bridging the gap between small present day accelerator-target sources and a large pulsed plasma engineering research facility in the 1990's. It also has important potential as a compact engineering test reactor for realistic operational testing of integrated subsystems for a linear fusion reactor. Its design, performance and operating characteristics are discussed in the present paper. The necessary development programs to bring such a facility into timely operation are also described. (Auth.)

  3. SPHERES National Lab Facility

    Science.gov (United States)

    Benavides, Jose

    2014-01-01

    SPHERES is a facility of the ISS National Laboratory with three IVA nano-satellites designed and delivered by MIT to research estimation, control, and autonomy algorithms. Since Fall 2010, The SPHERES system is now operationally supported and managed by NASA Ames Research Center (ARC). A SPHERES Program Office was established and is located at NASA Ames Research Center. The SPHERES Program Office coordinates all SPHERES related research and STEM activities on-board the International Space Station (ISS), as well as, current and future payload development. By working aboard ISS under crew supervision, it provides a risk tolerant Test-bed Environment for Distributed Satellite Free-flying Control Algorithms. If anything goes wrong, reset and try again! NASA has made the capability available to other U.S. government agencies, schools, commercial companies and students to expand the pool of ideas for how to test and use these bowling ball-sized droids. For many of the researchers, SPHERES offers the only opportunity to do affordable on-orbit characterization of their technology in the microgravity environment. Future utilization of SPHERES as a facility will grow its capabilities as a platform for science, technology development, and education.

  4. Reliable Facility Location Problem with Facility Protection.

    Science.gov (United States)

    Tang, Luohao; Zhu, Cheng; Lin, Zaili; Shi, Jianmai; Zhang, Weiming

    2016-01-01

    This paper studies a reliable facility location problem with facility protection that aims to hedge against random facility disruptions by both strategically protecting some facilities and using backup facilities for the demands. An Integer Programming model is proposed for this problem, in which the failure probabilities of facilities are site-specific. A solution approach combining Lagrangian Relaxation and local search is proposed and is demonstrated to be both effective and efficient based on computational experiments on random numerical examples with 49, 88, 150 and 263 nodes in the network. A real case study for a 100-city network in Hunan province, China, is presented, based on which the properties of the model are discussed and some managerial insights are analyzed. PMID:27583542

  5. Energy solutions for sports facilities

    Energy Technology Data Exchange (ETDEWEB)

    Artuso, Paola; Santiangeli, Adriano [CIRPS: Inter-University Research Centre for Sustainable Development, Sapienza University of Rome, Via Eudossiana, 18, Rome (Italy)

    2008-06-15

    The sports facilities are characterized by special energy needs different from any other user and they are characterized by high heat and electricity loads. For this reason, the aim of this work has been to propose a tool to provide a preliminary estimation of the power and energy required by the sports centres. In addition, the possibility to make the building self-energy sufficient has been considered, thanks to the exploitation of renewable energy sources (RES). The overall work has been performed following three steps: energy needs analysis; local RES availability analysis; energy balance of Sport Centres. Considering that each sport facility is characterized by different energy needs depending on the sport typology itself, the analysis started from the features established by the CONI (National Italian Olympic Committee) standardization. For calculations a program in LabVIEW has been developed to evaluate the energy requirements of the sports centre considering as inputs the sport halls, the playgrounds and the supporting rooms, the level of the sport activity (e.g. agonistic) and the climatic conditions of the area where the facilities are located. The locally available RES are evaluated in order to decide which one can be exploited to feed the Sport Centre. The proposed solution for the energy production refers to a combination of different and innovative technologies which involve, in particular, hydrogen technologies. The energy and costs analysis has been finally carried out for an application case in Dubai. (author)

  6. Facile synthesis, structural characterization, and photoluminescence mechanism of Dy{sup 3+} doped YVO{sub 4} and Ca{sup 2+} co-doped YVO{sub 4}:Dy{sup 3+} nano-lattices

    Energy Technology Data Exchange (ETDEWEB)

    Dhiren Meetei, Sanoujam, E-mail: sdmdhiren@gmail.com; Dorendrajit Singh, Shougaijam, E-mail: dorendrajit@yahoo.co.in, E-mail: mdebensingh@gmail.com [Department of Physics, Manipur University, Canchipur, Imphal-795003, Manipur (India); Deben Singh, Mutum, E-mail: dorendrajit@yahoo.co.in, E-mail: mdebensingh@gmail.com [Department of Physics, Thambal Marik College, Oinam-795134, Bishnupur, Manipur (India)

    2014-05-28

    Light plays a vital role in the evolution of life. From sunlight to candle-light and then to other form of lighting devices, human beings are utilizing light since time immemorial. Lighting devices such as conventional incandescent lamp and fluorescent lamp have been replaced by Light Emitting Diodes (LEDs) for the later is cheap, durable, etc. Now-a-days, phosphor converted LEDs have been burning issues in the fabrication of lighting devices. Especially, lanthanide ion(s) doped phosphors are of great interest for the same. However, doped phosphors have a limitation of luminescence quenching, i.e., instead of increasing luminescence on increasing dopant concentration, the luminescence decreases. Therefore, it must be rectified by one or other means so as to get maximum desirable intensity for uses in display or lighting devices. In the present work, YVO{sub 4}:Dy{sup 3+} and YVO{sub 4}:Dy{sup 3+}/Ca{sup 2+} nano-lattices are synthesized by a facile technique. Structural characterizations such as x-ray diffraction, SEM, TEM, HRTEM, and Selected Area Electron Diffraction (SAED) of the samples are reported. Photoluminescence (PL) excitation and emission, enhanced mechanism, and lifetime are thoroughly discussed. PL intensity of the quenched YVO{sub 4}:Dy{sup 3+} is made increased up to 432.63% by Ca{sup 2+} co-doping. Role of the Ca{sup 2+} on the luminescence enhanced mechanism of YVO{sub 4}:Dy{sup 3+}/Ca{sup 2+} is elucidated.

  7. AOV Facility Tool/Facility Safety Specifications

    Data.gov (United States)

    Department of Transportation — Develop and maintain authorizing documents that are standards that facilities must follow. These standards are references of FAA regulations and are specific to the...

  8. Computational analysis of irradiation facilities at the JSI TRIGA reactor.

    Science.gov (United States)

    Snoj, Luka; Zerovnik, Gašper; Trkov, Andrej

    2012-03-01

    Characterization and optimization of irradiation facilities in a research reactor is important for optimal performance. Nowadays this is commonly done with advanced Monte Carlo neutron transport computer codes such as MCNP. However, the computational model in such calculations should be verified and validated with experiments. In the paper we describe the irradiation facilities at the JSI TRIGA reactor and demonstrate their computational characterization to support experimental campaigns by providing information on the characteristics of the irradiation facilities. PMID:22154389

  9. Beta measurements at Department of Energy facilities

    International Nuclear Information System (INIS)

    Pacific Northwest Laboratory performed a two-step process to characterize the current beta measurement practices at DOE facilities. PNL issued a survey questionnaire on beta measurement practices to DOE facilities and reported the results. PNL measured beta doses and spectra at seven selected DOE facilities and compared selected measurement techniques in the facility environment. This report documents the results of the radiation field measurements and the comparison of measurement techniques at the seven facilities. Data collected included beta dose and spectral measurements at seven DOE facilities that had high beta-to-gamma ratios (using a silicon surface barrier spectrometer, a plastic scintillator spectrometer, and a multielement beta dosimeter). Other dosimeters and survey meters representative of those used at DOE facilities or under development were also used for comparison. Field spectra were obtained under two distinct conditions. Silicon- and scintillation-based spectrometer systems were used under laboratory conditions where high beta-to-gamma dose ratios made the beta spectra easier to observe and analyze. In the second case, beta spectrometers were taken into actual production and maintenance areas of DOE facilities. Analyses of beta and gamma spectra showed that 234Th- /sup 234m/Pa, 231Th, 137Cs, and 90Sr/90Y were the major nuclides contributing to beta doses at the facilities visited. Beta doses from other fission products and 60Co were also measured, but the potential for exposure was less significant. 21 refs., 64 figs., 18 tabs

  10. A negative ion source test facility

    Energy Technology Data Exchange (ETDEWEB)

    Melanson, S.; Dehnel, M., E-mail: morgan@d-pace.com; Potkins, D.; Theroux, J.; Hollinger, C.; Martin, J.; Stewart, T.; Jackle, P.; Withington, S. [D-Pace, Inc., P.O. Box 201, Nelson, British Columbia V1L 5P9 (Canada); Philpott, C.; Williams, P.; Brown, S.; Jones, T.; Coad, B. [Buckley Systems Ltd., 6 Bowden Road, Mount Wellington, Auckland 1060 (New Zealand)

    2016-02-15

    Progress is being made in the development of an Ion Source Test Facility (ISTF) by D-Pace Inc. in collaboration with Buckley Systems Ltd. in Auckland, NZ. The first phase of the ISTF is to be commissioned in October 2015 with the second phase being commissioned in March 2016. The facility will primarily be used for the development and the commercialization of ion sources. It will also be used to characterize and further develop various D-Pace Inc. beam diagnostic devices.

  11. Grout treatment facility dangerous waste permit application

    International Nuclear Information System (INIS)

    The Grout Treatment Facility (GTF) will provide permanent disposal for approximately 43 Mgal of low-level radioactive liquid waste currently being stored in underground tanks on the Hanford Site. The first step in permanent disposal is accomplished by solidifying the liquid waste with cementitious dry materials. The resulting grout is cast within underground vaults. This report on the GTF contains information on the following: Geologic data, hydrologic data, groundwater monitoring program, information, detection monitoring program, groundwater characterization drawings, building emergency plan--grout treatment facility, response action plan for grout treatment facility, Hanford Facility contingency plan, training course descriptions, overview of the Hanford Facility Grout Performance, assessment, bland use and zoning map, waste minimization plan, cover design engineering report, and clay liners (ADMIXTURES) in semiarid environments

  12. Energetics Conditioning Facility

    Data.gov (United States)

    Federal Laboratory Consortium — The Energetics Conditioning Facility is used for long term and short term aging studies of energetic materials. The facility has 10 conditioning chambers of which 2...

  13. Dialysis Facility Compare

    Data.gov (United States)

    U.S. Department of Health & Human Services — Dialysis Facility Compare helps you find detailed information about Medicare-certified dialysis facilities. You can compare the services and the quality of care...

  14. Facility Response Plan (FRP)

    Data.gov (United States)

    U.S. Environmental Protection Agency — A Facility Response Plan (FRP) demonstrates a facility's preparedness to respond to a worst case oil discharge. Under the Clean Water Act, as amended by the Oil...

  15. Projectile Demilitarization Facilities

    Data.gov (United States)

    Federal Laboratory Consortium — The Projectile Wash Out Facility is US Army Ammunition Peculiar Equipment (APE 1300). It is a pilot scale wash out facility that uses high pressure water and steam...

  16. Explosive Components Facility

    Data.gov (United States)

    Federal Laboratory Consortium — The 98,000 square foot Explosive Components Facility (ECF) is a state-of-the-art facility that provides a full-range of chemical, material, and performance analysis...

  17. Armament Technology Facility (ATF)

    Data.gov (United States)

    Federal Laboratory Consortium — The Armament Technology Facility is a 52,000 square foot, secure and environmentally-safe, integrated small arms and cannon caliber design and evaluation facility....

  18. Wastewater Treatment Facilities

    Data.gov (United States)

    Iowa State University GIS Support and Research Facility — Individual permits for municipal, industrial, and semi-public wastewater treatment facilities in Iowa for the National Pollutant Discharge Elimination System...

  19. The Educational Facilities Charrette

    Science.gov (United States)

    Chase, William W.

    1970-01-01

    The deputy director for the Division of Facilities Development of the U.S. Office of Education discusses a technique for studying and resolving educational facilities development problems within the context of total community planning needs." (Author/AA)

  20. Financing Professional Sports Facilities

    OpenAIRE

    Baade, Robert A.; Victor A. Matheson

    2011-01-01

    This paper examines public financing of professional sports facilities with a focus on both early and recent developments in taxpayer subsidization of spectator sports. The paper explores both the magnitude and the sources of public funding for professional sports facilities.

  1. POWER SYSTEMS DEVELOPMENT FACILITY

    Energy Technology Data Exchange (ETDEWEB)

    Unknown

    2002-11-01

    This report discusses test campaign GCT4 of the Kellogg Brown & Root, Inc. (KBR) transport reactor train with a Siemens Westinghouse Power Corporation (Siemens Westinghouse) particle filter system at the Power Systems Development Facility (PSDF) located in Wilsonville, Alabama. The transport reactor is an advanced circulating fluidized-bed reactor designed to operate as either a combustor or a gasifier using one of two possible particulate control devices (PCDs). The transport reactor was operated as a pressurized gasifier during GCT4. GCT4 was planned as a 250-hour test run to continue characterization of the transport reactor using a blend of several Powder River Basin (PRB) coals and Bucyrus limestone from Ohio. The primary test objectives were: Operational Stability--Characterize reactor loop and PCD operations with short-term tests by varying coal-feed rate, air/coal ratio, riser velocity, solids-circulation rate, system pressure, and air distribution. Secondary objectives included the following: Reactor Operations--Study the devolatilization and tar cracking effects from transient conditions during transition from start-up burner to coal. Evaluate the effect of process operations on heat release, heat transfer, and accelerated fuel particle heat-up rates. Study the effect of changes in reactor conditions on transient temperature profiles, pressure balance, and product gas composition. Effects of Reactor Conditions on Synthesis Gas Composition--Evaluate the effect of air distribution, steam/coal ratio, solids-circulation rate, and reactor temperature on CO/CO{sub 2} ratio, synthesis gas Lower Heating Value (LHV), carbon conversion, and cold and hot gas efficiencies. Research Triangle Institute (RTI) Direct Sulfur Recovery Process (DSRP) Testing--Provide syngas in support of the DSRP commissioning. Loop Seal Operations--Optimize loop seal operations and investigate increases to previously achieved maximum solids-circulation rate.

  2. The Radiological Research Accelerator Facility

    International Nuclear Information System (INIS)

    The Radiological Research Accelerator Facility (RARAF) is based on 4-MV Van de Graaff accelerator, which is used to generate a variety of well-characterized radiation beams for research in radiobiology, radiological physics, and radiation chemistry. It is part of the Center for Radiological Research (CRR) -- formerly the Radiological Research Laboratory (RRL) -- of Columbia University, and its operation is supported as a National Facility by the US Department of Energy (DOE). As such, RARAF is available to all potential users on an equal basis, and scientists outside the CRR are encouraged to submit proposals for experiments at RARAF. The operation of the Van de Graaff is supported by the DOE, but the research projects themselves must be supported separately. Brief summaries of research experiments are included. Accelerator usage is summarized and development activities are discussed. 8 refs., 8 tabs

  3. Facilities projects performance measurement system

    International Nuclear Information System (INIS)

    The two DOE-owned facilities at Hanford, the Fuels and Materials Examination Facility (FMEF), and the Fusion Materials Irradiation Test Facility (FMIT), are described. The performance measurement systems used at these two facilities are next described

  4. Facility transition instruction

    International Nuclear Information System (INIS)

    The Bechtel Hanford, Inc. facility transition instruction was initiated in response to the need for a common, streamlined process for facility transitions and to capture the knowledge and experience that has accumulated over the last few years. The instruction serves as an educational resource and defines the process for transitioning facilities to long-term surveillance and maintenance (S and M). Generally, these facilities do not have identified operations missions and must be transitioned from operational status to a safe and stable configuration for long-term S and M. The instruction can be applied to a wide range of facilities--from process canyon complexes like the Plutonium Uranium Extraction Facility or B Plant, to stand-alone, lower hazard facilities like the 242B/BL facility. The facility transition process is implemented (under the direction of the US Department of Energy, Richland Operations Office [RL] Assistant Manager-Environmental) by Bechtel Hanford, Inc. management, with input and interaction with the appropriate RL division and Hanford site contractors as noted in the instruction. The application of the steps identified herein and the early participation of all organizations involved are expected to provide a cost-effective, safe, and smooth transition from operational status to deactivation and S and M for a wide range of Hanford Site facilities

  5. Nuclear Physics accelerator facilities

    International Nuclear Information System (INIS)

    The Nuclear Physics program requires the existence and effective operation of large and complex accelerator facilities. These facilities provide the variety of projectile beams upon which virtually all experimental nuclear research depends. Their capability determine which experiments can be performed and which cannot. Seven existing accelerator facilities are operated by the Nuclear Physics program as national facilities. These are made available to all the Nation's scientists on the basis of scientific merit and technical feasibility of proposals. The national facilities are the Clinton P. Anderson Meson Physics Facility (LAMPF) at Los Alamos National Laboratory; the Bates Linear Accelerator Center at Massachusetts Institute of Technology; the Bevalac at Lawrence Berkeley Laboratory; the Tandem/AGS Heavy Ion Facility at Brookhaven National Laboratory; the ATLAS facility at Argonne National Laboratory; the 88-Inch Cyclotron at Lawrence Berkeley Laboratory; the Holifield Heavy Ion Research Facility at Oak Ridge National Laboratory. The Nuclear Physics Injector at the Stanford Linear Accelerator Center (SLAC) enables the SLAC facility to provide a limited amount of beam time for nuclear physics research on the same basis as the other national facilities. To complement the national facilities, the Nuclear Physics program supports on-campus accelerators at Duke University, Texas A and M University, the University of Washington, and Yale University. The facility at Duke University, called the Triangle Universities Nuclear Laboratory (TUNL), is jointly staffed by Duke University, North Carolina State University, and the University of North Carolina. These accelerators are operated primarily for the research use of the local university faculty, junior scientists, and graduate students

  6. PROJECTIZING AN OPERATING NUCLEAR FACILITY

    Energy Technology Data Exchange (ETDEWEB)

    Adams, N

    2007-07-08

    This paper will discuss the evolution of an operations-based organization to a project-based organization to facilitate successful deactivation of a major nuclear facility. It will describe the plan used for scope definition, staff reorganization, method estimation, baseline schedule development, project management training, and results of this transformation. It is a story of leadership and teamwork, pride and success. Workers at the Savannah River Site's (SRS) F Canyon Complex (FCC) started with a challenge--take all the hazardous byproducts from nearly 50 years of operations in a major, first-of-its-kind nuclear complex and safely get rid of them, leaving the facility cold, dark, dry and ready for whatever end state is ultimately determined by the United States Department of Energy (DOE). And do it in four years, with a constantly changing workforce and steadily declining funding. The goal was to reduce the overall operating staff by 93% and budget by 94%. The facilities, F Canyon and its adjoined sister, FB Line, are located at SRS, a 310-square-mile nuclear reservation near Aiken, S.C., owned by DOE and managed by Washington Group International subsidiary Washington Savannah River Company (WSRC). These facilities were supported by more than 50 surrounding buildings, whose purpose was to provide support services during operations. The radiological, chemical and industrial hazards inventory in the old buildings was significant. The historical mission at F Canyon was to extract plutonium-239 and uranium-238 from irradiated spent nuclear fuel through chemical processing. FB Line's mission included conversion of plutonium solutions into metal, characterization, stabilization and packaging, and storage of both metal and oxide forms. The plutonium metal was sent to another DOE site for use in weapons. Deactivation in F Canyon began when chemical separations activities were completed in 2002, and a cross-functional project team concept was implemented to

  7. PROJECTIZING AN OPERATING NUCLEAR FACILITY

    International Nuclear Information System (INIS)

    This paper will discuss the evolution of an operations-based organization to a project-based organization to facilitate successful deactivation of a major nuclear facility. It will describe the plan used for scope definition, staff reorganization, method estimation, baseline schedule development, project management training, and results of this transformation. It is a story of leadership and teamwork, pride and success. Workers at the Savannah River Site's (SRS) F Canyon Complex (FCC) started with a challenge--take all the hazardous byproducts from nearly 50 years of operations in a major, first-of-its-kind nuclear complex and safely get rid of them, leaving the facility cold, dark, dry and ready for whatever end state is ultimately determined by the United States Department of Energy (DOE). And do it in four years, with a constantly changing workforce and steadily declining funding. The goal was to reduce the overall operating staff by 93% and budget by 94%. The facilities, F Canyon and its adjoined sister, FB Line, are located at SRS, a 310-square-mile nuclear reservation near Aiken, S.C., owned by DOE and managed by Washington Group International subsidiary Washington Savannah River Company (WSRC). These facilities were supported by more than 50 surrounding buildings, whose purpose was to provide support services during operations. The radiological, chemical and industrial hazards inventory in the old buildings was significant. The historical mission at F Canyon was to extract plutonium-239 and uranium-238 from irradiated spent nuclear fuel through chemical processing. FB Line's mission included conversion of plutonium solutions into metal, characterization, stabilization and packaging, and storage of both metal and oxide forms. The plutonium metal was sent to another DOE site for use in weapons. Deactivation in F Canyon began when chemical separations activities were completed in 2002, and a cross-functional project team concept was implemented to successfully

  8. 340 Facility compliance assessment

    International Nuclear Information System (INIS)

    This study provides an environmental compliance evaluation of the RLWS and the RPS systems of the 340 Facility. The emphasis of the evaluation centers on compliance with WAC requirements for hazardous and mixed waste facilities, federal regulations, and Westinghouse Hanford Company (WHC) requirements pertinent to the operation of the 340 Facility. The 340 Facility is not covered under either an interim status Part A permit or a RCRA Part B permit. The detailed discussion of compliance deficiencies are summarized in Section 2.0. This includes items of significance that require action to ensure facility compliance with WAC, federal regulations, and WHC requirements. Outstanding issues exist for radioactive airborne effluent sampling and monitoring, radioactive liquid effluent sampling and monitoring, non-radioactive liquid effluent sampling and monitoring, less than 90 day waste storage tanks, and requirements for a permitted facility

  9. Facility Effluent Monitoring Plan for Pacific Northwest National Laboratory Balance-of-Plant Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Ballinger, M.Y.; Shields, K.D.

    1999-04-02

    The Pacific Northwest National Laboratory (PNNL) operates a number of research and development (R and D) facilities for the Department of Energy on the Hanford Site. According to DOE Order 5400.1, a Facility Effluent Monitoring Plan is required for each site, facility, or process that uses, generates, releases, or manages significant pollutants or hazardous materials. Three of the R and D facilities: the 325, 331, and 3720 Buildings, are considered major emission points for radionuclide air sampling and thus individual Facility Effluent Monitoring Plans (FEMPs) have been developed for them. Because no definition of ''significant'' is provided in DOE Order 5400.1 or the accompanying regulatory guide DOE/EH-0173T, this FEMP was developed to describe monitoring requirements in the DOE-owned, PNNL-operated facilities that do not have individual FEMPs. The remainder of the DOE-owned, PNNL-operated facilities are referred to as Balance-of-Plant (BOP) facilities. Activities in the BOP facilities range from administrative to laboratory and pilot-scale R and D. R and D activities include both radioactive and chemical waste characterization, fluid dynamics research, mechanical property testing, dosimetry research, and molecular sciences. The mission and activities for individual buildings are described in the FEMP.

  10. Facility Effluent Monitoring Plan for Pacific Northwest National Laboratory Balance-of-Plant Facilities

    International Nuclear Information System (INIS)

    The Pacific Northwest National Laboratory (PNNL) operates a number of research and development (R and D) facilities for the Department of Energy on the Hanford Site. According to DOE Order 5400.1, a Facility Effluent Monitoring Plan is required for each site, facility, or process that uses, generates, releases, or manages significant pollutants or hazardous materials. Three of the R and D facilities: the 325, 331, and 3720 Buildings, are considered major emission points for radionuclide air sampling and thus individual Facility Effluent Monitoring Plans (FEMPs) have been developed for them. Because no definition of ''significant'' is provided in DOE Order 5400.1 or the accompanying regulatory guide DOE/EH-0173T, this FEMP was developed to describe monitoring requirements in the DOE-owned, PNNL-operated facilities that do not have individual FEMPs. The remainder of the DOE-owned, PNNL-operated facilities are referred to as Balance-of-Plant (BOP) facilities. Activities in the BOP facilities range from administrative to laboratory and pilot-scale R and D. R and D activities include both radioactive and chemical waste characterization, fluid dynamics research, mechanical property testing, dosimetry research, and molecular sciences. The mission and activities for individual buildings are described in the FEMP

  11. Synchrotron radiation facilities

    CERN Multimedia

    1972-01-01

    Particularly in the past few years, interest in using the synchrotron radiation emanating from high energy, circular electron machines has grown considerably. In our February issue we included an article on the synchrotron radiation facility at Frascati. This month we are spreading the net wider — saying something about the properties of the radiation, listing the centres where synchrotron radiation facilities exist, adding a brief description of three of them and mentioning areas of physics in which the facilities are used.

  12. Air gun test facility

    International Nuclear Information System (INIS)

    This paper describes a facility that is potentially useful in providing data for models to predict the effects of nuclear explosions on cities. IIT Research Institute has a large air gun facility capable of launching heavy items of a wide variety of geometries to velocities ranging from about 80 fps to 1100 fps. The facility and its capabilities are described, and city model problem areas capable of investigation using the air gun are presented

  13. Textiles Performance Testing Facilities

    Data.gov (United States)

    Federal Laboratory Consortium — The Textiles Performance Testing Facilities has the capabilities to perform all physical wet and dry performance testing, and visual and instrumental color analysis...

  14. Region 9 NPDES Facilities

    Data.gov (United States)

    U.S. Environmental Protection Agency — Point geospatial dataset representing locations of NPDES Facilities. NPDES (National Pollution Discharge Elimination System) is an EPA permit program that regulates...

  15. Neutron Therapy Facility

    Data.gov (United States)

    Federal Laboratory Consortium — The Neutron Therapy Facility provides a moderate intensity, broad energy spectrum neutron beam that can be used for short term irradiations for radiobiology (cells)...

  16. DUPIC facility engineering

    Energy Technology Data Exchange (ETDEWEB)

    Park, J. J.; Lee, H. H.; Kim, K. H. and others

    2000-03-01

    The objectives of this study are (1) the refurbishment for PIEF(Post Irradiation Examination Facility) and M6 hot-cell in IMEF(Irradiated Material Examination Facility), (2) the establishment of the compatible facility for DUPIC fuel fabrication experiments which is licensed by government organization, and (3) the establishment of the transportation system and transportation cask for nuclear material between facilities. The report for this project describes following contents, such as objectives, necessities, scope, contents, results of current step, R and D plan in future and etc.

  17. High Combustion Research Facility

    Data.gov (United States)

    Federal Laboratory Consortium — At NETL's High-Pressure Combustion Research Facility in Morgantown, WV, researchers can investigate new high-pressure, high-temperature hydrogen turbine combustion...

  18. Target Assembly Facility

    Data.gov (United States)

    Federal Laboratory Consortium — The Target Assembly Facility integrates new armor concepts into actual armored vehicles. Featuring the capability ofmachining and cutting radioactive materials, it...

  19. Pavement Testing Facility

    Data.gov (United States)

    Federal Laboratory Consortium — Comprehensive Environmental and Structural Analyses The ERDC Pavement Testing Facility, located on the ERDC Vicksburg campus, was originally constructed to provide...

  20. Composite Structures Manufacturing Facility

    Data.gov (United States)

    Federal Laboratory Consortium — The Composite Structures Manufacturing Facility specializes in the design, analysis, fabrication and testing of advanced composite structures and materials for both...

  1. Joint Computing Facility

    Data.gov (United States)

    Federal Laboratory Consortium — Raised Floor Computer Space for High Performance Computing The ERDC Information Technology Laboratory (ITL) provides a robust system of IT facilities to develop and...

  2. Geodynamics Research Facility

    Data.gov (United States)

    Federal Laboratory Consortium — This GSL facility has evolved over the last three decades to support survivability and protective structures research. Experimental devices include three gas-driven...

  3. DUPIC facility engineering

    International Nuclear Information System (INIS)

    The objectives of this study are 1) the refurbishment for PIEF(Post Irradiation Examination Facility) and M6 hot-cell in IMEF(Irradiated Material Examination Facility), 2) the establishment of the compatible facility for DUPIC fuel fabrication experiments which is licensed by government organization, and 3) the establishment of the transportation system and transportation cask for nuclear material between facilities. The report for this project describes following contents, such as objectives, necessities, scope, contents, results of current step, R and D plan in future and etc

  4. Universal Drive Train Facility

    Data.gov (United States)

    Federal Laboratory Consortium — This vehicle drive train research facility is capable of evaluating helicopter and ground vehicle power transmission technologies in a system level environment. The...

  5. Manufacturing Demonstration Facility (MDF)

    Data.gov (United States)

    Federal Laboratory Consortium — The U.S. Department of Energy Manufacturing Demonstration Facility (MDF) at Oak Ridge National Laboratory (ORNL) provides a collaborative, shared infrastructure to...

  6. Proximal Probes Facility

    Data.gov (United States)

    Federal Laboratory Consortium — The Proximal Probes Facility consists of laboratories for microscopy, spectroscopy, and probing of nanostructured materials and their functional properties. At the...

  7. GPS Test Facility

    Data.gov (United States)

    Federal Laboratory Consortium — The Global Positioning System (GPS) Test Facility Instrumentation Suite (GPSIS) provides great flexibility in testing receivers by providing operational control of...

  8. School Facilities Survey.

    Science.gov (United States)

    Saunders, Harry B.

    This survey of facility needs includes an evaluation of staff organization and operating procedures for the Philadelphia Public School District. The educational policies adopted by the Philadelphia Board of Education relating to school facilities are discussed, and existing sites and buildings, population enrollment data, and financial data are…

  9. Science Facilities Bibliography.

    Science.gov (United States)

    National Science Foundation, Washington, DC.

    A bibliographic collection on science buildings and facilities is cited with many different reference sources for those concerned with the design, planning, and layout of science facilities. References are given covering a broad scope of information on--(1) physical plant planning, (2) management and safety, (3) building type studies, (4) design…

  10. FACILITIES FOR PHYSICAL FITNESS.

    Science.gov (United States)

    MUSIAL, STAN

    THIS ARTICLE CITES THE LOW PRIORITY THAT PHYSICAL EDUCATION GENERALLY HAS IN CURRICULUM AND SCHOOL FACILITY PLANNING. IT ALSO CITES THE REASONS FOR DEVELOPING MORE ADEQUATE PHYSICAL EDUCATION FACILITIES--(1) OUR WAY OF LIFE NO LONGER PROVIDES VIGOROUS PHYSICAL ACTIVITY NECESSARY FOR HEALTHY DEVELOPMENT, (2) A DIRECT RELATIONSHIP EXISTS BETWEEN…

  11. Florida Educational Facilities, 1999.

    Science.gov (United States)

    Florida State Dept. of Education, Tallahassee. Office of Educational Facilities.

    This publication describes Florida school and community college facilities completed in 1999, including photographs and floor plans. The facilities profiled are: Buchholz High School (Alachua County); Gator Run Elementary School (Broward); Corkscrew Elementary School (Collier); The 500 Role Models Academy of Excellence (Miami-Dade); Caribbean…

  12. Bevalac biomedical facility

    International Nuclear Information System (INIS)

    This paper describes the physical layout of the Bevalac Facility and the research programs carried out at the facility. Beam time on the Bevalac is divided between two disciplines: one-third for biomedical research and two-thirds for nuclear science studies. The remainder of the paper discusses the beam delivery system including dosimetry, beam sharing and beam scanning

  13. The Evaluation of the Selected On-Site Location for a New Nuclear Facility on a Multi-Facility Site

    International Nuclear Information System (INIS)

    Pelindaba is a multi-facility nuclear and chemical site in the North West Province of South Africa where Necsa currently operates SAFARI-1. A proposed new dedicated isotope production reactor facility is to be constructed on this site. The siting process followed is tailored from the IAEA guidelines. This paper describes the site selection and site characterization for a new facility at Pelindaba. (author)

  14. Grout treatment facility operation

    International Nuclear Information System (INIS)

    This paper summarizes the operation of the Grout Treatment Facility from initial testing to the final disposal to date of 3.8 x 103 m3 (1 Mgal) of low-level radioactive waste. It describes actual component testing and verification, testing of the full-scale system with simulated waste feed, summary of the radioactive disposal operation, lessons learned and equipment performance summary, facility impacts from safety analyses, long-term performance assessments, the Part B application, and projected facility modifications. The Grout Treatment Facility is one of two operations for permanently disposing of liquid defense wastes at the Hanford site near Richland, Washington, for the U.S. Department of Energy. High- and low-level radioactive wastes have been accumulating from defense material production since the mid-1940s at the Hanford site. All radioactive low-level and low-level mixed liquid wastes will be disposed of at the future Hanford Vitrification Facility

  15. Nuclear physics accelerator facilities

    International Nuclear Information System (INIS)

    This paper describes many of the nuclear physics heavy-ion accelerator facilities in the US and the research programs being conducted. The accelerators described are: Argonne National Laboratory--ATLAS; Brookhaven National Laboratory--Tandem/AGS Heavy Ion Facility; Brookhaven National Laboratory--Relativistic Heavy Ion Collider (RHIC) (Proposed); Continuous Electron Beam Accelerator Facility; Lawrence Berkeley Laboratory--Bevalac; Lawrence Berkeley Laboratory--88-Inch Cyclotron; Los Alamos National Laboratory--Clinton P. Anderson Meson Physics Facility (LAMPF); Massachusetts Institute of Technology--Bates Linear Accelerator Center; Oak Ridge National Laboratory--Holifield Heavy Ion Research Facility; Oak Ridge National Laboratory--Oak Ridge Electron Linear Accelerator; Stanford Linear Accelerator Center--Nuclear Physics Injector; Texas AandM University--Texas AandM Cyclotron; Triangle Universities Nuclear Laboratory (TUNL); University of Washington--Tandem/Superconducting Booster; and Yale University--Tandem Van de Graaff

  16. POWER SYSTEMS DEVELOPMENT FACILITY

    Energy Technology Data Exchange (ETDEWEB)

    Unknown

    2002-05-01

    This report discusses test campaign GCT3 of the Halliburton KBR transport reactor train with a Siemens Westinghouse Power Corporation (Siemens Westinghouse) particle filter system at the Power Systems Development Facility (PSDF) located in Wilsonville, Alabama. The transport reactor is an advanced circulating fluidized-bed reactor designed to operate as either a combustor or a gasifier using one of two possible particulate control devices (PCDs). The transport reactor was operated as a pressurized gasifier during GCT3. GCT3 was planned as a 250-hour test run to commission the loop seal and continue the characterization of the limits of operational parameter variations using a blend of several Powder River Basin coals and Bucyrus limestone from Ohio. The primary test objectives were: (1) Loop Seal Commissioning--Evaluate the operational stability of the loop seal with sand and limestone as a bed material at different solids circulation rates and establish a maximum solids circulation rate through the loop seal with the inert bed. (2) Loop Seal Operations--Evaluate the loop seal operational stability during coal feed operations and establish maximum solids circulation rate. Secondary objectives included the continuation of reactor characterization, including: (1) Operational Stability--Characterize the reactor loop and PCD operations with short-term tests by varying coal feed, air/coal ratio, riser velocity, solids circulation rate, system pressure, and air distribution. (2) Reactor Operations--Study the devolatilization and tar cracking effects from transient conditions during transition from start-up burner to coal. Evaluate the effect of process operations on heat release, heat transfer, and accelerated fuel particle heat-up rates. Study the effect of changes in reactor conditions on transient temperature profiles, pressure balance, and product gas composition. (3) Effects of Reactor Conditions on Syngas Composition--Evaluate the effect of air distribution, steam

  17. Reactor coolant cleanup facility

    International Nuclear Information System (INIS)

    A depressurization device is disposed in pipelines upstream of recycling pumps of a reactor coolant cleanup facility to reduce a pressure between the pressurization device and the recycling pump at the downstream, thereby enabling high pressure coolant injection from other systems by way of the recycling pumps. Upon emergency, the recycling pumps of the coolant cleanup facility can be used in common to an emergency reactor core cooling facility and a reactor shutdown facility. Since existent pumps of the emergency reactor core cooling facility and the reactor shutdown facility which are usually in a stand-by state can be removed, operation confirmation test and maintenance for equipments in both of facilities can be saved, so that maintenance and reliability of the plant are improved and burdens on operators can also be mitigated. Moreover, low pressure design can be adopted for a non-regenerative heat exchanger and recycling coolant pumps, which enables to improve the reliability and economical property due to reduction of possibility of leakage. (N.H.)

  18. DUPIC facility engineering

    Energy Technology Data Exchange (ETDEWEB)

    Lee, J. S.; Choi, J. W.; Go, W. I.; Kim, H. D.; Song, K. C.; Jeong, I. H.; Park, H. S.; Im, C. S.; Lee, H. M.; Moon, K. H.; Hong, K. P.; Lee, K. S.; Suh, K. S.; Kim, E. K.; Min, D. K.; Lee, J. C.; Chun, Y. B.; Paik, S. Y.; Lee, E. P.; Yoo, G. S.; Kim, Y. S.; Park, J. C.

    1997-09-01

    In the early stage of the project, a comprehensive survey was conducted to identify the feasibility of using available facilities and of interface between those facilities. It was found out that the shielded cell M6 interface between those facilities. It was found out that the shielded cell M6 of IMEF could be used for the main process experiments of DUPIC fuel fabrication in regard to space adequacy, material flow, equipment layout, etc. Based on such examination, a suitable adapter system for material transfer around the M6 cell was engineered. Regarding the PIEF facility, where spent PWR fuel assemblies are stored in an annex pool, disassembly devices in the pool are retrofitted and spent fuel rod cutting and shipping system to the IMEF are designed and built. For acquisition of casks for radioactive material transport between the facilities, some adaptive refurbishment was applied to the available cask (Padirac) based on extensive analysis on safety requirements. A mockup test facility was newly acquired for remote test of DUPIC fuel fabrication process equipment prior to installation in the M6 cell of the IMEF facility. (author). 157 refs., 57 tabs., 65 figs.

  19. DUPIC facility engineering

    International Nuclear Information System (INIS)

    In the early stage of the project, a comprehensive survey was conducted to identify the feasibility of using available facilities and of interface between those facilities. It was found out that the shielded cell M6 interface between those facilities. It was found out that the shielded cell M6 of IMEF could be used for the main process experiments of DUPIC fuel fabrication in regard to space adequacy, material flow, equipment layout, etc. Based on such examination, a suitable adapter system for material transfer around the M6 cell was engineered. Regarding the PIEF facility, where spent PWR fuel assemblies are stored in an annex pool, disassembly devices in the pool are retrofitted and spent fuel rod cutting and shipping system to the IMEF are designed and built. For acquisition of casks for radioactive material transport between the facilities, some adaptive refurbishment was applied to the available cask (Padirac) based on extensive analysis on safety requirements. A mockup test facility was newly acquired for remote test of DUPIC fuel fabrication process equipment prior to installation in the M6 cell of the IMEF facility. (author). 157 refs., 57 tabs., 65 figs

  20. Biotechnology Facility: An ISS Microgravity Research Facility

    Science.gov (United States)

    Gonda, Steve R.; Tsao, Yow-Min

    2000-01-01

    The International Space Station (ISS) will support several facilities dedicated to scientific research. One such facility, the Biotechnology Facility (BTF), is sponsored by the Microgravity Sciences and Applications Division (MSAD) and developed at NASA's Johnson Space Center. The BTF is scheduled for delivery to the ISS via Space Shuttle in April 2005. The purpose of the BTF is to provide: (1) the support structure and integration capabilities for the individual modules in which biotechnology experiments will be performed, (2) the capability for human-tended, repetitive, long-duration biotechnology experiments, and (3) opportunities to perform repetitive experiments in a short period by allowing continuous access to microgravity. The MSAD has identified cell culture and tissue engineering, protein crystal growth, and fundamentals of biotechnology as areas that contain promising opportunities for significant advancements through low-gravity experiments. The focus of this coordinated ground- and space-based research program is the use of the low-gravity environment of space to conduct fundamental investigations leading to major advances in the understanding of basic and applied biotechnology. Results from planned investigations can be used in applications ranging from rational drug design and testing, cancer diagnosis and treatments and tissue engineering leading to replacement tissues.

  1. Sustainable Facilities Management

    DEFF Research Database (Denmark)

    Nielsen, Susanne Balslev; Elle, Morten; Hoffmann, Birgitte;

    2004-01-01

    The Danish public housing sector has more than 20 years of experience with sustainable facilities management based on user involvement. The paper outlines this development in a historical perspective and gives an analysis of different approaches to sustainable facilities management. The focus...... is on the housing departments and strateies for the management of the use of resources. The research methods used are case studies based on interviews in addition to literature studies. The paper explores lessons to be learned about sustainable facilities management in general, and points to a need for new...

  2. Studying facility siting

    Energy Technology Data Exchange (ETDEWEB)

    Weber, R.J. [PSRG Consultants Inc. (United States)

    2001-02-01

    The article relates to safety in facility siting and the many factors to be taken into account at an early planning stage. Outline flowcharts for analysing the process for a potential explosion show: Stage 1 -building and hazard identification; Stage 2 -building evaluation and Stage 3 -Risk management. A similar chart relates to analysis for a potential toxic release. A 68-point checklist of factors to be considered in a facility siting study is given. It is pointed out that apart from meeting regulatory requirements, a sound facility siting study can lead to more effective use of resources.

  3. Facility Description 2012. Summary report of the encapsulation plant and disposal facility designs

    International Nuclear Information System (INIS)

    The purpose of the facility description is to be a specific summary report of the scope of Posiva's nuclear facilities (encapsulation plant and disposal facility) in Olkiluoto. This facility description is based on the 2012 designs and completing Posiva working reports. The facility description depicts the nuclear facilities and their operation as the disposal of spent nuclear fuel starts in Olkiluoto in about 2020. According to the decisions-in-principle of the government, the spent nuclear fuel from Loviisa and Olkiluoto nuclear power plants in operation and in future cumulative spent nuclear fuel from Loviisa 1 and 2, Olkiluoto 1, 2, 3 and 4 nuclear power plants, is permitted to be disposed of in Olkiluoto bedrock. The design of the disposal facility is based on the KBS-3V concept (vertical disposal). Long-term safety concept is based on the multi-barrier principle i.e. several release barriers, which ensure one another so that insufficiency in the performance of one barrier doesn't jeopardize long-term safety of the disposal. The release barriers are the following: canister, bentonite buffer and deposition tunnel backfill, and the host rock around the repository. The canisters are installed into the deposition holes, which are bored to the floor of the deposition tunnels. The canisters are enveloped with compacted bentonite blocks, which swell after absorbing water. The surrounding bedrock and the central and access tunnel backfill provide additional retardation, retention, and dilution. The nuclear facilities consist of an encapsulation plant and of underground final disposal facility including other aboveground buildings and surface structures serving the facility. The access tunnel and ventilation shafts to the underground disposal facility and some auxiliary rooms are constructed as a part of ONKALO underground rock characterization facility during years 2004-2014. The construction works needed for the repository start after obtaining the construction

  4. Skilled nursing or rehabilitation facilities

    Science.gov (United States)

    ... page: //medlineplus.gov/ency/patientinstructions/000435.htm Skilled nursing or rehabilitation facilities To use the sharing features ... facility. Who Needs to go to a Skilled Nursing or Rehabilitation Facility? Your health care provider may ...

  5. Design of Children Entertainment Facilities

    OpenAIRE

    Mei Li

    2009-01-01

    In this paper, mainly through analysis of problems on existing children entertainment facilities and the impact of children entertainment facilities on children psychological development, it is to be discussed about the key point of children entertainment facilities design.

  6. Hydrography - Water Pollution Control Facilities

    Data.gov (United States)

    NSGIC GIS Inventory (aka Ramona) — A Water Pollution Control Facility is a DEP primary facility type related to the Water Pollution Control Program. The sub-facility types related to Water Pollution...

  7. National Solar Thermal Test Facility

    Data.gov (United States)

    Federal Laboratory Consortium — The National Solar Thermal Test Facility (NSTTF) is the only test facility in the United States of its type. This unique facility provides experimental engineering...

  8. GPS Satellite Simulation Facility

    Data.gov (United States)

    Federal Laboratory Consortium — The GPS satellite simulation facility consists of a GPS satellite simulator controlled by either a Silicon Graphics Origin 2000 or PC depending upon unit under test...

  9. Frost Effects Research Facility

    Data.gov (United States)

    Federal Laboratory Consortium — Full-scale study in controlled conditions The Frost Effects Research Facility (FERF) is the largest refrigerated warehouse in the United States that can be used for...

  10. Mark 1 Test Facility

    Data.gov (United States)

    Federal Laboratory Consortium — The Mark I Test Facility is a state-of-the-art space environment simulation test chamber for full-scale space systems testing. A $1.5M dollar upgrade in fiscal year...

  11. Combustion Research Facility

    Data.gov (United States)

    Federal Laboratory Consortium — For more than 30 years The Combustion Research Facility (CRF) has served as a national and international leader in combustion science and technology. The need for a...

  12. The Birmingham Irradiation Facility

    International Nuclear Information System (INIS)

    At the end of 2012 the proton irradiation facility at the CERN PS will shut down for two years. With this in mind, we have been developing a new ATLAS scanning facility at the University of Birmingham Medical Physics cyclotron. With proton beams of energy approximately 30 MeV, fluences corresponding to those of the upgraded Large Hadron Collider (HL-LHC) can be reached conveniently. The facility can be used to irradiate silicon sensors, optical components and mechanical structures (e.g. carbon fibre sandwiches) for the LHC upgrade programme. Irradiations of silicon sensors can be carried out in a temperature controlled cold box that can be scanned through the beam. The facility is described in detail along with the first tests carried out with mini (1×1 cm2) silicon sensors

  13. Dialysis Facility Compare Data

    Data.gov (United States)

    U.S. Department of Health & Human Services — These are the official datasets used on the Medicare.gov Dialysis Facility Compare Website provided by the Centers for Medicare and Medicaid Services. These data...

  14. IHS Facility Locator

    Data.gov (United States)

    U.S. Department of Health & Human Services — This map can be used to find an Indian Health Service, Tribal or Urban Indian Health Program facility. This map can be used to: Zoom in to a general location to...

  15. Electra Laser Facility

    Data.gov (United States)

    Federal Laboratory Consortium — FUNCTION: The Electra Laser Facility is used to develop the science and technology needed to develop a reliable, efficient, high-energy, repetitively pulsed krypton...

  16. College/University Facilities.

    Science.gov (United States)

    Athletic Business, 2002

    2002-01-01

    Describes the building designs of 117 state-of-the-art of college athletic and recreational facilities, including the educational contexts and design goals. Includes information on architects and designers, construction cost, size, and occupancy date. Also provides photographs. (EV)

  17. Decontamination of nuclear facilities

    International Nuclear Information System (INIS)

    Thirty-seven papers were presented at this conference in five sessions. Topics covered include regulation, control and consequences of decontamination; decontamination of components and facilities; chemical and non-chemical methods of decontamination; and TMI decontamination experience

  18. The Birmingham Irradiation Facility

    CERN Document Server

    Dervan, P; Hodgson, P; Marin-Reyes, H; Wilson, J

    2013-01-01

    At the end of 2012 the proton irradiation facility at the CERN PS [1] will shut down for two years. With this in mind, we have been developing a new ATLAS scanning facility at the University of Birmingham Medical Physics cyclotron. With proton beams of energy approximately 30 MeV, fluences corresponding to those of the upgraded Large Hadron Collider (HL-LHC) can be reached conveniently. The facility can be used to irradiate silicon sensors, optical components and mechanical structures (e.g. carbon fibre sandwiches) for the LHC upgrade programme. Irradiations of silicon sensors can be carried out in a temperature controlled cold box that can be scanned through the beam. The facility is described in detail along with the first tests carried out with mini (1 x 1 cm^2 ) silicon sensors.

  19. Coastal Inlet Model Facility

    Data.gov (United States)

    Federal Laboratory Consortium — The Coastal Inlet Model Facility, as part of the Coastal Inlets Research Program (CIRP), is an idealized inlet dedicated to the study of coastal inlets and equipped...

  20. FacilitiesSchools_PTSCHOOL

    Data.gov (United States)

    Vermont Center for Geographic Information — FacilitiesSchools_PTSCHOOL is designed to provide point locations of every Vermont School along with the established school ID (PSID) for geographic analysis of...

  1. Laser Guidance Analysis Facility

    Data.gov (United States)

    Federal Laboratory Consortium — This facility, which provides for real time, closed loop evaluation of semi-active laser guidance hardware, has and continues to be instrumental in the development...

  2. FDA Certified Mammography Facilities

    Science.gov (United States)

    ... Products Radiation-Emitting Products Home Radiation-Emitting Products Mammography Quality Standards Act and Program Consumer Information (MQSA) ... it Email Print This list of FDA Certified Mammography Facilities is updated weekly. If you click on ...

  3. Environmental Test Facility (ETF)

    Data.gov (United States)

    Federal Laboratory Consortium — The Environmental Test Facility (ETF) provides non-isolated shock testing for stand-alone equipment and full size cabinets under MIL-S-901D specifications. The ETF...

  4. Water Tunnel Facility

    Data.gov (United States)

    Federal Laboratory Consortium — NETL’s High-Pressure Water Tunnel Facility in Pittsburgh, PA, re-creates the conditions found 3,000 meters beneath the ocean’s surface, allowing scientists to study...

  5. Wind Tunnel Testing Facilities

    Data.gov (United States)

    Federal Laboratory Consortium — NASA Ames Research Center is pleased to offer the services of our premier wind tunnel facilities that have a broad range of proven testing capabilities to customers...

  6. Liquid Effluent Retention Facility

    Data.gov (United States)

    Federal Laboratory Consortium — The Liquid Effluent Retention Facility (LERF) is located in the central part of the Hanford Site. LERF is permitted by the State of Washington and has three liquid...

  7. Hypersonic Tunnel Facility (HTF)

    Data.gov (United States)

    Federal Laboratory Consortium — The Hypersonic Tunnel Facility (HTF) is a blow-down, non-vitiated (clean air) free-jet wind tunnel capable of testing large-scale, propulsion systems at Mach 5, 6,...

  8. Healthcare Facility Locations

    Data.gov (United States)

    U.S. Department of Health & Human Services — MAP:http://tinyurl.com/HealthcareFacilityLocationsMap The California Department of Public Health (CDPH), Center for Health Care Quality, Licensing and Certification...

  9. Pittsburgh City Facilities

    Data.gov (United States)

    Allegheny County / City of Pittsburgh / Western PA Regional Data Center — Pittsburgh City FacilitiesIncludes: City Administrative Buildings, Police Stations, Fire Stations, EMS Stations, DPW Sites, Senior Centers, Recreation Centers,...

  10. Indoor Ground Ejection Facility

    Data.gov (United States)

    Federal Laboratory Consortium — This climate controlled facility is used to evaluate air stores and equipment to determine ejection velocities, store pitch rates, and arming wire and device system...

  11. Robotics Research Facility

    Data.gov (United States)

    Federal Laboratory Consortium — This 60 feet x 100 feet structure on the grounds of the Fort Indiantown Gap Pennsylvania National Guard (PNG) Base is a mixed-use facility comprising office space,...

  12. Advanced Microscopy Facility

    Data.gov (United States)

    Federal Laboratory Consortium — FUNCTION: Provides a facility for high-resolution studies of complex biomolecular systems. The goal is an understanding of how to engineer biomolecules for various...

  13. Air Data Calibration Facility

    Data.gov (United States)

    Federal Laboratory Consortium — This facility is for low altitude subsonic altimeter system calibrations of air vehicles. Mission is a direct support of the AFFTC mission. Postflight data merge is...

  14. Skilled Nursing Facility PPS

    Data.gov (United States)

    U.S. Department of Health & Human Services — Section 4432(a) of the Balanced Budget Act (BBA) of 1997 modified how payment is made for Medicare skilled nursing facility (SNF) services. Effective with cost...

  15. Ballistic Test Facility

    Data.gov (United States)

    Federal Laboratory Consortium — The Ballistic Test Facility is comprised of two outdoor and one indoor test ranges, which are all instrumented for data acquisition and analysis. Full-size aircraft...

  16. Structural Test Facility

    Data.gov (United States)

    Federal Laboratory Consortium — Provides a wide variety of testing equipment, fixtures and facilities to perform both unique aviation component testing as well as common types of materials testing...

  17. Facility Effluent Monitoring Plan for Pacific Northwest National Laboratory Balance-of-Plant Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Ballinger, Marcel Y.; Gervais, Todd L.

    2004-11-15

    The Pacific Northwest National Laboratory (PNNL) operates a number of Research & Development (R&D) facilities for the U.S. Department of Energy (DOE) on the Hanford Site. Facility effluent monitoring plans (FEMPs) have been developed to document the facility effluent monitoring portion of the Environmental Monitoring Plan (DOE 2000) for the Hanford Site. Three of PNNL’s R&D facilities, the 325, 331, and 3720 Buildings, are considered major emission points for radionuclide air sampling, and individual FEMPs were developed for these facilities in the past. In addition, a balance-of-plant (BOP) FEMP was developed for all other DOE-owned, PNNL-operated facilities at the Hanford Site. Recent changes, including shutdown of buildings and transition of PNNL facilities to the Office of Science, have resulted in retiring the 3720 FEMP and combining the 331 FEMP into the BOP FEMP. This version of the BOP FEMP addresses all DOE-owned, PNNL-operated facilities at the Hanford Site, excepting the Radiochemical Processing Laboratory, which has its own FEMP because of the unique nature of the building and operations. Activities in the BOP facilities range from administrative to laboratory and pilot-scale R&D. R&D activities include both radioactive and chemical waste characterization, fluid dynamics research, mechanical property testing, dosimetry research, and molecular sciences. The mission and activities for individual buildings are described in Appendix A. Potential radioactive airborne emissions in the BOP facilities are estimated annually using a building inventory-based approach provided in federal regulations. Sampling at individual BOP facilities is based on a potential-to-emit assessment. Some of these facilities are considered minor emission points and thus are sampled routinely, but not continuously, to confirm the low emission potential. One facility, the 331 Life Sciences Laboratory, has a major emission point and is sampled continuously. Sampling systems are

  18. Design of the disposal facility 2012

    International Nuclear Information System (INIS)

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

  19. Building 211 cyclotron characterization survey report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-03-30

    The Building 211 Cyclotron Characterization Survey includes an assessment of the radioactive and chemical inventory of materials stored within the facility; an evaluation of the relative distribution of accelerator-produced activation products within various cyclotron components and adjacent structures; measurement of the radiation fields throughout the facility; measurement and assessment of internal and external radioactive surface contamination on various equipment, facility structures, and air-handling systems; and an assessment of lead (Pb) paint and asbestos hazards within the facility.

  20. Nuclear physics accelerator facilities

    International Nuclear Information System (INIS)

    Brief descriptions are given of DOE and Nuclear Physics program operated and sponsored accelerator facilities. Specific facilities covered are the Argonne Tandem/Linac Accelerator System, the Tandem/AGS Heavy Ion Facility at Brookhaven National Laboratory, the proposed Continuous Beam Accelerator at Newport News, Virginia, the Triangle Universities Nuclear Laboratory at Duke University, the Bevalac and the SuperHILAC at Lawrence Berkeley Laboratory, the 88-Inch Cyclotron at Lawrence Berkeley Laboratory, the Clinton P. Anderson Meson Physics Facility at Los Alamos National Laboratory, the Bates Linear Accelerator Center at Massachusetts Institute of Technology, the Holifield Heavy Ion Research Facility at Oak Ridge National Laboratory, the Nuclear Physics Injector at Stanford Linear Accelerator Center, the Texas A and M Cyclotrons, the Tandem/Superconducting Booster Accelerator at the University of Washington and the Tandem Van de Graaff at the A.W. Wright Nuclear Structure Laboratory of Yale University. Included are acquisition cost, research programs, program accomplishments, future directions, and operating parameters of each facility

  1. The CUTLASS database facilities

    International Nuclear Information System (INIS)

    The enhancement of the CUTLASS database management system to provide improved facilities for data handling is seen as a prerequisite to its effective use for future power station data processing and control applications. This particularly applies to the larger projects such as AGR data processing system refurbishments, and the data processing systems required for the new Coal Fired Reference Design stations. In anticipation of the need for improved data handling facilities in CUTLASS, the CEGB established a User Sub-Group in the early 1980's to define the database facilities required by users. Following the endorsement of the resulting specification and a detailed design study, the database facilities have been implemented as an integral part of the CUTLASS system. This paper provides an introduction to the range of CUTLASS Database facilities, and emphasises the role of Database as the central facility around which future Kit 1 and (particularly) Kit 6 CUTLASS based data processing and control systems will be designed and implemented. (author)

  2. Advanced reactor experimental facilities

    International Nuclear Information System (INIS)

    For many years, the NEA has been examining advanced reactor issues and disseminating information of use to regulators, designers and researchers on safety issues and research needed. Following the recommendation of participants at an NEA workshop, a Task Group on Advanced Reactor Experimental Facilities (TAREF) was initiated with the aim of providing an overview of facilities suitable for carrying out the safety research considered necessary for gas-cooled reactors (GCRs) and sodium fast reactors (SFRs), with other reactor systems possibly being considered in a subsequent phase. The TAREF was thus created in 2008 with the following participating countries: Canada, the Czech Republic, Finland, France, Germany, Hungary, Italy, Japan, Korea and the United States. In a second stage, India provided valuable information on its experimental facilities related to SFR safety research. The study method adopted entailed first identifying high-priority safety issues that require research and then categorizing the available facilities in terms of their ability to address the safety issues. For each of the technical areas, the task members agreed on a set of safety issues requiring research and established a ranking with regard to safety relevance (high, medium, low) and the status of knowledge based on the following scale relative to full knowledge: high (100%-75%), medium (75 - 25%) and low (25-0%). Only the issues identified as being of high safety relevance and for which the state of knowledge is low or medium were included in the discussion, as these issues would likely warrant further study. For each of the safety issues, the TAREF members identified appropriate facilities, providing relevant information such as operating conditions (in- or out-of reactor), operating range, description of the test section, type of testing, instrumentation, current status and availability, and uniqueness. Based on the information collected, the task members assessed prospects and priorities

  3. Decommissioning the UHTREX Reactor Facility at Los Alamos, New Mexico

    Energy Technology Data Exchange (ETDEWEB)

    Salazar, M.; Elder, J.

    1992-08-01

    The Ultra-High Temperature Reactor Experiment (UHTREX) facility was constructed in the late 1960s to advance high-temperature and gas-cooled reactor technology. The 3-MW reactor was graphite moderated and helium cooled and used 93% enriched uranium as its fuel. The reactor was run for approximately one year and was shut down in February 1970. The decommissioning of the facility involved removing the reactor and its associated components. This document details planning for the decommissioning operations which included characterizing the facility, estimating the costs of decommissioning, preparing environmental documentation, establishing a system to track costs and work progress, and preplanning to correct health and safety concerns in the facility. Work to decommission the facility began in 1988 and was completed in September 1990 at a cost of $2.9 million. The facility was released to Department of Energy for other uses in its Los Alamos program.

  4. Design philosophy of the Jet Propulsion Laboratory infrared detector test facility

    Science.gov (United States)

    Burns, R.; Blessinger, M. A.

    1983-01-01

    To support the development of advanced infrared remote sensing instrumentation using line and area arrays, a test facility has been developed to characterize the detectors. The necessary performance characteristics of the facility were defined by considering current and projected requirements for detector testing. The completed facility provides the desired level of detector testing capability as well as providing ease of human interaction.

  5. Examining the Association between Hazardous Waste Facilities and Rural "Brain Drain"

    Science.gov (United States)

    Hunter, Lori M.; Sutton, Jeannette

    2004-01-01

    Rural communities are increasingly being faced with the prospect of accepting facilities characterized as "opportunity-threat," such as facilities that generate, treat, store, or otherwise dispose of hazardous wastes. Such facilities may offer economic gains through jobs and tax revenue, although they may also act as environmental "disamenities."…

  6. Comprehensive facilities plan

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-09-01

    The Ernest Orlando Lawrence Berkeley National Laboratory`s Comprehensive Facilities Plan (CFP) document provides analysis and policy guidance for the effective use and orderly future development of land and capital assets at the Berkeley Lab site. The CFP directly supports Berkeley Lab`s role as a multiprogram national laboratory operated by the University of California (UC) for the Department of Energy (DOE). The CFP is revised annually on Berkeley Lab`s Facilities Planning Website. Major revisions are consistent with DOE policy and review guidance. Facilities planing is motivated by the need to develop facilities for DOE programmatic needs; to maintain, replace and rehabilitate existing obsolete facilities; to identify sites for anticipated programmatic growth; and to establish a planning framework in recognition of site amenities and the surrounding community. The CFP presents a concise expression of the policy for the future physical development of the Laboratory, based upon anticipated operational needs of research programs and the environmental setting. It is a product of the ongoing planning processes and is a dynamic information source.

  7. Power Systems Development Facility

    International Nuclear Information System (INIS)

    The objective of the PSDF would be to provide a modular facility which would support the development of advanced, pilot-scale, coal-based power systems and hot gas clean-up components. These pilot-scale components would be designed to be large enough so that the results can be related and projected to commercial systems. The facility would use a modular approach to enhance the flexibility and capability for testing; consequently, overall capital and operating costs when compared with stand-alone facilities would be reduced by sharing resources common to different modules. The facility would identify and resolve technical barrier, as well as-provide a structure for long-term testing and performance assessment. It is also intended that the facility would evaluate the operational and performance characteristics of the advanced power systems with both bituminous and subbituminous coals. Five technology-based experimental modules are proposed for the PSDF: (1) an advanced gasifier module, (2) a fuel cell test module, (3) a PFBC module, (4) a combustion gas turbine module, and (5) a module comprised of five hot gas cleanup particulate control devices. The final module, the PCD, would capture coal-derived ash and particles from both the PFBC and advanced gasifier gas streams to provide for overall particulate emission control, as well as to protect the combustion turbine and the fuel cell

  8. Fifty cell test facility

    Energy Technology Data Exchange (ETDEWEB)

    Arntzen, J. D.; Kolba, V. M.; Miller, W. E.; Gay, E. C.

    1980-07-01

    This report describes the design of a facility capable of the simultaneous testing of up to 50 high-temperature (400 to 500/sup 0/C) lithium alloy/iron sulfide cells; this facility is located in the Chemical Engineering Division of Argonne National Laboratory (ANL). The emphasis will be on the lifetime testing of cells fabricated by ANL and industrial contractors to acquire statistical data on the performance of cells of various designs. A computer-based data-acquisition system processes the cell performance data generated from the cells on test. The terminals and part of the data-acquisition equipment are housed in an air-conditioned enclosure adjacent to the testing facility; the computer is located remotely.

  9. FACILITIES MANAGEMENT AT CERN

    CERN Multimedia

    2002-01-01

    Recently we have been confronted with difficulties concerning services which are part of a new contract for facilities management. Please see below for some information about this contract. Following competitive tendering and the Finance Committee decision, the contract was awarded to the Swiss firm 'Facilities Management Network (FMN)'. The owners of FMN are two companies 'M+W Zander' and 'Avireal', both very experienced in this field of facilities management. The contract entered into force on 1st July 2002. CERN has grouped together around 20 different activities into this one contract, which was previously covered by separate contracts. The new contract includes the management and execution of many activities, in particular: Guards and access control; cleaning; operation and maintenance of heating plants, cooling and ventilation equipment for buildings not related to the tunnel or the LHC; plumbing; sanitation; lifts; green areas and roads; waste disposal; and includes a centralised helpdesk for these act...

  10. Mirror Fusion Test Facility

    International Nuclear Information System (INIS)

    On October 1, 1977 work began at LLL on the Mirror Fusion Test Facility (MFTF), an advanced experimental fusion device. Scheduled for operation in late 1981, MFTF is designed as an intermediate step between present mirror machines, such as 2XIIB, and an experimental fusion reactor. This design incorporates improved technology and a better theoretical understanding of how neutral beam injection, plasma guns, and gas injection into the plasma region compensate for cooling and particle losses. With the new facility, we expect to achieve a confinement factor (n tau) of 1012 particles . sm/cm3--a tenfold increase over 2XIIB n tau values--and to increase plasma temperature to over 500 million K. The following article describes this new facility and reports on progress in some of the R and D projects that are providing the technological base for its construction

  11. INTEGRATION OF FACILITY MODELING CAPABILITIES FOR NUCLEAR NONPROLIFERATION ANALYSIS

    Energy Technology Data Exchange (ETDEWEB)

    Gorensek, M.; Hamm, L.; Garcia, H.; Burr, T.; Coles, G.; Edmunds, T.; Garrett, A.; Krebs, J.; Kress, R.; Lamberti, V.; Schoenwald, D.; Tzanos, C.; Ward, R.

    2011-07-18

    Developing automated methods for data collection and analysis that can facilitate nuclear nonproliferation assessment is an important research area with significant consequences for the effective global deployment of nuclear energy. Facility modeling that can integrate and interpret observations collected from monitored facilities in order to ascertain their functional details will be a critical element of these methods. Although improvements are continually sought, existing facility modeling tools can characterize all aspects of reactor operations and the majority of nuclear fuel cycle processing steps, and include algorithms for data processing and interpretation. Assessing nonproliferation status is challenging because observations can come from many sources, including local and remote sensors that monitor facility operations, as well as open sources that provide specific business information about the monitored facilities, and can be of many different types. Although many current facility models are capable of analyzing large amounts of information, they have not been integrated in an analyst-friendly manner. This paper addresses some of these facility modeling capabilities and illustrates how they could be integrated and utilized for nonproliferation analysis. The inverse problem of inferring facility conditions based on collected observations is described, along with a proposed architecture and computer framework for utilizing facility modeling tools. After considering a representative sampling of key facility modeling capabilities, the proposed integration framework is illustrated with several examples.

  12. Interface control document between Analytical Services and Solid Waste Disposal Division

    International Nuclear Information System (INIS)

    This interface control document (ICD) between Analytical Services and Solid Waste Disposal (SWD) establishes a baseline description of the support needed and the wastes that will require management as part of the interface between the two divisions. It is important that each division has a clear understanding of the other division's expectations regarding levels and type of support needed. This ICD deals with the waste sampling support needed by SWD and the waste generated by the specified analytical laboratories. The baseline description of wastes includes waste volumes, characteristics and shipping schedules, which will be used to plan the proper support requirements. The laboratories included in this document are 222-S Laboratory Facility, the Waste Sampling and Characterization Facility (WSCF) and the Chemical Engineering Laboratory. These three facilities provide support to the entire site and are not associated with one major program/facility. The laboratories associated with major facilities or programs such as Engineering/Environmental Development Laboratory at K Basins Operation are not within the scope of this document

  13. Quadrant I RCRA Facility Investigation Work Plan

    International Nuclear Information System (INIS)

    The objective of this Facility Investigation (FRI) at the Portsmouth Gaseous Diffusion Plant (PORTS) is to acquire, analyze and interpret data which will: (1) characterize the environmental setting including ground water, surface water and sediment, soil and air; (2) define and characterize sources of contamination; (3) characterize the vertical and horizontal extent and degree of contamination of the environment; (4) assess the risk to human health and the environment resulting from possible exposure to contaminants; and, (5) support the Corrective Measures Study (CMS) which will follow the RFI. Investigations to characterize the environmental setting, sources of contamination, and vertical and horizontal extent and degree of contamination will be conducted relative to individual potential sources which have been identified in the Quadrant I Description of Current Conditions. These unit investigations will follow the systematic approach which is outlined below

  14. Decommissioning plan depleted uranium manufacturing facility

    International Nuclear Information System (INIS)

    Aerojet Ordnance Tennessee, Inc. (Aerojet) is decommissioning its California depleted uranium (DU) manufacturing facility. Aerojet has conducted manufacturing and research and development activities at the facility since 1977 under a State of California Source Materials License. The decontamination is being performed by a contractor selector for technical competence through competitive bid. Since the facility will be released for uncontrolled use it will be decontaminated to levels as low as reasonably achievable (ALARA). In order to fully apply the principles of ALARA, and ensure the decontamination is in full compliance with appropriate guides, Aerojet has retained Rogers and Associaties Engineering Corporation (RAE) to assist in the decommissioning. RAE has assisted in characterizing the facility and preparing contract bid documents and technical specifications to obtain a qualified decontamination contractor. RAE will monitor the decontamination work effort to assure the contractor's performance complies with the contract specifications and the decontamination plan. The specifications require a thorough cleaning and decontamination of the facility, not just sufficient cleaning to meet the numeric cleanup criteria

  15. Biotechnology core facilities: trends and update.

    Science.gov (United States)

    Ivanetich, K M; Niece, R L; Rohde, M; Fowler, E; Hayes, T K

    1993-09-01

    A survey of 128 biotechnology core facilities has provided data on the finances, services, space requirements, and personnel. An average facility had four full-time personnel and 7.5 major instrument systems, and occupied 969 sq. ft. Average total income was $244,000/year, but annual user fee income was only $125,000. Typically, facilities required substantial institutional support or grants. Cost recovery (user fee income divided by total income) averaged 49%. During the last 5 years user fee income, total income, and cost recovery have increased. In-house charges for protein sequencing and peptide synthesis increased approximately 30%, while oligonucleotide synthesis charges decreased by 74%. The costs (charges corrected for subsidy from non-user fee income) for most services did not significantly change, except that oligonucleotide synthesis costs decreased by 25% in 1992. DNA synthesis had the highest throughout per month (116 samples), followed by amino acid analysis (86 samples) and DNA sequencing (67 samples). Other services averaged from 5 to 60 samples. DNA synthesis and purification were the services used by the greatest number of principal investigators. A number of services including DNA sequencing, mass spectrometry, capillary electrophoresis, RNA synthesis, electroblotting, and carbohydrate analysis have been introduced in the last 3 years. Although these services are characterized by high levels of methods development and non-user runs, they are offered by twice the percentage of facilities as in 1989, and are increasingly contributing to facility income. PMID:8375609

  16. Line facilities outline

    International Nuclear Information System (INIS)

    This book deals with line facilities. The contents of this book are outline line of wire telecommunication ; development of line, classification of section of line and theory of transmission of line, cable line ; structure of line, line of cable in town, line out of town, domestic cable and other lines, Optical communication ; line of optical cable, transmission method, measurement of optical communication and cable of the sea bottom, Equipment of telecommunication line ; telecommunication line facilities and telecommunication of public works, construction of cable line and maintenance and Regulation of line equipment ; regulation on technique, construction and maintenance.

  17. Bevalac Radiotherapy Facility

    International Nuclear Information System (INIS)

    Patient Treatment Room at the Bevalac is now in full operation. In the design of this facility, emphasis has been placed on creating an atmosphere appropriate to a clinical facility; the usual features of an irradiation cave have been hidden behind carpets, curtains and paint. Patient positioning is done with a Philips Ram-style couch, with additional fixtures to accommodate a patient in the seated or standing, as well as the supine, position. Dosimetry apparatus, collimators, ion chambers and the beam flattening system used to produce the highly uniform 20 cm diameter therapy field are described

  18. Physical protection of nuclear facilities. Quarterly progress report, January--March 1977

    Energy Technology Data Exchange (ETDEWEB)

    Chapman, L.D. (ed.)

    1977-07-01

    The physical protection of nuclear facilities program consists of four major areas--evaluation methodology development, path generation/selection methodology, facility characterization, and component functional performance characterization. Activities in each of these areas for the second quarter of FY 77 are summarized.

  19. Facility effluent monitoring

    Energy Technology Data Exchange (ETDEWEB)

    Gleckler, B.P.

    1995-06-01

    This section of the 1994 Hanford Site Environmental Report summarizes the facility effluent monitoring programs and provides an evaluation of effluent monitoring data. These evaluations are useful in assessing the effectiveness of effluent treatment and control systems, as well as management practices.

  20. Decommissioning of Nuclear Facilities

    International Nuclear Information System (INIS)

    Atomic Energy Regulatory Board (AERB) is of the view that every organisation should focus attention on the decommissioning of nuclear facilities after completion of their useful life. AERB is aware that, internationally there is a growing interest in plant life extension due to economic considerations. Regulatory bodies stipulate upgradation of safety features based on international experience and current safety standards. However, decommissioning becomes a necessity at some time after the extended life of the plant. Nuclear industry has demonstrated that, with modern technological developments, decommissioning of nuclear facilities can be carried out without undue risk to the occupational workers, members of the public and protection of the environment. In view of limited experience in the field of decommissioning, this document is being issued as a safety manual instead of a safety guide. This manual elaborates the various technical and safety considerations in the decommissioning of nuclear facilities including ultimate disposal of radioactive materials/ wastes generated during decommissioning. Details that are required to be furnished to the regulatory body while applying for authorisation for decommissioning and till its completion are enumerated. This manual is issued to assist Department of Atomic Energy (DAE) units in formulating a decommissioning programme. Since the subject of decommissioning of nuclear facilities is a continuously evolving process, AERB is of the view, that provisions of this manual will apply for a period of five years from the date of issue and will be subsequently revised, if necessary

  1. Dismantling of nuclear facilities

    International Nuclear Information System (INIS)

    Nuclear facilities have a long estimable lifetime but necessarily limited in time. At the end of their operation period, basic nuclear installations are the object of cleansing operations and transformations that will lead to their definitive decommissioning and then to their dismantling. Because each facility is somewhere unique, cleansing and dismantling require specific techniques. The dismantlement consists in the disassembly and disposing off of big equipments, in the elimination of radioactivity in all rooms of the facility, in the demolition of buildings and eventually in the reconversion of all or part of the facility. This article describes these different steps: 1 - dismantling strategy: main de-construction guidelines, expected final state; 2 - industries and sites: cleansing and dismantling at the CEA, EDF's sites under de-construction; 3 - de-construction: main steps, definitive shutdown, preparation of dismantling, electromechanical dismantling, cleansing/decommissioning, demolition, dismantling taken into account at the design stage, management of polluted soils; 4 - waste management: dismantlement wastes, national policy of radioactive waste management, management of dismantlement wastes; 5 - mastery of risks: risk analysis, conformability of risk management with reference documents, main risks encountered at de-construction works; 6 - regulatory procedures; 7 - international overview; 8 - conclusion. (J.S.)

  2. Facility Modernization Report

    Energy Technology Data Exchange (ETDEWEB)

    Robinson, D; Ackley, R

    2007-05-10

    Modern and technologically up-to-date facilities and systems infrastructure are necessary to accommodate today's research environment. In response, Lawrence Livermore National Laboratory (LLNL) has a continuing commitment to develop and apply effective management models and processes to maintain, modernize, and upgrade its facilities to meet the science and technology mission. The Facility Modernization Pilot Study identifies major subsystems of facilities that are either technically or functionally obsolete, lack adequate capacity and/or capability, or need to be modernized or upgraded to sustain current operations and program mission. This study highlights areas that need improvement, system interdependencies, and how these systems/subsystems operate and function as a total productive unit. Although buildings are 'grandfathered' in and are not required to meet current codes unless there are major upgrades, this study also evaluates compliance with 'current' building, electrical, and other codes. This study also provides an evaluation of the condition and overall general appearance of the structure.

  3. TNO HVAC facilities

    NARCIS (Netherlands)

    Hammink, H.A.J.

    2015-01-01

    TNO has extensive knowledge of heating, ventilation and air conditioning (HVAC), and can offer its services through theoretical studies, laboratory experiments and field measurements. This complete scope, made possible through our test facilities, enables the effective development of new products, i

  4. Facilities of Environmental Distinction

    Science.gov (United States)

    Pascopella, Angela

    2011-01-01

    Three of nine school buildings that have won the latest Educational Facility Design Awards from the American Institute of Architects (AIA) Committee on Architecture for Education stand out from the crowd of other school buildings because they are sustainable and are connected to the nature that surrounds them. They are: (1) Thurston Elementary…

  5. Multipurpose dry storage facilities

    International Nuclear Information System (INIS)

    SGN has gained considerable experience in the design and construction of interim storage facilities for spent fuel and various nuclear waste, and can therefore propose single product and multiproduct facilities capable of accommodating all types of waste in a single structure. The pooling of certain functions (transport cask reception, radiation protection), the choice of optimized technologies to meet the specific needs of the clients (automatic transfer by shielded cask or nuclearized crane) and the use of the same type of well to cool the heat releasing packages (glass canisters, fuel elements) make it possible to propose industrially proven and cost effective solutions. The studies conducted by SGN on behalf of the Dutch company COVRA (Centrale Organisatie Voor Radioactif Afval), offer an example of the application of this new concept. This paper first presents the SGN experience through a short description of reference storage facilities for various types of products (MLW, HLW and Spent Fuel). It goes on with a typical application to show how these proven technologies are combined to obtain single product or multiproduct facilities tailored to the client's specific requirements. (author)

  6. Basic nuclear facilities

    International Nuclear Information System (INIS)

    This document reprints the text of the French by-law from February 21, 2002 relative to the information of populations living in the vicinity of a facility for which a particular emergency plan exists. The by-law precises the content of the information documents intended for the populations living in the area of application of the plan. (J.S.)

  7. Track and Field Facilities.

    Science.gov (United States)

    Wood, Tony

    2001-01-01

    Discusses planning and design tips that help ensure track and field facilities are successful and well-suited to both school and community use. Examines approaches to determining the best track surface and ways to maximize track and field flexibility with limited space. (GR)

  8. Toroid magnet test facility

    CERN Multimedia

    2002-01-01

    Because of its exceptional size, it was not feasible to assemble and test the Barrel Toroid - made of eight coils - as an integrated toroid on the surface, prior to its final installation underground in LHC interaction point 1. It was therefore decided to test these eight coils individually in a dedicated test facility.

  9. Requirements and design concept for a facility mapping system

    International Nuclear Information System (INIS)

    The Department of Energy (DOE) has for some time been considering the Decontamination and Dismantlement (D ampersand D) of facilities which are no longer in use, but which are highly contaminated with radioactive wastes. One of the holdups in performing the D ampersand D task is the accumulation of accurate facility characterizations that can enable a safe and orderly cleanup process. According to the Technical Strategic Plan for the Decontamination and Decommissioning Integrated Demonstration, open-quotes the cost of characterization using current baseline technologies for approximately 100 acres of gaseous diffusion plant at Oak Ridge alone is, for the most part incalculableclose quotes. Automated, robotic techniques will be necessary for initial characterization and continued surveillance of these types of sites. Robotic systems are being designed and constructed to accomplish these tasks. This paper describes requirements and design concepts for a system to accurately map a facility contaminated with hazardous wastes. Some of the technologies involved in the Facility Mapping System are: remote characterization with teleoperated, sensor-based systems, fusion of data sets from multiple characterization systems, and object recognition from 3D data models. This Facility Mapping System is being assembled by Oak Ridge National Laboratory for the DOE Office of Technology Development Robotics Technology Development Program

  10. Assisted Living Facilities, care facilities, Published in 2006, Washoe County.

    Data.gov (United States)

    NSGIC GIS Inventory (aka Ramona) — This Assisted Living Facilities dataset, was produced all or in part from Published Reports/Deeds information as of 2006. It is described as 'care facilities'. Data...

  11. EPA Facility Registry Service (FRS): Facility Interests Dataset - Intranet Download

    Data.gov (United States)

    U.S. Environmental Protection Agency — This downloadable data package consists of location and facility identification information from EPA's Facility Registry Service (FRS) for all sites that are...

  12. EPA Facility Registry Service (FRS): Facility Interests Dataset - Intranet

    Data.gov (United States)

    U.S. Environmental Protection Agency — This web feature service consists of location and facility identification information from EPA's Facility Registry Service (FRS) for all sites that are available in...

  13. EPA Facility Registry Service (FRS): Facility Interests Dataset Download

    Data.gov (United States)

    U.S. Environmental Protection Agency — This downloadable data package consists of location and facility identification information from EPA's Facility Registry Service (FRS) for all sites that are...

  14. EPA Facility Registry Service (FRS): Facility Interests Dataset

    Data.gov (United States)

    U.S. Environmental Protection Agency — This web feature service consists of location and facility identification information from EPA's Facility Registry Service (FRS) for all sites that are available in...

  15. EPA Facility Registry Service (FRS): AIRS_AFS Sub Facilities

    Data.gov (United States)

    U.S. Environmental Protection Agency — The Air Facility System (AFS) contains compliance and permit data for stationary sources regulated by EPA, state and local air pollution agencies. The sub facility...

  16. Site characterization handbook

    Energy Technology Data Exchange (ETDEWEB)

    1988-06-01

    This Handbook discusses both management and technical elements that should be considered in developing a comprehensive site characterization program. Management elements typical of any project of a comparable magnitude and complexity are combined with a discussion of strategies specific to site characterization. Information specific to the technical elements involved in site characterization is based on guidance published by the Nuclear Regulatory Commission (NRC) with respect to licensing requirements for LLW disposal facilities. The objective of this Handbook is to provide a reference for both NRC Agreement States and non-Agreement States for use in developing a comprehensive site characterization program that meets the specific objectives of the State and/or site developer/licensee. Each site characterization program will vary depending on the objectives, licensing requirements, schedules/budgets, physical characteristics of the site, proposed facility design, and the specific concerns raised by government agencies and the public. Therefore, the Handbook is not a prescriptive guide to site characterization. 18 refs., 6 figs.

  17. Space station furnace facility

    Science.gov (United States)

    Cobb, Sharon D.; Lehoczky, Sandor L.

    1996-07-01

    The Space Shuttle Furnace Facility (SSFF) is the modular, multi-user scientific instrumentation for conducting materials research in the reduced gravity environment of the International Space Station. The facility is divided into the Core System and two Instrument Racks. The core system provides the common electrical and mechanical support equipment required to operate experiment modules (EMs). The EMs are investigator unique furnaces or apparatus designed to accomplish specific science investigations. Investigations are peer selected every two years from proposals submitted in response to National Aeronautics and Space Administration Research Announcements. The SSFF Core systems are designed to accommodate an envelope of eight types of experiment modules. The first two modules to be developed for the first instrument rack include a high temperature gradient furnace with quench, and a low temperature gradient furnace. A new EM is planned to be developed every two years.

  18. Universal Test Facility

    Science.gov (United States)

    Laughery, Mike

    A universal test facility (UTF) for Space Station Freedom is developed. In this context, universal means that the experimental rack design must be: automated, highly marketable, and able to perform diverse microgravity experiments according to NASA space station requirements. In order to fulfill these broad objectives, the facility's customers, and their respective requirements, are first defined. From these definitions, specific design goals and the scope of the first phase of this project are determined. An examination is first made into what types of research are most likely to make the UTF marketable. Based on our findings, the experiments for which the UTF would most likely be used included: protein crystal growth, hydroponics food growth, gas combustion, gallium arsenide crystal growth, microorganism development, and cell encapsulation. Therefore, the UTF is designed to fulfill all of the major requirements for the experiments listed above. The versatility of the design is achieved by taking advantage of the many overlapping requirements presented by these experiments.

  19. World Class Facilities Management

    DEFF Research Database (Denmark)

    Malmstrøm, Ole Emil; Jensen, Per Anker

    2013-01-01

    Alle der med entusiasme arbejder med Facilities Management drømmer om at levere World Class. DFM drømmer om at skabe rammer og baggrund for, at vi i Danmark kan bryste os at være blandt de førende på verdensplan. Her samles op på, hvor tæt vi er på at nå drømmemålet.......Alle der med entusiasme arbejder med Facilities Management drømmer om at levere World Class. DFM drømmer om at skabe rammer og baggrund for, at vi i Danmark kan bryste os at være blandt de førende på verdensplan. Her samles op på, hvor tæt vi er på at nå drømmemålet....

  20. Facilities evaluation report

    International Nuclear Information System (INIS)

    The Buried Waste Integrated Demonstration (BWID) is a program of the Department of Energy (DOE) Office of Technology Development whose mission is to evaluate different new and existing technologies and determine how well they address DOE community waste remediation problems. Twenty-three Technical Task Plans (TTPs) have been identified to support this mission during FY-92; 10 of these have identified some support requirements when demonstrations take place. Section 1 of this report describes the tasks supported by BWID, determines if a technical demonstration is proposed, and if so, identifies the support requirements requested by the TTP Principal Investigators. Section 2 of this report is an evaluation identifying facility characteristics of existing Idaho National Engineering Laboratory (INEL) facilities that may be considered for use in BWID technology demonstration activities

  1. The VAO Transient Facility

    CERN Document Server

    Graham, Matthew J; Drake, Andrew; Mahabal, Ashish; Williams, Roy; Seaman, Rob

    2011-01-01

    The time domain community wants robust and reliable tools to enable production of and subscription to community-endorsed event notification packets (VOEvent). The VAO Transient Facility (VTF) is being designed to be the premier brokering service for the community, both collecting and disseminating observations about time-critical astronomical transients but also supporting annotations and the application of intelligent machine-learning to those observations. This distinguishes two types of activity associated with the facility: core infrastructure and user services. In this paper, we will review the prior art in both areas and describe the planned capabilities of the VTF. In particular, we will focus on scalability and quality-of-service issues required by the next generation of sky surveys, such as LSST and SKA.

  2. Radioactive contamination at nuclear fuel cycle facilities. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Bernhardt, D.E.; Grant, M.W.; Rich, D.C.; Jensen, C.M.; Macbeth, P.J.

    1982-01-01

    This report presents information to characterize uranium fuel cycle facilities (excluding reactors), levels of contamination at those facilities, and volumes and activity of wastes associated with their decontamination and decommissioning (DandD). It is one of a series of reports providing information to assist the U.S. Environmental Protection Agency in setting standards and guidelines for permissible residual levels of radioactivity from DandD. The categories of facilities covered by this report are: Uranium mines, Uranium mills, Uranium hexafluoride conversion plants, Fuel fabrication plants, including both low and high enriched uranium and mixed oxide facilities. Both active and inactive facilities are identified. The highest volumes of DandD waste (hundreds of millions of cubic meters) are associated with uranium mines, while the highest amounts of radioactivity are a result of DandD at fuel reprocessing plants.

  3. Examining the amenability of urban street networks for locating facilities

    Science.gov (United States)

    Zhang, Tong; Zeng, Zhe; Jia, Tao; Li, Jing

    2016-09-01

    This paper aims to characterize urban street networks from the perspective of facility location that is widely used for siting public or private services. Both topological and geometrical features of urban street networks are investigated to examine their impacts on the performance of facility location. We propose a set of efficiency and centrality measures to evaluate the amenability of street networks for locating facilities. The evaluation of 15 large cities in the U.S. reveals that facility locations are strongly affected by road network structures. For realistic street networks, grid planned road network are more amenable to locating facilities than irregular networks. The analyses on idealized network offer further evidence of the correlations between network properties and service provision efficiencies.

  4. Microgravity Simulation Facility (MSF)

    Science.gov (United States)

    Richards, Stephanie E. (Compiler); Levine, Howard G.; Zhang, Ye

    2016-01-01

    The Microgravity Simulator Facility (MSF) at Kennedy Space Center (KSC) was established to support visiting scientists for short duration studies utilizing a variety of microgravity simulator devices that negate the directional influence of the "g" vector (providing simulated conditions of micro or partial gravity). KSC gravity simulators can be accommodated within controlled environment chambers allowing investigators to customize and monitor environmental conditions such as temperature, humidity, CO2, and light exposure.

  5. Japan hadron facility

    Energy Technology Data Exchange (ETDEWEB)

    Shibata, Tokushi [High Energy Accelerator Research Organization, Tsukuba, Ibaraki (Japan)

    1998-03-01

    JHF aims at promoting the variety of research fields using various secondary beams produced by high-intensity proton beams. The accelerator of JHF will be an accelerator complex of a 200 MeV LINAC, a 3 GeV booster proton synchrotron, and a 50 GeV proton synchrotron. The four main experimental facilities of K-Arena, M-Arena, N-Arena, and E-Arena are planed. The outline of the project is presented. (author)

  6. Proton beam therapy facility

    Energy Technology Data Exchange (ETDEWEB)

    1984-10-09

    It is proposed to build a regional outpatient medical clinic at the Fermi National Accelerator Laboratory (Fermilab), Batavia, Illinois, to exploit the unique therapeutic characteristics of high energy proton beams. The Fermilab location for a proton therapy facility (PTF) is being chosen for reasons ranging from lower total construction and operating costs and the availability of sophisticated technical support to a location with good access to patients from the Chicago area and from the entire nation. 9 refs., 4 figs., 26 tabs.

  7. Disaster Prevention Sector Facility

    OpenAIRE

    Inter-American Development Bank (IDB)

    2001-01-01

    This document (GN-2085-5) was favorably considered by the Bank's Board of Directors on March 12, 2001. The Sector Facility, in particular, will assist countries to take an integrated approach to reducing and managing their risk to natural hazards before a disastrous event through the following components: (1) Risk identification and forecasting to understand and quantify vulnerability and disaster risk; (2) mitigation to address the structural sources of vulnerability; and (3) preparedness to...

  8. ORNL calibrations facility

    International Nuclear Information System (INIS)

    The ORNL Calibrations Facility is operated by the Instrumentation Group of the Industrial Safety and Applied Health Physics Division. Its primary purpose is to maintain radiation calibration standards for calibration of ORNL health physics instruments and personnel dosimeters. This report includes a discussion of the radioactive sources and ancillary equipment in use and a step-by-step procedure for calibration of those survey instruments and personnel dosimeters in routine use at ORNL

  9. Facility decontamination technology workshop

    Energy Technology Data Exchange (ETDEWEB)

    None

    1980-10-01

    Purpose of the meeting was to provide a record of experience at nuclear facilities, other than TMI-2, of events and incidents which have required decontamination and dose reduction activities, and to furnish GPU and others involved in the TMI-2 cleanup with the results of that decontamination and dose reduction technology. Separate abstracts were prepared for 24 of the 25 papers; the remaining paper had been previously abstracted. (DLC)

  10. Beryllium facilities in India

    International Nuclear Information System (INIS)

    Due to its unique combination of physical, mechanical, thermal and nuclear properties, beryllium is indispensable for many applications in the fields of nuclear and space sciences. Beryllia and copper beryllium alloys have also found extensive applications in the electrical and electronic industries. Beryllium facilities at Bhabha Atomic Research Centre (BARC) have been set up to meet indigenous requirements for these materials. Besides developing beryllium technology, the project team has also designed and developed a number of special purpose equipment. (Author)

  11. The National Ignition Facility

    Energy Technology Data Exchange (ETDEWEB)

    Miller, G H; Moses, E I; Wuest, C R

    2004-06-03

    The National Ignition Facility (NIF) at Lawrence Livermore National Laboratory is a stadium-sized facility that, when completed in 2008, will contain a 192-beam, 1.8- Megajoule, 500-Terawatt, ultraviolet laser system together with a 10-meter-diameter target chamber and room for 100 diagnostics. NIF is the world's largest and most energetic laser experimental system and will provide a scientific center to study inertial confinement fusion and matter at extreme energy densities and pressures. NIF's energetic laser beams will compress fusion targets to conditions required for thermonuclear burn, liberating more energy than required to initiate the fusion reactions. Other NIF experiments will study physical processes at temperatures approaching 10{sup 8} K and 10{sup 11} bar; conditions that exist naturally only in the interior of stars and planets. NIF has completed the first phases of its laser commissioning program. The first four beams of NIF have generated 106 kilojoules in 23-ns pulses of infrared light and over 16 kJ in 3.5- ns pulses at the third harmonic (351 nm). NIF's target experimental systems are being commissioned and experiments have begun. This paper provides a detailed look the NIF laser systems, laser and optical performance, and results from recent laser commissioning shots. We follow this with a discussion of NIF's high-energy-density and inertial fusion experimental capabilities, the first experiments on NIF, and plans for future capabilities of this unique facility.

  12. ATLAS Facility Description Report

    International Nuclear Information System (INIS)

    A thermal-hydraulic integral effect test facility, ATLAS (Advanced Thermal-hydraulic Test Loop for Accident Simulation), has been constructed at KAERI (Korea Atomic Energy Research Institute). The ATLAS has the same two-loop features as the APR1400 and is designed according to the well-known scaling method suggested by Ishii and Kataoka to simulate the various test scenarios as realistically as possible. It is a half-height and 1/288-volume scaled test facility with respect to the APR1400. The fluid system of the ATLAS consists of a primary system, a secondary system, a safety injection system, a break simulating system, a containment simulating system, and auxiliary systems. The primary system includes a reactor vessel, two hot legs, four cold legs, a pressurizer, four reactor coolant pumps, and two steam generators. The secondary system of the ATLAS is simplified to be of a circulating loop-type. Most of the safety injection features of the APR1400 and the OPR1000 are incorporated into the safety injection system of the ATLAS. In the ATLAS test facility, about 1300 instrumentations are installed to precisely investigate the thermal-hydraulic behavior in simulation of the various test scenarios. This report describes the scaling methodology, the geometric data of the individual component, and the specification and the location of the instrumentations in detail

  13. Medical Image Analysis Facility

    Science.gov (United States)

    1978-01-01

    To improve the quality of photos sent to Earth by unmanned spacecraft. NASA's Jet Propulsion Laboratory (JPL) developed a computerized image enhancement process that brings out detail not visible in the basic photo. JPL is now applying this technology to biomedical research in its Medical lrnage Analysis Facility, which employs computer enhancement techniques to analyze x-ray films of internal organs, such as the heart and lung. A major objective is study of the effects of I stress on persons with heart disease. In animal tests, computerized image processing is being used to study coronary artery lesions and the degree to which they reduce arterial blood flow when stress is applied. The photos illustrate the enhancement process. The upper picture is an x-ray photo in which the artery (dotted line) is barely discernible; in the post-enhancement photo at right, the whole artery and the lesions along its wall are clearly visible. The Medical lrnage Analysis Facility offers a faster means of studying the effects of complex coronary lesions in humans, and the research now being conducted on animals is expected to have important application to diagnosis and treatment of human coronary disease. Other uses of the facility's image processing capability include analysis of muscle biopsy and pap smear specimens, and study of the microscopic structure of fibroprotein in the human lung. Working with JPL on experiments are NASA's Ames Research Center, the University of Southern California School of Medicine, and Rancho Los Amigos Hospital, Downey, California.

  14. The National Ignition Facility

    Energy Technology Data Exchange (ETDEWEB)

    Miller, G H; Moses, E I; Wuest, C R

    2004-02-06

    The National Ignition Facility (NIF) at Lawrence Livermore National Laboratory is a stadium-sized facility containing a 192-beam, 1.8-Megajoule, 500-Terawatt, ultraviolet laser system together with a 10-meter-diameter target chamber and room for 100 diagnostics. NIF is the world's largest and most energetic laser experimental system, providing a scientific center to study inertial confinement fusion and matter at extreme energy densities and pressures. NIF's energetic laser beams will compress fusion targets to conditions required for thermonuclear burn, liberating more energy than required to initiate the fusion reactions. Other NIF experiments will study physical processes at temperatures approaching 10{sup 8} K and 10{sup 11} bar; conditions that exist naturally only in the interior of stars and planets. NIF has completed the first phases of its laser commissioning program. The first four beams of NIF have generated 106 kilojoules in 23-ns pulses of infrared light and over 16 kJ in 3.5-ns pulses at the third harmonic (351 nm). NIF's target experimental systems are being commissioned and experiments have begun. This paper provides a detailed look the NIF laser systems, laser and optical performance, and results from recent laser commissioning shots. We follow this with a discussion of NIF's high-energy-density and inertial fusion experimental capabilities, the first experiments on NIF, and plans for future capabilities of this unique facility.

  15. Nitramine Drying & Fine Grinding Facility

    Data.gov (United States)

    Federal Laboratory Consortium — The Nitramine Drying and Fine Grinding Facility provides TACOM-ARDEC with a state-of-the-art facility capable of drying and grinding high explosives (e.g., RDX and...

  16. Carbon Fiber Technology Facility (CFTF)

    Data.gov (United States)

    Federal Laboratory Consortium — Functionally within the MDF, ORNL operates DOE’s unique Carbon Fiber Technology Facility (CFTF)—a 42,000 ft2 innovative technology facility and works with leading...

  17. Environmentally Regulated Facilities in Iowa

    Data.gov (United States)

    Iowa State University GIS Support and Research Facility — A unique record for each facility site with an environmental interest by DNR (such as permits). This brings together core environmental information in one place for...

  18. Shock Thermodynamic Applied Research Facility

    Data.gov (United States)

    Federal Laboratory Consortium — The Shock Thermodynamic Applied Research Facility (STAR) facility, within Sandia’s Solid Dynamic Physics Department, is one of a few institutions in the world with...

  19. Air Facility System (AFS) Widget

    Data.gov (United States)

    U.S. Environmental Protection Agency — The Air Facility System (AFS) widget allows users to enter a specific location and retrieve facilities in the area of interest for stationary sources of air...

  20. Emission Facilities - Air Emission Plants

    Data.gov (United States)

    NSGIC GIS Inventory (aka Ramona) — Represents the Primary Facility type Air Emission Plant (AEP) point features. Air Emissions Plant is a DEP primary facility type related to the Air Quality Program....

  1. Facile synthesis of new nano sorbent for magnetic solid-phase extraction by self assembling of bis-(2,4,4-trimethyl pentyl)-dithiophosphinic acid on Fe3O4-Ag core-shell nanoparticles: Characterization and application

    International Nuclear Information System (INIS)

    Graphical abstract: Self assembling of bis-(2,4,4-trimethylpentyl)-dithiophosphinic acid on Fe3O4-Ag core-shell nanoparticles and application of it for solid phase extraction of PAHs. Highlights: ► A novel sorbent for magnetic solid-phase extraction of PAHs was introduced. ► Silver was coated on Fe3O4 nanoparticles (MNPs) by reduction of AgNO3 with NaBH4. ► Bis-(2,4,4-trimethylpentyl)-dithiophosphinic acid self-assembled on silver coated MNPs. ► Size, morphology, composition and properties of the nanoparticles were characterized. ► Extraction efficiency of the sorbent was investigated by extraction of five PAHs. - Abstract: A novel sorbent for magnetic solid-phase extraction by self-assembling of organosulfur compound, (bis-(2,4,4-trimethylpentyl)-dithiophosphinic acid), onto the silver-coated Fe3O4 nanoparticles was introduced. Due to the formation of covalent bond of S-Ag, the new coating on the silver surface was very stable and showed high thermal stability (up to 320 °C). The size, morphology, composition, and properties of the prepared nanoparticles have also been characterized and determined using scanning electron microscopy (SEM), energy-dispersive X-ray analyzer (EDX), dynamic light scattering (DLS), Fourier transform-infrared (FT-IR) spectroscopy, and thermal gravimetric analysis (TGA). Extraction efficiency of the new sorbent was investigated by extraction of five polycyclic aromatic hydrocarbons (PAHs) as model compounds. The optimum extraction conditions for PAHs were obtained as of extraction time, 20 min; 50 mg sorbent from 100 mL of the sample solution, and elution with 100 μL of 1-propanol under fierce vortex for 2 min. Under the optimal conditions, the calibration curves were obtained in the range of 0.05–100 μg L−1 (R2 > 0.9980) and the LODs (S/N = 3) were obtained in the range of 0.02–0.10 μg L−1. Relative standard deviations (RSDs) for intra- and inter-day precision were 2.6–4.2% and 3.6–8.3%, respectively. In

  2. A central tower solar test facility /RM/CTSTF/

    Science.gov (United States)

    Bevilacqua, S.; Gislon, R.

    The considered facility is intended for the conduction of test work in connection with studies of receivers, thermodynamic cycles, heliostats, components, and subassemblies. Major components of the test facility include a mirror field with a reflecting surface of 800 sq m, a 40 m tower, an electronic control system, a data-acquisition system, and a meteorological station. A preliminary experimental program is discussed, taking into account investigations related to facility characterization, an evaluation of advanced low-cost heliostats, materials and components tests, high-concentration photovoltaic experiments, and a study of advanced solar thermal cycles.

  3. Indoor Lighting Facilities

    Science.gov (United States)

    Matsushima, Koji; Saito, Yoshinori; Ichikawa, Shigenori; Kawauchi, Takao; Tanaka, Tsuneo; Hirano, Rika; Tazuke, Fuyuki

    According to the statistics by the Ministry of Land, Infrastructure and Transport, the total floor space of all building construction started was 188.87 million m2 (1.5% increase y/y), marking the fourth straight year of increase. Many large-scale buildings under construction in central Tokyo become fully occupied by tenants before completion. As for office buildings, it is required to develop comfortable and functional office spaces as working styles are becoming more and more diversified, and lighting is also an element of such functionalities. The total floor space of construction started for exhibition pavilions, multipurpose halls, conference halls and religious architectures decreased 11.1% against the previous year. This marked a decline for 10 consecutive years and the downward trend continues. In exhibition pavilions, the light radiation is measured and adjusted throughout the year so as not to damage the artworks by lighting. Hospitals, while providing higher quality medical services and enhancing the dwelling environment of patients, are expected to meet various restrictions and requirements, including the respect for privacy. Meanwhile, lighting designs for school classrooms tend to be homogeneous, yet new ideas are being promoted to strike a balance between the economical and functional aspects. The severe economic environment continues to be hampering the growth of theaters and halls in both the private and public sectors. Contrary to the downsizing trend of such facilities, additional installations of lighting equipment were conspicuous, and the adoption of high efficacy lighting appliances and intelligent function control circuits are becoming popular. In the category of stores/commercial facilities, the construction of complex facilities is a continuing trend. Indirect lighting, high luminance discharge lamps with excellent color rendition and LEDs are being effectively used in these facilities, together with the introduction of lighting designs

  4. PUREX facility preclosure work plan

    International Nuclear Information System (INIS)

    This preclosure work plan presents a description of the PUREX Facility, the history of the waste managed, and addresses transition phase activities that position the PUREX Facility into a safe and environmentally secure configuration. For purposes of this documentation, the PUREX Facility does not include the PUREX Storage Tunnels (DOE/RL-90/24). Information concerning solid waste management units is discussed in the Hanford Facility Dangerous Waste Permit Application, General Information Portion (DOE/RL-91-28, Appendix 2D)

  5. Grout treatment facility dangerous waste permit application

    International Nuclear Information System (INIS)

    The Grout Treatment Facility (GTF) will provide permanent disposal for approximately 43 Mgal of radioactive liquid waste currently being stored in underground tanks on the Hanford Site. The first step in permanent disposal is accomplished by solidifying the low-level liquid waste with cementitious dry materials. The resulting grout is cast within underground vaults. This report on the GTF contains information on the following: Hanford Site Maps, road evaluation for the grout treatment facility, Department of Ecology certificate of non-designation for centralia fly ash, double-shell tank waste compositional modeling, laboratory analysis reports for double-shell tank waste, stored in tanks 241-AN-103, 241-AN-106, and 241-AW-101, grout vault heat transfer results for M-106 grout formulation, test results for extraction procedure toxicity testing, test results for toxicity testing of double-shell tank grout, pilot-scale grout production test with a simulated low-level waste, characterization of simulated low-level waste grout produced in a pilot-scale test, description of the procedure for sampling nonaging waste storage tanks, description of laboratory procedures, grout campaign waste composition verification, variability in properties of grouted phosphate/sulfate N-reactor waste, engineering drawings, description of operating procedures, equipment list--transportable grout equipment, grout treatment facility--tank integrity assessment plan, long-term effects of waste solutions on concrete and reinforcing steel, vendor information, grout disposal facilities construction quality assurance plan, and flexible membrane liner/waste compatibility test results

  6. Overview of the National Ignition Facility

    International Nuclear Information System (INIS)

    The National Ignition Facility (NIF) at Lawrence Livermore National Laboratory will be the world's largest and most powerful laser system for inertial confinement fusion (ICF) and experiments studying high energy density (HED) science. NIF is a 192 beam Nd-glass laser facility that will produce 1.8 MJ, 500 TW of ultraviolet light making it over fifty times more energetic than present ICF facilities. The NIF Project began in 1995 and is scheduled for completion in 2009. Ignition experiments on NIF, which will use tritium, are scheduled to begin in 2010. Tritium will arrive at the facility in individual target assemblies. The assemblies will be mounted to the Cryogenic TARget POSitioner (TARPOS), which provides the cryogenic cooling systems necessary to complete the formation of the ignition target's fuel ice layer. It also provides the positioning system that transports and holds the target at the center of the NIF chamber during a shot. After a shot, unburned tritium will be captured by the cryopumps. Upon regeneration, the cryopump effluent will be directed to the Tritium Processing System, part of NIF's. Personnel and Environmental Protection Systems. These systems also include, local contamination control systems, area and stack tritium monitoring systems, a decontamination area, and waste packaging and characterization capability. This equipment will be used along with standard contamination control practices to manage the tritium hazard to workers and to limit releases to the environment to negligibly small amounts

  7. Decommissioning of nuclear facilities

    International Nuclear Information System (INIS)

    Present concepts on stages of, designing for and costs of decommissioning, together with criteria for site release, are described. Recent operations and studies and assessments in progress are summarized. Wastes from decommissioning are characterized

  8. Logistics support of space facilities

    Science.gov (United States)

    Lewis, William C.

    1988-01-01

    The logistic support of space facilities is described, with special attention given to the problem of sizing the inventory of ready spares kept at the space facility. Where possible, data from the Space Shuttle Orbiter is extrapolated to provide numerical estimates for space facilities. Attention is also given to repair effort estimation and long duration missions.

  9. Proton Beam Energy Characterization

    OpenAIRE

    Marus, Lauren A.; Engle, J.W.; John, K. D.; Birnbaum, E. R.; Nortier, F. M.

    2015-01-01

    Introduction The Los Alamos Isotope Production Facility (IPF) is actively engaged in the development of isotope production technologies that can utilize its 100 MeV proton beam. Characterization of the proton beam energy and current is vital for optimizing isotope production and accurately conducting research at the IPF. Motivation In order to monitor beam intensity during research irradiations, aluminum foils are interspersed in experimental stacks. A theoretical yield of 22Na from...

  10. A new AMS facility in Mexico

    Energy Technology Data Exchange (ETDEWEB)

    Solís, C., E-mail: corina@fisica.unam.mx; Chávez-Lomelí, E.; Ortiz, M.E.; Huerta, A.; Andrade, E.; Barrios, E.

    2014-07-15

    A new Accelerator Mass Spectrometry system has been installed at the Institute of Physics of the National Autonomous University of Mexico (UNAM). A sample preparation chemistry laboratory equipped with computer controlled graphitization equipment (AGEIII) has also been established. Together both facilities constitute the LEMA (Laboratorio de Espectrometría de Masas con Aceleradores) first of its kind in Mexico. High sensitivity characterization of the concentration in a sample of {sup 14}C as well as {sup 10}Be, {sup 26}Al, {sup 129}I and Pu are now possible. Since the demand for {sup 14}C dating is far more abundant, a data analysis program was developed in the cross-platform programming language Python in order to calculate radiocarbon age. Results from installation, acceptance tests and the first results of {sup 14}C analyses of reference materials prepared in our own facility are presented.

  11. A new AMS facility in Mexico

    Science.gov (United States)

    Solís, C.; Chávez-Lomelí, E.; Ortiz, M. E.; Huerta, A.; Andrade, E.; Barrios, E.

    2014-07-01

    A new Accelerator Mass Spectrometry system has been installed at the Institute of Physics of the National Autonomous University of Mexico (UNAM). A sample preparation chemistry laboratory equipped with computer controlled graphitization equipment (AGEIII) has also been established. Together both facilities constitute the LEMA (Laboratorio de Espectrometría de Masas con Aceleradores) first of its kind in Mexico. High sensitivity characterization of the concentration in a sample of 14C as well as 10Be, 26Al, 129I and Pu are now possible. Since the demand for 14C dating is far more abundant, a data analysis program was developed in the cross-platform programming language Python in order to calculate radiocarbon age. Results from installation, acceptance tests and the first results of 14C analyses of reference materials prepared in our own facility are presented.

  12. The Great Plains Wind Power Test Facility

    Energy Technology Data Exchange (ETDEWEB)

    Schroeder, John

    2014-01-31

    This multi-year, multi-faceted project was focused on the continued development of a nationally-recognized facility for the testing, characterization, and improvement of grid-connected wind turbines, integrated wind-water desalination systems, and related educational and outreach topics. The project involved numerous faculty and graduate students from various engineering departments, as well as others from the departments of Geosciences (in particular the Atmospheric Science Group) and Economics. It was organized through the National Wind Institute (NWI), which serves as an intellectual hub for interdisciplinary and transdisciplinary research, commercialization and education related to wind science, wind energy, wind engineering and wind hazard mitigation at Texas Tech University (TTU). Largely executed by an academic based team, the project resulted in approximately 38 peer-reviewed publications, 99 conference presentations, the development/expansion of several experimental facilities, and two provisional patents.

  13. The Great Plains Wind Power Test Facility

    Energy Technology Data Exchange (ETDEWEB)

    Schroeder, John [Texas Tech Univ., Lubbock, TX (United States)

    2014-01-30

    This multi-year, multi-faceted project was focused on the continued development of a nationally-recognized facility for the testing, characterization, and improvement of grid-connected wind turbines, integrated wind-water desalination systems, and related educational and outreach topics. The project involved numerous faculty and graduate students from various engineering departments, as well as others from the departments of Geosciences (in particular the Atmospheric Science Group) and Economics. It was organized through the National Wind Institute (NWI), which serves as an intellectual hub for interdisciplinary and transdisciplinary research, commercialization and education related to wind science, wind energy, wind engineering and wind hazard mitigation at Texas Tech University (TTU). Largely executed by an academic based team, the project resulted in approximately 38 peer-reviewed publications, 99 conference presentations, the development/expansion of several experimental facilities, and two provisional patents.

  14. Medical irradiation facilities of HIMAC

    International Nuclear Information System (INIS)

    The construction of the accelerator facilities and the HIMAC buildings started in 1988; the entire HIMAC facility will be completed in 1993. After the initial dosimetry and the mandatory verification of the biological effects of HIMAC beams, clinical trials of the heavy ion beams will start in early 1994 using the HIMAC radiation oncological facilities. The design of this facility, the only medically dedicated heavy-ion accelerator under construction in the world, has been based on the various medical requirements. After becoming operational the HIMAC facility will be opened for domestic and international research collaboration as well as the treatment of patients. (author)

  15. Working with the NCL - Process Overview - Nanotechnology Characterization Laboratory

    Science.gov (United States)

    The Nanotechnology Characterization Lab's (NCL) charter is to serve as a national characterization facility for nanomaterials submitted from academia, industry, and other government laboratories, i.e., intramural and extramural sources.

  16. Facilities removal working group

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-03-01

    This working group`s first objective is to identify major economic, technical, and regulatory constraints on operator practices and decisions relevant to offshore facilities removal. Then, the group will try to make recommendations as to regulatory and policy adjustments, additional research, or process improvements and/or technological advances, that may be needed to improve the efficiency and effectiveness of the removal process. The working group will focus primarily on issues dealing with Gulf of Mexico platform abandonments. In order to make the working group sessions as productive as possible, the Facilities Removal Working Group will focus on three topics that address a majority of the concerns and/or constraints relevant to facilities removal. The three areas are: (1) Explosive Severing and its Impact on Marine Life, (2) Pile and Conductor Severing, and (3) Deep Water Abandonments This paper will outline the current state of practice in the offshore industry, identifying current regulations and specific issues encountered when addressing each of the three main topics above. The intent of the paper is to highlight potential issues for panel discussion, not to provide a detailed review of all data relevant to the topic. Before each panel discussion, key speakers will review data and information to facilitate development and discussion of the main issues of each topic. Please refer to the attached agenda for the workshop format, key speakers, presentation topics, and panel participants. The goal of the panel discussions is to identify key issues for each of the three topics above. The working group will also make recommendations on how to proceed on these key issues.

  17. The Fair Facility

    Science.gov (United States)

    Nilsson, Thomas

    2015-03-01

    The FAIR (Facility for Antiproton and Ion Beams), under construction at the GSI site in Darmstadt, Germany, will be addressing a wealth of outstanding questions within the realm of subatomic, atomic and plasma physics through a combination of novel accelerators, storage rings and innovative experimental setups. The envisaged programme of FAIR yields a breadth that is unprecedented at an accelerator-based infrastructure. A brief review of the FAIR infrastructure and scientific reach is made, together with an update of the status of the construction.

  18. CLIC Test Facility 3

    CERN Multimedia

    Kossyvakis, I; Faus-golfe, A

    2007-01-01

    The design of CLIC is based on a two-beam scheme, where short pulses of high power 30 GHz RF are extracted from a drive beam running parallel to the main beam. The 3rd generation CLIC Test Facility (CTF3) will demonstrate the generation of the drive beam with the appropriate time structure, the extraction of 30 GHz RF power from this beam, as well as acceleration of a probe beam with 30 GHz RF cavities. The project makes maximum use of existing equipment and infrastructure of the LPI complex, which became available after the closure of LEP.

  19. Characterization of the geochemical processes present in the radionuclides and metals mobilization in the tailing dam at the Uranium Mining and Milling Facilities - Pocos de Caldas, MG, Brazil; Caracterizacao dos processos geoquimicos atuantes na mobilizacao de radionuclideos e metais na bacia de rejeitos do complexo minero-industrial de Pocos de Caldas, MG, Brazil

    Energy Technology Data Exchange (ETDEWEB)

    Pinto, Patricia Freitas

    1995-08-01

    In Brazil, the first step of nuclear fuel cycle - the mining and milling of the uranium ore - is developed at the Uranium Mining and Milling Facilities of Pocos de Caldas, Minas Gerais state. The wastes management is a very important aspect of the process. The understanding of the geochemical processes that occur in the tailings dam is a key question to define a plan of action concerning the decommissioning strategy of the facility. The objective of the present work was to give some issues to help in the adoption of the remedial actions concerning the decommissioning of the facility. It focused on the characterization of the most important geochemical processes regulating the mobilization of radionuclides and heavy metals in the tailings dam. Two cores from the tailings dam (uncovered area) were collected. Seepage and drainage waters were sampled, the same being true for the tailings dam lake. Groundwater form an aquifer bellow the tailings dam and superficial waters from a river that receives the effluents of the dam (Soberbo River) were also sampled. Data from the mining company were used to calculate the inventory of radionuclides and heavy metals deposited in the waste dam.The obtained results showed that pyrite oxidation is the key process in the mobilization of radionuclides and heavy metals from the wastes. Pyrite oxidation is a process regulated by oxygen diffusion and water. In the studied scenario it could be shown that the process was limited to a one meter deep layer in the uncovered part of the waste dam. Because of this, Fe, Al, Mn, Zn, Th and {sup 238} U showed higher concentrations in the bottom layers of the cores in relation to the upper ones. {sup 226} Ra and {sup 210} Pb showed opposite patterns. The coprecipitation with Ca SO{sub 4} was the most relevant mechanism in both radionuclides immobilization in the wastes. Sulfate was the only chemical species that could be assigned as a contaminant in aquifer bellow the waste dam. As a conclusion, the

  20. PUREX facility hazards assessment

    Energy Technology Data Exchange (ETDEWEB)

    Sutton, L.N.

    1994-09-23

    This report documents the hazards assessment for the Plutonium Uranium Extraction Plant (PUREX) located on the US Department of Energy (DOE) Hanford Site. Operation of PUREX is the responsibility of Westinghouse Hanford Company (WHC). This hazards assessment was conducted to provide the emergency planning technical basis for PUREX. DOE Order 5500.3A requires an emergency planning hazards assessment for each facility that has the potential to reach or exceed the lowest level emergency classification. In October of 1990, WHC was directed to place PUREX in standby. In December of 1992 the DOE Assistant Secretary for Environmental Restoration and Waste Management authorized the termination of PUREX and directed DOE-RL to proceed with shutdown planning and terminal clean out activities. Prior to this action, its mission was to reprocess irradiated fuels for the recovery of uranium and plutonium. The present mission is to establish a passively safe and environmentally secure configuration at the PUREX facility and to preserve that condition for 10 years. The ten year time frame represents the typical duration expended to define, authorize and initiate follow-on decommissioning and decontamination activities.

  1. TESLA Test Facility. Status

    Energy Technology Data Exchange (ETDEWEB)

    Aune, B. [Deutsches Elektronen-Synchrotron (DESY), Hamburg (Germany); TESLA Collaboration

    1996-01-01

    The TESLA Test Facility (TTF), under construction at DESY by an international collaboration, is an R and D test bed for the superconducting option for future linear e+/e-colliders. It consists of an infrastructure to process and test the cavities and of a 500 MeV linac. The infrastructure has been installed and is fully operational. It includes a complex of clean rooms, an ultra-clean water plant, a chemical etching installation and an ultra-high vacuum furnace. The linac will consist of four cryo-modules, each containing eight 1 meter long nine-cell cavities operated at 1.3 GHz. The base accelerating field is 15 MV/m. A first injector will deliver a low charge per bunch beam, with the full average current (8 mA in pulses of 800 {mu}s). A more powerful injector based on RF gun technology will ultimately deliver a beam with high charge and low emittance to allow measurements necessary to qualify the TESLA option and to demonstrate the possibility of operating a free electron laser based on the Self-Amplified-Spontaneous-Emission principle. Overview and status of the facility will be given. Plans for the future use of the linac are presented. (R.P.). 19 refs.

  2. Underground Facilities, Technological Challenges

    CERN Document Server

    Spooner, N

    2010-01-01

    This report gives a summary overview of the status of international under- ground facilities, in particular as relevant to long-baseline neutrino physics and neutrino astrophysics. The emphasis is on the technical feasibility aspects of creating the large underground infrastructures that will be needed in the fu- ture to house the necessary detectors of 100 kton to 1000 kton scale. There is great potential in Europe to build such a facility, both from the technical point of view and because Europe has a large concentration of the necessary engi- neering and geophysics expertise. The new LAGUNA collaboration has made rapid progress in determining the feasibility for a European site for such a large detector. It is becoming clear in fact that several locations are technically fea- sible in Europe. Combining this with the possibility of a new neutrino beam from CERN suggests a great opportunity for Europe to become the leading centre of neutrino studies, combining both neutrino astrophysics and neutrino beam stu...

  3. Grout Facilities standby plan

    International Nuclear Information System (INIS)

    This plan defines how the Grout Facilities will be deactivated to meet the intent of the recently renegotiated Tri-Party Agreement (TPA). The TPA calls for the use of the grout process as an emergency option only in the event that tank space is not available to resolve tank safety issues. The availability of new tanks is expected by 1997. Since a grout startup effort would take an estimated two years, a complete termination of the Grout Disposal Program is expected in December 1995. The former Tank Waste Remediation (TWRS) Strategy, adopted in 1988, called for the contents of Hanford's 28 newer double-shell waste tanks to be separated into high-level radioactive material to be vitrified and disposed of in a geologic repository; low-level wastes were to be sent to the Grout Facility to be made into a cement-like-mixture and poured into underground vaults at Hanford for disposal. The waste in the 149 older single-shell tanks (SST) were to undergo further study and analysis before a disposal decision was made

  4. Geothermal energy conversion facility

    Energy Technology Data Exchange (ETDEWEB)

    Kutscher, C.F.

    1997-12-31

    With the termination of favorable electricity generation pricing policies, the geothermal industry is exploring ways to improve the efficiency of existing plants and make them more cost-competitive with natural gas. The Geothermal Energy Conversion Facility (GECF) at NREL will allow researchers to study various means for increasing the thermodynamic efficiency of binary cycle geothermal plants. This work has received considerable support from the US geothermal industry and will be done in collaboration with industry members and utilities. The GECF is being constructed on NREL property at the top of South Table Mountain in Golden, Colorado. As shown in Figure 1, it consists of an electrically heated hot water loop that provides heating to a heater/vaporizer in which the working fluid vaporizes at supercritical or subcritical pressures as high as 700 psia. Both an air-cooled and water-cooled condenser will be available for condensing the working fluid. In order to minimize construction costs, available equipment from the similar INEL Heat Cycle Research Facility is being utilized.

  5. Aircraft Landing Dynamics Facility - A unique facility with new capabilities

    Science.gov (United States)

    Davis, P. A.; Stubbs, S. M.; Tanner, J. A.

    1985-01-01

    The Aircraft Landing Dynamics Facility (ALDF), formerly called the Landing Loads Track, is described. The paper gives a historical overview of the original NASA Langley Research Center Landing Loads Track and discusses the unique features of this national test facility. Comparisons are made between the original track characteristics and the new capabilities of the Aircraft Landing Dynamics Facility following the recently completed facility update. Details of the new propulsion and arresting gear systems are presented along with the novel features of the new high-speed carriage. The data acquisition system is described and the paper concludes with a review of future test programs.

  6. Indoor Lighting Facilities

    Science.gov (United States)

    Matsushima, Koji; Saito, Yoshinori; Ichikawa, Shigenori; Kawauchi, Takao; Tanaka, Tsuneo; Hirano, Rika; Tazuke, Fuyuki

    According to the statistics on building construction floor area from the Ministry of Land, Infrastructure, Transport and Tourism, the total floor area of building construction started in Japan in 2007 was 160,991 thousand square meters, or 14.8% less than the area of the previous year, and the reduction was the first reduction in the past five years. The office markets in Tokyo and Nagoya were active, as represented by the supplies of skyscrapers, and energy saving measures, such as the adoption of high efficiency lighting equipment, the control for initial stage illuminance, daylight harvesting, and the use of occupancy sensors, were well established. In the field of public construction, including museums, multi-purpose halls, and religious buildings, the total area of the new construction was 10.8% less than the total for the previous year, and this reduction was a continuation of an eleven-year trend. In spaces with high ceiling, the innovation for easy replacement of light sources used with reflection mirror systems and optical fibers was noted. Hospitals adapted to the expectation for improved services in their selection of lighting facilities to improve the residential environment for patients while taking into consideration the needs of the aging population, by their use of devices in corridors to help maintain a continuity of light. In libraries, a pendant system was developed to illuminate both ceilings and book shelves. In the field of theaters and halls, the time limit for repairing existing systems had come for the large facilities that were opened during the theater and hall construction boom of the 1960s through 1980s, and around 26 renovations were done. Almost all the renovations were conversions to intelligent dimming systems and lighting control desks. In the field of stores and commercial facilities, the atmosphere and glitter of the selling floor was produced by new light sources, such as ceramic metal halide lamps and LEDs, which have high

  7. FMIT facility control system

    International Nuclear Information System (INIS)

    The control system for the Fusion Materials Irradiation Test (FMIT) Facility, under construction at Richland, Washington, uses current techniques in distributed processing to achieve responsiveness, maintainability and reliability. Developmental experience with the system on the FMIT Prototype Accelerator (FPA) being designed at the Los Alamos National Laboratory is described as a function of the system's design goals and details. The functional requirements of the FMIT control system dictated the use of a highly operator-responsive, display-oriented structure, using state-of-the-art console devices for man-machine communications. Further, current technology has allowed the movement of device-dependent tasks into the area traditionally occupied by remote input-output equipment; the system's dual central process computers communicate with remote communications nodes containing microcomputers that are architecturally similar to the top-level machines. The system has been designed to take advantage of commercially available hardware and software

  8. The Avian Development Facility

    Science.gov (United States)

    2003-01-01

    The Avian Development Facility (ADF) supports 36 eggs in two carousels, one of which rotates to provide a 1-g control for comparing to eggs grown in microgravity. The ADF was designed to incubate up to 36 Japanese quail eggs, 18 in microgravity and 18 in artificial gravity. The two sets of eggs were exposed to otherwise identical conditions, the first time this is been accomplished in space. Eggs are preserved at intervals to provide snapshots of their development for later analysis. Quails incubate in just 15 days, so they are an ideal species to be studied within the duration of space shuttle missions. Further, several investigators can use the same specimens to address different questions. The ADF originated in NASA's Shuttle Student Involvement program in the 1980s and was developed under the NASA Small Business Irnovation Research program. In late 2001, the ADF made its first flight and carried eggs used in two investigations.

  9. Technology Development Facility (TDF)

    International Nuclear Information System (INIS)

    We have been studying small, driven, magnetic-mirror-based fusion reactors for the Technology Development Facility (TDF), that will test fusion reactor materials, components, and subsystems. Magnetic mirror systems are particularly interesting for this application because of their inherent steady-state operation, potentially high neutron wall loading, and relatively small size. Our design is a tandem mirror device first described by Fowler and Logan, based on the physics of the TMX experiments at Lawrence Livermore National Laboratory (LLNL). The device produces 20 MW of fusion power with a first-wall, uncollided 14-MeV neutron flux of 1.4 MW/m2 on an area of approximately 8 m2, while consuming approximately 250 MW of electrical power. The work was done by a combined industrial-laboratory-university group

  10. The National Ignition Facility

    International Nuclear Information System (INIS)

    The National Ignition Facility (NIF) is the largest construction project ever undertaken at Lawrence Livermore National Laboratory (LLNL). NIF consists of 192 forty-centimeter-square laser beams and a 10-m-diameter target chamber. NIF is being designed and built by an LLNL-led team from Los Alamos National Laboratory, Sandia National Laboratories, the University of Rochester, and LLNL. Physical construction began in 1997. The Laser and Target Area Building and the Optics Assembly Building were the first major construction activities, and despite several unforeseen obstacles, the buildings are now 92% complete and have been done on time and within cost. Prototype component development and testing has proceeded in parallel. Optics vendors have installed full-scale production lines and have done prototype production runs. The assembly and integration of the beampath infrastructure has been reconsidered and a new approach has been developed. This paper will discuss the status of the NIF project and the plans for completion. (author)

  11. Power Systems Development Facility

    Energy Technology Data Exchange (ETDEWEB)

    Southern Company Services

    2009-01-31

    In support of technology development to utilize coal for efficient, affordable, and environmentally clean power generation, the Power Systems Development Facility (PSDF), located in Wilsonville, Alabama, has routinely demonstrated gasification technologies using various types of coals. The PSDF is an engineering scale demonstration of key features of advanced coal-fired power systems, including a Transport Gasifier, a hot gas particulate control device, advanced syngas cleanup systems, and high-pressure solids handling systems. This final report summarizes the results of the technology development work conducted at the PSDF through January 31, 2009. Twenty-one major gasification test campaigns were completed, for a total of more than 11,000 hours of gasification operation. This operational experience has led to significant advancements in gasification technologies.

  12. Decommissioning Russian Research Facilities

    International Nuclear Information System (INIS)

    Gosatomnadzor of Russia is conducting the safety regulation and inspection activity related to nuclear and radiation safety of nuclear research facilities (RR), including research reactors, critical assemblies and sub-critical assemblies. Most of the Russian RR were built and put in operation more than 30 years ago. The problems of ageing equipment and strengthening of safety requirements in time, the lack of further experimental programmes and financial resources, have created a condition when some of the RR were forced to take decisions on their decommissioning. The result of these problems was reflected in reducing the number of RR from 113 in 1998 to 81 in the current year. At present, seven RR are already under decommissioning or pending it. Last year, the Ministry of Atomic Energy took the decision to finally shut down two remaining actual research reactors in the Physics and Power Engineering Institute in Obninsk: AM-1, the first reactor in the world built for peaceful purposes, graphite-type reactor, and the fast liquid metal reactor BR-10, and to start their preparation for decommissioning. It is not enough just to declare the decommissioning of a RR: it is also vital to find financial resources for that purpose. For this reason, due to lack of financing, the MR reactor at the Kurchatov Institute has been pending decommissioning since 1992 and still is. The other example of long-lasting decommissioning is TVR, a heavy water reactor at the Institute of Theoretical Physics in Moscow (ITEF). The reason is also poor financing. Another example discussed in the paper concerns on-site disposal of a RR located above the Arctic Pole Circle, owned by the Norilsk Mining Company. Furthermore, the experience of the plutonium reactor decommissioning at the Joint Institute of Nuclear Research is also discussed. As shown, the Russian Federation has had good experiences in the decommissioning of nuclear research facilities. (author)

  13. Securing a HENP Computing Facility

    CERN Document Server

    Misawa, S; Throwe, T

    2003-01-01

    Traditionally, HENP computing facilities have been open facilities that are accessed in many different ways by users that are both internal and external to the facility. However, the need to protect the facility from cybersecurity threats has made it difficult to maintain the openness of the facility to off-site and on-site users. In this paper, we discuss the strategy we have used and the architecture we have developed and deployed to increase the security the US ATLAS and RHIC Computing Facilities, while trying to maintain the openness and accessibility that our user community has come to expect. Included in this discussion are the tools that we have used and the operational experience we have had with the deployed architecture.

  14. User facilities at federal laboratories

    Energy Technology Data Exchange (ETDEWEB)

    Baron, S.; Marcuse, W.

    1988-04-01

    Recent initiatives by the Congress and the Administration have been directed to improving American industrial competitiveness. One of these initiatives is directed to encouraging industrial users to avail themselves of special facilities existent at federal laboratories. The facilities available at the National Bureau of Standards (NBS) and seven Department of Energy (DOE) laboratories are presented here. One facility at each Laboratory is described in detail, the remainder are listed with the names and telephone numbers of individuals to contact for further information.

  15. Regulatory facility guide for Ohio

    Energy Technology Data Exchange (ETDEWEB)

    Anderson, S.S.; Bock, R.E.; Francis, M.W.; Gove, R.M.; Johnson, P.E.; Kovac, F.M.; Mynatt, J.O. [Oak Ridge National Lab., TN (United States); Rymer, A.C. [Transportation Consulting Services, Knoxville, TN (United States)

    1994-02-28

    The Regulatory Facility Guide (RFG) has been developed for the DOE and contractor facilities located in the state of Ohio. It provides detailed compilations of international, federal, and state transportation-related regulations applicable to shipments originating at destined to Ohio facilities. This RFG was developed as an additional resource tool for use both by traffic managers who must ensure that transportation operations are in full compliance with all applicable regulatory requirements and by oversight personnel who must verify compliance activities.

  16. Data Management Facility Operations Plan

    Energy Technology Data Exchange (ETDEWEB)

    Keck, Nicole N

    2014-06-30

    The Data Management Facility (DMF) is the data center that houses several critical Atmospheric Radiation Measurement (ARM) Climate Research Facility services, including first-level data processing for the ARM Mobile Facilities (AMFs), Eastern North Atlantic (ENA), North Slope of Alaska (NSA), Southern Great Plains (SGP), and Tropical Western Pacific (TWP) sites, as well as Value-Added Product (VAP) processing, development systems, and other network services.

  17. Computational analysis of irradiation facilities at the JSI TRIGA reactor

    Energy Technology Data Exchange (ETDEWEB)

    Snoj, Luka, E-mail: luka.snoj@ijs.si [Jozef Stefan Institute, Jamova cesta 39, SI-1000 Ljubljana (Slovenia); Zerovnik, Gasper, E-mail: gasper.zerovnik@ijs.si [Jozef Stefan Institute, Jamova cesta 39, SI-1000 Ljubljana (Slovenia); Trkov, Andrej, E-mail: andrej.trkov@ijs.si [Jozef Stefan Institute, Jamova cesta 39, SI-1000 Ljubljana (Slovenia)

    2012-03-15

    Characterization and optimization of irradiation facilities in a research reactor is important for optimal performance. Nowadays this is commonly done with advanced Monte Carlo neutron transport computer codes such as MCNP. However, the computational model in such calculations should be verified and validated with experiments. In the paper we describe the irradiation facilities at the JSI TRIGA reactor and demonstrate their computational characterization to support experimental campaigns by providing information on the characteristics of the irradiation facilities. - Highlights: Black-Right-Pointing-Pointer TRIGA reactor at JSI suitable for irradiation under well defined conditions. Black-Right-Pointing-Pointer It features irradiation channels of different fluxes, spectra, and dimensions. Black-Right-Pointing-Pointer Computational model has been developed and experimentally verified. Black-Right-Pointing-Pointer The model used for optimization of experiments and evaluation of uncertainties.

  18. Region 9 NPDES 2011 Facilities

    Data.gov (United States)

    U.S. Environmental Protection Agency — Point geospatial dataset representing locations of NPDES Facilities. NPDES (National Pollution Discharge Elimination System) is an EPA permit program that regulates...

  19. Weapons Neutron Research Facility (WNR)

    Data.gov (United States)

    Federal Laboratory Consortium — The Weapons Neutron Research Facility (WNR) provides neutron and proton beams for basic, applied, and defense-related research. Neutron beams with energies ranging...

  20. Materials Engineering Research Facility (MERF)

    Data.gov (United States)

    Federal Laboratory Consortium — Argonne?s Materials Engineering Research Facility (MERF) enables engineers to develop manufacturing processes for producing advanced battery materials in sufficient...

  1. 304 Concretion facility closure plan

    International Nuclear Information System (INIS)

    The Hanford Site, located northwest of Richland, Washington, houses reactors, chemical-separation systems, and related facilities used for the production of special nuclear materials. The 300 Area of the Hanford Site contains reactor fuel manufacturing facilities and several research and development laboratories. Recyclable scrap uranium Zircaloy-2 and copper silicon alloy, uranium-titanium alloy, beryllium/Zircaloy-2 alloy, and Zircaloy-2 chips and fines were secured in concrete billets in the 304 Concretion Facility, located in the 300 Area. The beryllium/Zircaloy-2 alloy and Zircaloy-2 chips and fines are designated as low-level radioactive mixed waste (LLRMW) with the characteristic of ignitability. The concretion process reduced the ignitability of the fines and chips for safe storage and shipment. This process has been discontinued and the 304 Concretion Facility is now undergoing closure as defined in the Resource Conservation and Recovery Act of 1976 (RCRA). This closure plan presents a description of the facility, the history of materials and wastes managed, and the procedures that will be followed to close the 304 Concretion Facility (304 Facility). Clean closure of the 304 Facility is the proposed method for closure of the facility. Justification for this proposal is presented. 15 refs., 22 figs., 4 tabs

  2. Agency Data on User Facilities

    Data.gov (United States)

    National Aeronautics and Space Administration — The purpose of the Aerospace Technical Facility Inventory is to facilitate the sharing of specialized capabilities within the aerospace research/engineering...

  3. Region 9 NPDES Facilities 2012

    Data.gov (United States)

    U.S. Environmental Protection Agency — Point geospatial dataset representing locations of NPDES Facilities. NPDES (National Pollution Discharge Elimination System) is an EPA permit program that regulates...

  4. Radio Frequency Anechoic Chamber Facility

    Data.gov (United States)

    Federal Laboratory Consortium — FUNCTION: Supports the design, manufacture, and test of antenna systems. The facility is also used as an electromagnetic compatibility/radio frequency interference...

  5. Poultry Slaughtering and Processing Facilities

    Data.gov (United States)

    Department of Homeland Security — Agriculture Production Poultry Slaughtering and Processing in the United States This dataset consists of facilities which engage in slaughtering, processing, and/or...

  6. National Ignition Facility system design requirements conventional facilities SDR001

    Energy Technology Data Exchange (ETDEWEB)

    Hands, J.

    1996-04-09

    This System Design Requirements (SDR) document specifies the functions to be performed and the minimum design requirements for the National Ignition Facility (NIF) site infrastructure and conventional facilities. These consist of the physical site and buildings necessary to house the laser, target chamber, target preparation areas, optics support and ancillary functions.

  7. RADBALL TECHNOLOGY TESTING FOR HOT CELL CHARACTERIZATION

    Energy Technology Data Exchange (ETDEWEB)

    Farfan, E.; Jannik, T.

    2010-03-25

    Operations at various U.S. Department of Energy sites have resulted in substantial radiological contamination of tools, equipment, and facilities. It is essential to use remote technologies for characterization and decommissioning to keep worker exposures as low as reasonably achievable in these highly contaminated environments. A significant initial step in planning and implementing D&D of contaminated facilities involves the development of an accurate assessment of the radiological, chemical, and structural conditions inside of the facilities. Collected information describing facility conditions using remote technologies could reduce the conservatism associated with planning initial worker entry (and associated cost).

  8. Decommissioning of Radiotherapy Facilities

    International Nuclear Information System (INIS)

    Radiotherapy units containing high activity sealed radioactive sources of 60Co or 137Cs are mainly use for medical, research or calibration applications. After several half-lives of decay, the radionuclide source has to be changed or the unit is decommissioned if no longer required. Before starting a decommissioning project it is very important to look for documents relating to any sources held or installed in equipment. In general this should be no problem because the recommended working life of such sealed radioactive sources is limited to 10 or a maximum of 15 years. These time periods are short in comparison with other facilities like research laboratories or small reactors. These documents (source certificates) will be very helpful to plan the decommissioning because they say everything about the original activity of the source at a reference date, the type of the source and the manufacturer. The next step may be to contact the machine supplier or the source manufacturer, but be aware that neither may still be in existence or may have changed their type of business. In such cases, it is recommended to contact national or international sealed source manufacturers or suppliers for help. Sometimes it is also helpful to contact colleagues in other hospitals or research centres to ask for information about specialists in this topic. In general it is not useful, and even very dangerous, to try to decommission such a unit without expert help It is essential to have specialist tools and shielded containers to recover the source out of the unit. It is strongly recommended to invite the source removal specialist for a site visit to review the situation before starting any decommissioning process. A further problem can occur, if the source must be transported to a national storage centre or even an international storage facility, as the source must be packaged to meet international transport requirements. The end state of such a project should be an empty room where the

  9. Facility effluent monitoring plan for 242-A Evaporator facility

    International Nuclear Information System (INIS)

    A facility effluent monitoring plan is required by the US Department of Energy in DOE Order 5400.1* for any operations that involve hazardous materials and radioactive substances that could affect employee or public safety or the environment. A facility effluent monitoring plan determination was performed during Calendar Year 1991 and the evaluation showed the need for a facility effluent monitoring plan. This document is prepared using the specific guidelines identified in A Guide for Preparing Hanford Site Facility effluent Monitoring Plans, WHC-EP-0438-1**. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether they are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements

  10. Uncertainties in risk assessment at USDOE facilities

    International Nuclear Information System (INIS)

    The United States Department of Energy (USDOE) has embarked on an ambitious program to remediate environmental contamination at its facilities. Decisions concerning cleanup goals, choices among cleanup technologies, and funding prioritization should be largely risk-based. Risk assessments will be used more extensively by the USDOE in the future. USDOE needs to develop and refine risk assessment methods and fund research to reduce major sources of uncertainty in risk assessments at USDOE facilities. The terms open-quote risk assessment close-quote and open-quote risk management close-quote are frequently confused. The National Research Council (1983) and the United States Environmental Protection Agency (USEPA, 1991a) described risk assessment as a scientific process that contributes to risk management. Risk assessment is the process of collecting, analyzing and integrating data and information to identify hazards, assess exposures and dose responses, and characterize risks. Risk characterization must include a clear presentation of open-quotes... the most significant data and uncertainties...close quotes in an assessment. Significant data and uncertainties are open-quotes...those that define and explain the main risk conclusionsclose quotes. Risk management integrates risk assessment information with other considerations, such as risk perceptions, socioeconomic and political factors, and statutes, to make and justify decisions. Risk assessments, as scientific processes, should be made independently of the other aspects of risk management (USEPA, 1991a), but current methods for assessing health risks are based on conservative regulatory principles, causing unnecessary public concern and misallocation of funds for remediation

  11. Uncertainties in risk assessment at USDOE facilities

    Energy Technology Data Exchange (ETDEWEB)

    Hamilton, L.D.; Holtzman, S.; Meinhold, A.F.; Morris, S.C.; Rowe, M.D.

    1994-01-01

    The United States Department of Energy (USDOE) has embarked on an ambitious program to remediate environmental contamination at its facilities. Decisions concerning cleanup goals, choices among cleanup technologies, and funding prioritization should be largely risk-based. Risk assessments will be used more extensively by the USDOE in the future. USDOE needs to develop and refine risk assessment methods and fund research to reduce major sources of uncertainty in risk assessments at USDOE facilities. The terms{open_quote} risk assessment{close_quote} and{open_quote} risk management{close_quote} are frequently confused. The National Research Council (1983) and the United States Environmental Protection Agency (USEPA, 1991a) described risk assessment as a scientific process that contributes to risk management. Risk assessment is the process of collecting, analyzing and integrating data and information to identify hazards, assess exposures and dose responses, and characterize risks. Risk characterization must include a clear presentation of {open_quotes}... the most significant data and uncertainties...{close_quotes} in an assessment. Significant data and uncertainties are {open_quotes}...those that define and explain the main risk conclusions{close_quotes}. Risk management integrates risk assessment information with other considerations, such as risk perceptions, socioeconomic and political factors, and statutes, to make and justify decisions. Risk assessments, as scientific processes, should be made independently of the other aspects of risk management (USEPA, 1991a), but current methods for assessing health risks are based on conservative regulatory principles, causing unnecessary public concern and misallocation of funds for remediation.

  12. Nuclear physics accelerator facilities

    International Nuclear Information System (INIS)

    The Department of Energy's Nuclear Physics program is a comprehensive program of interdependent experimental and theoretical investigation of atomic nuclei. Long range goals are an understanding of the interactions, properties, and structures of atomic nuclei and nuclear matter at the most elementary level possible and an understanding of the fundamental forces of nature by using nuclei as a proving ground. Basic ingredients of the program are talented and imaginative scientists and a diversity of facilities to provide the variety of probes, instruments, and computational equipment needed for modern nuclear research. Approximately 80% of the total Federal support of basic nuclear research is provided through the Nuclear Physics program; almost all of the remaining 20% is provided by the National Science Foundation. Thus, the Department of Energy (DOE) has a unique responsibility for this important area of basic science and its role in high technology. Experimental and theoretical investigations are leading us to conclude that a new level of understanding of atomic nuclei is achievable. This optimism arises from evidence that: (1) the mesons, protons, and neutrons which are inside nuclei are themselves composed of quarks and gluons and (2) quantum chromodynamics can be developed into a theory which both describes correctly the interaction among quarks and gluons and is also an exact theory of the strong nuclear force. These concepts are important drivers of the Nuclear Physics program

  13. Generalized plotting facility

    Energy Technology Data Exchange (ETDEWEB)

    Burris, R.D.; Gray, W.H.

    1978-01-01

    A command which causes the translation of any supported graphics file format to a format acceptable to any supported device was implemented on two linked DECsystem-10s. The processing of the command is divided into parsing and translating phases. In the parsing phase, information is extracted from the command and augmented by default data. The results of this phase are saved on disk, and the appropriate translating routine is invoked. Twenty-eight translating programs were implemented in this system. They support four different graphics file formats, including the DISSPLA and Calcomp formats, and seven different types of plotters, including Tektronix, Calcomp, and Versatec devices. Some of the plotters are devices linked to the DECsystem-10s, and some are driven by IBM System/360 computers linked via a communications network to the DECsystem-10s. The user of this facility can use any of the supported packages to create a file of graphics data, preview the file on an on-line scope, and, when satisfied, cause the same data to be plotted on a hard-copy device. All of the actions utilize a single simple command format. 2 figures.

  14. Power Systems Development Facility

    Energy Technology Data Exchange (ETDEWEB)

    Southern Company Services

    2004-04-30

    This report discusses Test Campaign TC15 of the Kellogg Brown & Root, Inc. (KBR) Transport Gasifier train with a Siemens Power Generation, Inc. (SPG) particle filter system at the Power Systems Development Facility (PSDF) located in Wilsonville, Alabama. The Transport Gasifier is an advanced circulating fluidized-bed reactor designed to operate as either a combustor or gasifier using a particulate control device (PCD). While operating as a gasifier, either air or oxygen can be used as the oxidant. Test run TC15 began on April 19, 2004, with the startup of the main air compressor and the lighting of the gasifier startup burner. The Transport Gasifier was shutdown on April 29, 2004, accumulating 200 hours of operation using Powder River Basin (PRB) subbituminous coal. About 91 hours of the test run occurred during oxygen-blown operations. Another 6 hours of the test run was in enriched-air mode. The remainder of the test run, approximately 103 hours, took place during air-blown operations. The highest operating temperature in the gasifier mixing zone mostly varied from 1,800 to 1,850 F. The gasifier exit pressure ran between 200 and 230 psig during air-blown operations and between 110 and 150 psig in oxygen-enhanced air operations.

  15. Power Systems Development Facility

    Energy Technology Data Exchange (ETDEWEB)

    None

    2003-07-01

    This report discusses Test Campaign TC12 of the Kellogg Brown & Root, Inc. (KBR) Transport Gasifier train with a Siemens Westinghouse Power Corporation (SW) particle filter system at the Power Systems Development Facility (PSDF) located in Wilsonville, Alabama. The Transport Gasifier is an advanced circulating fluidized-bed reactor designed to operate as either a combustor or a gasifier using a particulate control device (PCD). While operating as a gasifier, either air or oxygen can be used as the oxidant. Test run TC12 began on May 16, 2003, with the startup of the main air compressor and the lighting of the gasifier start-up burner. The Transport Gasifier operated until May 24, 2003, when a scheduled outage occurred to allow maintenance crews to install the fuel cell test unit and modify the gas clean-up system. On June 18, 2003, the test run resumed when operations relit the start-up burner, and testing continued until the scheduled end of the run on July 14, 2003. TC12 had a total of 733 hours using Powder River Basin (PRB) subbituminous coal. Over the course of the entire test run, gasifier temperatures varied between 1,675 and 1,850 F at pressures from 130 to 210 psig.

  16. EVA Training and Development Facilities

    Science.gov (United States)

    Cupples, Scott

    2016-01-01

    Overview: Vast majority of US EVA (ExtraVehicular Activity) training and EVA hardware development occurs at JSC; EVA training facilities used to develop and refine procedures and improve skills; EVA hardware development facilities test hardware to evaluate performance and certify requirement compliance; Environmental chambers enable testing of hardware from as large as suits to as small as individual components in thermal vacuum conditions.

  17. Data analysis facility at LAMPF

    International Nuclear Information System (INIS)

    This report documents the discussions and conclusions of a study held in July 1977 to develop the requirements for a data analysis facility to support the experimental program in medium-energy physics at the Clinton P. Anderson Meson Physics Facility (LAMPF). 2 tables

  18. BNCT irradiation facility at the JRR-4

    Energy Technology Data Exchange (ETDEWEB)

    Torii, Y.; Kishi, T.; Kumada, H.; Yamamoto, K.; Sakurai, F.; Takayanagi, M. [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    2000-10-01

    The JRR--4 was modified for fuel enrichment reducing and reactor equipment renewal. And also a medical irradiation facility for the Boron Neutron Capture Therapy (BNCT) was installed at the JRR--4 in that time. The medical irradiation facility has been composed of a heavy water tank, a collimator and an irradiation room. The heavy water tank has four layers of heavy water for spectrum shifter and 75cm-thickness aluminum for the shield of fast neutron. The collimator is for collimating thermal neutron and epithermal neutron using polyethylene with lithium-fluoride and shielding gamma ray by bismuth. The irradiation room has sufficient space at exit side of the beam, to accommodate a large working area for setting the patient. Both of the medical treatment room and the patient-monitoring area were prepared adjacent to the irradiation room. The medical irradiation facility in the JRR-4 is designed to permit selection of neutron energies from thermal neutron to epithermal neutron by changing the thickness of heavy water layers. Therefore it is available to continue the same kind of BNCT with thermal neutron used to perform in the JRR-2, as well as to commence the research and development of BNCT with epithermal neutron, which will make the brain tumor treatment possible at a deep part of brain. The full power operation of the JRR-4 was resumed with LEU fuel in October 1998 and currently performing some experiments to measure the neutron fluxes and physical doses for determinate characterization of the medical irradiation facility. The first medical irradiation for BNCT was carried out on 25th October 1999. The patient was treated by Tsukuba University group using thermal neutron beam included epi-thermal neutrons. (author)

  19. Scintillator characterization using the LBL Pulsed X-ray Facility

    International Nuclear Information System (INIS)

    The authors have developed a bench-top pulsed x-ray system for measuring scintillation properties of compounds in crystal or powdered form. The source is a light-excited x-ray tube that produces 40 x-ray photons (mean energy 18.5 keV) per steradian in each 100 ps fwhm pulse. The repetition rate is adjustable from 0 to 107 pulses per second. The fluorescent emanations from the x-ray excited samples are detected with either a sapphire-windowed microchannel plate photomultiplier tube (spectral range 150--650 nm, transit time jitter 40 ps fwhm) or a quartz windowed GaAs(Cs) photomultiplier tube (spectral range 160--930 nm, transit time jitter 4 ns fwhm). Decay time spectra are acquired using a TDC Havina 40 ps fwhm resolution over a 84 ms dynamic range. A computer controlled monochromator can be inserted into the optical path to measure the emission spectrum or wavelength resolved decay time spectrum. A computer controlled sample changer allows up to 64 samples to be measured without intervention

  20. Facile synthesis and characterization of novel pseudo-hypercrosslinked resin

    Institute of Scientific and Technical Information of China (English)

    Si Guo Yuan; Shao Hui Zhang; Wei Hua Zou; Yong Hao Zhou; Xiao Hui Zhou

    2008-01-01

    A kind of pseudo-hypercrosslinked polymer resin was firstly synthesized via a continuous Friedel--Crafts alkylation poly-merization of benzene, diphenyl and their dichloromethyl derivatives. And the micromorphology and adsorption properties of theseresins were investigated. The results demonstrated that the novel resins have high-specific surface area (581.26-974.88 m2/g), high-pore volume (0.56-1.65 mL/g), small average porous radius (1.93-3.67 nm) and excellent adsorption properties for small non-polarorganic molecules.2008 Si Guo Yuan. Published by Elsevier B.V. on behalf of Chinese Chemical Society. All rights reserved.

  1. Mixed Waste Management Facility Preliminary Safety Analysis Report. Chapters 1 to 20

    International Nuclear Information System (INIS)

    This document provides information on waste management practices, occupational safety, and a site characterization of the Lawrence Livermore National Laboratory. A facility description, safety engineering analysis, mixed waste processing techniques, and auxiliary support systems are included

  2. Mixed Waste Management Facility Preliminary Safety Analysis Report. Chapters 1 to 20

    Energy Technology Data Exchange (ETDEWEB)

    1994-09-01

    This document provides information on waste management practices, occupational safety, and a site characterization of the Lawrence Livermore National Laboratory. A facility description, safety engineering analysis, mixed waste processing techniques, and auxiliary support systems are included.

  3. Canastota Renewable Energy Facility Project

    Energy Technology Data Exchange (ETDEWEB)

    Blake, Jillian; Hunt, Allen

    2013-12-13

    The project was implemented at the Madison County Landfill located in the Town of Lincoln, Madison County, New York. Madison County has owned and operated the solid waste and recycling facilities at the Buyea Road site since 1974. At the onset of the project, the County owned and operated facilities there to include three separate landfills, a residential solid waste disposal and recycled material drop-off facility, a recycling facility and associated administrative, support and environmental control facilities. This putrescible waste undergoes anaerobic decomposition within the waste mass and generates landfill gas, which is approximately 50% methane. In order to recover this gas, the landfill was equipped with gas collection systems on both the east and west sides of Buyea Road which bring the gas to a central point for destruction. In order to derive a beneficial use from the collected landfill gases, the County decided to issue a Request for Proposals (RFP) for the future use of the generated gas.

  4. CANISTER HANDLING FACILITY DESCRIPTION DOCUMENT

    Energy Technology Data Exchange (ETDEWEB)

    J.F. Beesley

    2005-04-21

    The purpose of this facility description document (FDD) is to establish requirements and associated bases that drive the design of the Canister Handling Facility (CHF), which will allow the design effort to proceed to license application. This FDD will be revised at strategic points as the design matures. This FDD identifies the requirements and describes the facility design, as it currently exists, with emphasis on attributes of the design provided to meet the requirements. This FDD is an engineering tool for design control; accordingly, the primary audience and users are design engineers. This FDD is part of an iterative design process. It leads the design process with regard to the flowdown of upper tier requirements onto the facility. Knowledge of these requirements is essential in performing the design process. The FDD follows the design with regard to the description of the facility. The description provided in this FDD reflects the current results of the design process.

  5. Fuel Handling Facility Description Document

    International Nuclear Information System (INIS)

    The purpose of the facility description document (FDD) is to establish the requirements and their bases that drive the design of the Fuel Handling Facility (FHF) to allow the design effort to proceed to license application. This FDD is a living document that will be revised at strategic points as the design matures. It identifies the requirements and describes the facility design as it currently exists, with emphasis on design attributes provided to meet the requirements. This FDD was developed as an engineering tool for design control. Accordingly, the primary audience and users are design engineers. It leads the design process with regard to the flow down of upper tier requirements onto the facility. Knowledge of these requirements is essential to performing the design process. It trails the design with regard to the description of the facility. This description is a reflection of the results of the design process to date

  6. Facility model for the Los Alamos Plutonium Facility

    International Nuclear Information System (INIS)

    The Los Alamos Plutonium Facility contains more than sixty unit processes and handles a large variety of nuclear materials, including many forms of plutonium-bearing scrap. The management of the Plutonium Facility is supporting the development of a computer model of the facility as a means of effectively integrating the large amount of information required for material control, process planning, and facility development. The model is designed to provide a flexible, easily maintainable facility description that allows the faciltiy to be represented at any desired level of detail within a single modeling framework, and to do this using a model program and data files that can be read and understood by a technically qualified person without modeling experience. These characteristics were achieved by structuring the model so that all facility data is contained in data files, formulating the model in a simulation language that provides a flexible set of data structures and permits a near-English-language syntax, and using a description for unit processes that can represent either a true unit process or a major subsection of the facility. Use of the model is illustrated by applying it to two configurations of a fictitious nuclear material processing line

  7. Siting noxious facilities: A test of the Facility Siting Credo

    Energy Technology Data Exchange (ETDEWEB)

    Kunreuther, H.; Fitzgerald, K. (Univ. of Pennsylvania, Philadelphia (United States)); Aarts, T.D. (Browning Ferris Industries, Houston, TX (United States))

    1993-06-01

    Over the past decade it has become increasingly difficult to site noxious facilities, despite the fact that there is a growing need to do so. To address this problem, a set of guidelines for a fairer, wiser, and more workable siting process -- the Facility Siting Credo -- was developed during a National Facility Siting Workshop in 1990. This paper presents an empirical test of these guidelines. A questionnaire based on the Credo was completed by stakeholders in 29 waste facility siting cases, both successful and unsuccessful, across the United States and Canada. Using an independent determination of outcome (success), a preliminary ranking of the importance of various Credo principles was obtained. The data reveal that establishing trust between the developer and host community is an important factor in facilitating the siting process. The siting process is most likely to be successful when the community perceives the facility design to be appropriate and to satisfy its needs. Public participation also is seen to be an important process variable, particularly if it encourages a view that the facility best meets community needs. Moreover, a siting process where communities volunteer to host facilities in an approach to holds promise for meeting many of these key success criteria. 45 refs., 5 figs., 3 tabs.

  8. The staff competency issue in low-threshold facilities for children and youth.

    OpenAIRE

    KOCOUREK, Jiří

    2012-01-01

    Thesis "The staff competency issue in low-threshold facilities for children and youth" characterized by professional competence of employees and persons of low-threshold facilities for children and youth and describes which competencies really apply in their work and what the broader (social, value and motivational) factors characterizing persons in the area of social practice professionally implemented. The findings can be recommended for use in human resources and the search for new employe...

  9. Characterization monitoring & sensor technology crosscutting program

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-08-01

    The purpose of the Characterization, Monitoring, and Sensor Technology Crosscutting Program (CMST-CP) is to deliver appropriate characterization, monitoring, and sensor technology (CMST) to the OFfice of Waste Management (EM-30), the Office of Environmental Restoration (EM-40), and the Office of Facility Transition and Management (EM-60).

  10. 33 CFR 154.1216 - Facility classification.

    Science.gov (United States)

    2010-07-01

    ... waters near the facility. Navigable waters is defined in 33 CFR part 2.36. (6) The fish, wildlife, and... 33 Navigation and Navigable Waters 2 2010-07-01 2010-07-01 false Facility classification. 154.1216... Vegetable Oils Facilities § 154.1216 Facility classification. (a) The Coast Guard classifies facilities...

  11. 340 waste handling facility interim safety basis

    Energy Technology Data Exchange (ETDEWEB)

    VAIL, T.S.

    1999-04-01

    This document presents an interim safety basis for the 340 Waste Handling Facility classifying the 340 Facility as a Hazard Category 3 facility. The hazard analysis quantifies the operating safety envelop for this facility and demonstrates that the facility can be operated without a significant threat to onsite or offsite people.

  12. 340 waste handling facility interim safety basis

    International Nuclear Information System (INIS)

    This document presents an interim safety basis for the 340 Waste Handling Facility classifying the 340 Facility as a Hazard Category 3 facility. The hazard analysis quantifies the operating safety envelop for this facility and demonstrates that the facility can be operated without a significant threat to onsite or offsite people

  13. Facility effluent monitoring plan for the plutonium uranium extraction facility

    Energy Technology Data Exchange (ETDEWEB)

    Wiegand, D.L.

    1994-09-01

    A facility effluent monitoring plan is required by the US Department of Energy in DOE Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could impact employee or public safety or the environment. This document is prepared using the specific guidelines identified in A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans, WHC-EP-0438-01. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether they are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements. This facility effluent monitoring plan shall ensure long-range integrity of the effluent monitoring systems by requiring an update whenever a new process or operation introduces new hazardous materials or significant radioactive materials. This document must be reviewed annually even if there are no operational changes, and it must be updated at a minimum of every three years.

  14. Facility Effluent Monitoring Plan for the uranium trioxide facility

    Energy Technology Data Exchange (ETDEWEB)

    Lohrasbi, J.; Johnson, D.L. [Westinghouse Hanford Co., Richland, WA (United States); De Lorenzo, D.S. [Los Alamos Technical Associates, Inc., NM (United States)

    1993-12-01

    A facility effluent monitoring plan is required by the US Department of Energy in DOE Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could impact employee or public safety or the environment. This document is prepared using the specific guidelines identified in A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans, WHC-EP-0438-01. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether they are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements. This facility effluent monitoring plan shall ensure long-range integrity of the effluent monitoring systems by requiring an update whenever a new process or operation introduces new hazardous materials or significant radioactive materials. This document must be reviewed annually even if there are no operational changes, and it must be updated at a minimum of every three years.

  15. Facility effluent monitoring plan for the Plutonium Uranium Extraction Facility

    Energy Technology Data Exchange (ETDEWEB)

    Greager, E.M.

    1997-12-11

    A facility effluent monitoring plan is required by the US Department of Energy in DOE Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could impact employee or public safety or the environment. This document is prepared using the specific guidelines identified in A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans, WHC-EP-0438-01. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether these systems are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements. This facility effluent monitoring plan will ensure long-range integrity of the effluent monitoring systems by requiring an update whenever a new process or operation introduces new hazardous materials or significant radioactive materials. This document must be reviewed annually even if there are no operational changes, and it must be updated, at a minimum, every 3 years.

  16. Assisted Living Facilities - MO 2010 Long Term Care Facilities (SHP)

    Data.gov (United States)

    NSGIC GIS Inventory (aka Ramona) — Long Term Care facilities (nursing homes) in Missouri - Data will not be made available for download via MSDIS. Interested parties should send an email inquiry to...

  17. Idaho Waste Vitrification Facilities Project Vitrified Waste Interim Storage Facility

    Energy Technology Data Exchange (ETDEWEB)

    Bonnema, Bruce Edward

    2001-09-01

    This feasibility study report presents a draft design of the Vitrified Waste Interim Storage Facility (VWISF), which is one of three subprojects of the Idaho Waste Vitrification Facilities (IWVF) project. The primary goal of the IWVF project is to design and construct a treatment process system that will vitrify the sodium-bearing waste (SBW) to a final waste form. The project will consist of three subprojects that include the Waste Collection Tanks Facility, the Waste Vitrification Facility (WVF), and the VWISF. The Waste Collection Tanks Facility will provide for waste collection, feed mixing, and surge storage for SBW and newly generated liquid waste from ongoing operations at the Idaho Nuclear Technology and Engineering Center. The WVF will contain the vitrification process that will mix the waste with glass-forming chemicals or frit and turn the waste into glass. The VWISF will provide a shielded storage facility for the glass until the waste can be disposed at either the Waste Isolation Pilot Plant as mixed transuranic waste or at the future national geological repository as high-level waste glass, pending the outcome of a Waste Incidental to Reprocessing determination, which is currently in progress. A secondary goal is to provide a facility that can be easily modified later to accommodate storage of the vitrified high-level waste calcine. The objective of this study was to determine the feasibility of the VWISF, which would be constructed in compliance with applicable federal, state, and local laws. This project supports the Department of Energy’s Environmental Management missions of safely storing and treating radioactive wastes as well as meeting Federal Facility Compliance commitments made to the State of Idaho.

  18. Facility effluent monitoring plan for 242-A evaporator facility

    International Nuclear Information System (INIS)

    A facility effluent monitoring plan is required by the U.S. Department of Energy in DOE Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could affect employee or public safety or the environment. A facility effluent monitoring plan determination was performed during Calendar Year 1991 and the evaluation showed the need for a facility effluent monitoring plan. This document is prepared using the specific guidelines identified in A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans, WHC-EP-0438-1. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether they are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements. This facility effluent monitoring plan shall ensure long-range integrity of the effluent monitoring systems by requiring an update whenever a new process or operation introduces new hazardous materials or significant radioactive materials. This document must be reviewed annually even if there are no operational changes, and it must be updated, as a minimum, every three years

  19. Facility effluent monitoring plan for 242-A evaporator facility

    Energy Technology Data Exchange (ETDEWEB)

    Crummel, G.M.; Gustavson, R.D.

    1995-02-01

    A facility effluent monitoring plan is required by the U.S. Department of Energy in DOE Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could affect employee or public safety or the environment. A facility effluent monitoring plan determination was performed during Calendar Year 1991 and the evaluation showed the need for a facility effluent monitoring plan. This document is prepared using the specific guidelines identified in A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans, WHC-EP-0438-1. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether they are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements. This facility effluent monitoring plan shall ensure long-range integrity of the effluent monitoring systems by requiring an update whenever a new process or operation introduces new hazardous materials or significant radioactive materials. This document must be reviewed annually even if there are no operational changes, and it must be updated, as a minimum, every three years.

  20. The Zwicky Transient Facility

    Science.gov (United States)

    Kulkarni, Shrinivas R.

    2016-01-01

    The Zwicky Transient Facility (ZTF) has been designed with a singular focus: a systematic exploration of the night sky at a magnitude level well suited for spectral classification and follow up with the existing class of 4-m to 10-m class telescopes. ZTF is the successor to the Palomar Transient Factory (PTF). The discovery engine for ZTF is a 47 square degree camera (realized through 16 e2V monolithic CCDs) that fills the entire focal plane of the 48-inch Oschin telescope of the Palomar Observatory. Single 30-s epoch sensitivity is about 20.5 in g and R bands. The Infarared Processing & Analysis Center (IPAC) is the data center for ZTF. ZTF is a public-private partnership with equal contributions from a consortium of world-wide partners and an NSF MSIP grant. Forty percent of ZTF time is set aside for two major community surveys: a 3-day cadence survey of high latitudes (to mimic LSST) and a time domain survey of the entire Northern Galactic plane. We expect first light in February 2017 and begin a 3-year survey starting summer of 2017. The first year will be spent on building up deep reference images of the sky (a must for transient surveys). During the second year IPAC will deliver near archival quality photometric products within 12 hours of observations. By comparison to reference images photometric alerts will be sent out. Year 3 will see the near real-time release of image differencing products. A Community Science Advisory Committee (CSAC), chaired by S. Ridgway (NOAO), has been set up to both advise the PI and to ensure that the US community's interests are well served. Astronomers interested in getting a head start on ZTF may wish to peruse the data releases from PTF. Young people (or young at heart) may wish to attend the annual summer school on PTF/ZTF (August, Caltech campus). The Principal Investigator (PI) for the project is S. Kulkarni and the Project Scientist is Eric Bellm.For further details please consult http://www.ptf.caltech.edu/ztf

  1. Remote experimental facility to solidify SRP high-level waste

    International Nuclear Information System (INIS)

    Small-scale equipment has been developed and installed in a remotely operated experimental facility at the Savannah River Laboratory (SRL) to study immobilization of radioactive waste in glass. The facility has been in operation for nine months. During this period, two 25-liter batches of high-level waste from different SRP waste storage tanks were processed. The waste was boiled in sodium hydroxide to dissolve alumina trihydrate, washed with water to remove soluble salts, dried in a fluid-bed dryer, and vitrified in a joule-heated melter. Off-gases from the melter were collected for characterization

  2. Health physics manual of good practices for tritium facilities

    International Nuclear Information System (INIS)

    The purpose of this document is to provide written guidance defining the generally accepted good practices in use at Department of Energy (DOE) tritium facilities. A open-quotes good practiceclose quotes is an action, policy, or procedure that enhances the radiation protection program at a DOE site. The information selected for inclusion in this document should help readers achieve an understanding of the key radiation protection issues at tritium facilities and provide guidance as to what characterizes excellence from a radiation protection point of view. The ALARA (As Low as Reasonable Achievable) program at DOE sites should be based, in part, on following the good practices that apply to their operations

  3. Tank vapor sampling and analysis data package for tank 241-C-106 waste retrieval sluicing system process test phase III

    Energy Technology Data Exchange (ETDEWEB)

    LOCKREM, L.L.

    1999-08-13

    This data package presents sampling data and analytical results from the March 28, 1999, vapor sampling of Hanford Site single-shell tank 241-C-106 during active sluicing. Samples were obtained from the 296-C-006 ventilation system stack and ambient air at several locations. Characterization Project Operations (CPO) was responsible for the collection of all SUMMATM canister samples. The Special Analytical Support (SAS) vapor team was responsible for the collection of all triple sorbent trap (TST), sorbent tube train (STT), polyurethane foam (PUF), and particulate filter samples collected at the 296-C-006 stack. The SAS vapor team used the non-electrical vapor sampling (NEVS) system to collect samples of the air, gases, and vapors from the 296-C-006 stack. The SAS vapor team collected and analyzed these samples for Lockheed Martin Hanford Corporation (LMHC) and Tank Waste Remediation System (TWRS) in accordance with the sampling and analytical requirements specified in the Waste Retrieval Sluicing System Vapor Sampling and Analysis Plan (SAP) for Evaluation of Organic Emissions, Process Test Phase III, HNF-4212, Rev. 0-A, (LMHC, 1999). All samples were stored in a secured Radioactive Materials Area (RMA) until the samples were radiologically released and received by SAS for analysis. The Waste Sampling and Characterization Facility (WSCF) performed the radiological analyses. The samples were received on April 5, 1999.

  4. Site characterization plan:

    International Nuclear Information System (INIS)

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

  5. Site characterization plan:

    International Nuclear Information System (INIS)

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

  6. EPA Facility Registry Service (FRS): RBLC

    Data.gov (United States)

    U.S. Environmental Protection Agency — This web feature service contains location and facility identification information from EPA's Facility Registry Service (FRS) for the subset of facilities that link...

  7. EPA Facility Registry Service (FRS): SDWIS

    Data.gov (United States)

    U.S. Environmental Protection Agency — This web feature service contains location and facility identification information from EPA's Facility Registry Service (FRS) for the subset of facilities that link...

  8. EPA Facility Registry Service (FRS): RMP

    Data.gov (United States)

    U.S. Environmental Protection Agency — This web feature service contains location and facility identification information from EPA's Facility Registry Service (FRS) for the subset of facilities that link...

  9. EPA Facility Registry Service (FRS): TRI

    Data.gov (United States)

    U.S. Environmental Protection Agency — This web feature service contains location and facility identification information from EPA's Facility Registry Service (FRS) for the subset of facilities that link...

  10. EPA Facility Registry Service (FRS): BRAC

    Data.gov (United States)

    U.S. Environmental Protection Agency — This web feature service contains location and facility identification information from EPA's Facility Registry Service (FRS) for the subset of facilities that link...

  11. 48 CFR 970.3770 - Facilities management.

    Science.gov (United States)

    2010-10-01

    ... 48 Federal Acquisition Regulations System 5 2010-10-01 2010-10-01 false Facilities management. 970... REGULATIONS DOE MANAGEMENT AND OPERATING CONTRACTS Facilities Management Contracting 970.3770 Facilities management....

  12. Skilled nursing and rehabilitation facilities - choosing

    Science.gov (United States)

    ... page: //medlineplus.gov/ency/patientinstructions/000436.htm Skilled nursing and rehabilitation facilities - choosing To use the sharing ... you may need to go to a skilled nursing or rehabilitation facility . Skilled nursing facilities provide care ...

  13. Geophysical Processes - Erosion & Sediment Control Facilities

    Data.gov (United States)

    NSGIC GIS Inventory (aka Ramona) — An Erosion and Sediment Control Facility is a DEP primary facility type related to the Water Pollution Control program. The following sub-facility types related to...

  14. EPA Facility Registry Service (FRS): OIL

    Data.gov (United States)

    U.S. Environmental Protection Agency — This dataset contains location and facility identification information from EPA's Facility Registry Service (FRS) for the subset of facilities that link to the Oil...

  15. EPA Facility Registry Service (FRS): RADINFO

    Data.gov (United States)

    U.S. Environmental Protection Agency — This web feature service contains location and facility identification information from EPA's Facility Registry Service (FRS) for the subset of facilities that link...

  16. EPA Facility Registry Service (FRS): NCDB

    Data.gov (United States)

    U.S. Environmental Protection Agency — This web feature service contains location and facility identification information from EPA's Facility Registry Service (FRS) for the subset of facilities that link...

  17. EPA Facility Registry Service (FRS): CAMDBS

    Data.gov (United States)

    U.S. Environmental Protection Agency — This web feature service contains location and facility identification information from EPA's Facility Registry Service (FRS) for the subset of facilities that link...

  18. EPA Facility Registry System (FRS): NCES

    Data.gov (United States)

    U.S. Environmental Protection Agency — This web feature service contains location and facility identification information from EPA's Facility Registry System (FRS) for the subset of facilities that link...

  19. EPA Facility Registry Service (FRS): NEI

    Data.gov (United States)

    U.S. Environmental Protection Agency — This web feature service contains location and facility identification information from EPA's Facility Registry Service (FRS) for the subset of facilities that link...

  20. EPA Facility Registry Service (FRS): BIA

    Data.gov (United States)

    U.S. Environmental Protection Agency — This web feature service contains location and facility identification information from EPA's Facility Registry Service (FRS) for the subset of facilities that link...