WorldWideScience

Sample records for activation analysis facility

  1. High-capacity neutron activation analysis facility

    International Nuclear Information System (INIS)

    A high-capacity neutron activation analysis facility, the Reactor Activation Facility, was designed and built and has been in operation for about a year at one of the Savannah River Plant's production reactors. The facility determines uranium and about 19 other elements in hydrogeochemical samples collected in the National Uranium Resource Evaluation program, which is sponsored and funded by the United States Department of Energy, Grand Junction Office. The facility has a demonstrated average analysis rate of over 10,000 samples per month, and a peak rate of over 16,000 samples per month. Uranium is determined by cyclic activation and delayed neutron counting of the U-235 fission products; other elements are determined from gamma-ray spectra recorded in subsequent irradiation, decay, and counting steps. The method relies on the absolute activation technique and is highly automated for round-the-clock unattended operation

  2. KFUPM fast neutron activation analysis facility

    International Nuclear Information System (INIS)

    A newly established Fast Neutron Activation Analysis facility at the Energy Research Laboratory is described. The facility mainly consists of a fast neutron irradiation station and a gamma ray counting station. Both stations are connected by a fast pneumatic sample transfer system which transports the sample from the irradiation station to the counting station in a short time of 3 s. The fast neutron activation analysis facility has been tested by measuring the 27A(n, α)24Na and 115In(n, n')115mIn cross sections at 14.8 and 2.5 MeV neutron energies, respectively. Within the experimental uncertainties, the measured cross sections for these elements agree with the published values. (orig.)

  3. A description of the BNL active surface analysis facility

    International Nuclear Information System (INIS)

    Berkeley Nuclear Laboratories has a responsibility for the assessment of radioactive specimens arising both from post irradiation examination of power reactor components and structures and experimental programmes concerned with fission and activation product transport. Existing analytical facilities have been extended with the commissioning of an active surface analysis instrument (XSAM 800pci, Kratos Analytical). Surface analysis involves the characterisation of the outer few atomic layers of a solid surface/interface whose chemical composition and electronic structure will probably be different from the bulk. The new instrument consists three interconnected chambers positioned in series; comprising of a high vacuum sample introduction chamber, an ultra-high vacuum sample treatment/fracture chamber and an ultra-high vacuum sample analysis chamber. The sample analysis chamber contains the electron, X-ray and ion-guns and the electron and ion detectors necessary for performing X-ray photoelectron spectroscopy, scanning Auger microscopy and secondary-ion mass spectroscopy. The chamber also contains a high stability manipulator to enable sub-micron imaging of specimens to be achieved and provide sample heating and cooling between - 180 and 6000C. (author)

  4. Software for a measuring facility for activation analysis

    International Nuclear Information System (INIS)

    A software package has been developed for an APPLE P.C. The programs are intended to control an automated measuring station for photon activation analysis at GELINA, the linear accelerator of C.B.N.M. at Geel (Belgium). They allow to set-up a measuring scheme, to execute it under computer control, to accumulate and store 2 K-spectra using a built-in ADC and to output the results as listings, plots or evaluated reports

  5. Self-sustainability of a research reactor facility with neutron activation analysis

    International Nuclear Information System (INIS)

    Long-term self-sustainability of a small reactor facility is possible because there is a large demand for non-destructive chemical analysis of bulk materials that can only be achieved with neutron activation analysis (NAA). The Ecole Polytechnique Montreal SLOWPOKE Reactor Facility has achieved self-sustainability for over twenty years, benefiting from the extreme reliability, ease of use and stable neutron flux of the SLOWPOKE reactor. The industrial clientele developed slowly over the years, mainly because of research users of the facility. A reliable NAA service with flexibility, high accuracy and fast turn-around time was achieved by developing an efficient NAA system, using a combination of the relative and k0 standardisation methods. The techniques were optimized to meet the specific needs of the client, such as low detection limit or high accuracy at high concentration. New marketing strategies are presented, which aim at a more rapid expansion. (author)

  6. Prompt gamma neutron activation analysis facility at the RA-6 research reactor

    International Nuclear Information System (INIS)

    A prompt gamma neutron activation activation analysis facility was developed at the 500 kw thermal power RA-6 research reactor of the Bariloche Atomic Center, Argentina.This facility consist of a radial beam port with external positioning of the sample.The gamma radiation is reduced by a bismuth filter placed inside the extraction tube and the beam diameter is limited by a set of two collimators up to 5 cm.The neutron flux at the sample position is 7 106 n/cm2s with a Cadmium ratio of 20/1.The gamma detector is a 50 % efficiency type p HPGe rounded by a NaI(Tl) for Compton suppressioning.The gamma spectra is measured through 0 to 8.5 MeV.The background have counting rate of 350 cps without sample. In this work is shown the efficiency curve, the calculed sensibilities and the lower detection limits for B, Cd, Sm, Gd, H, Cl, Hg, Eu, Ti, Ag, Au, Mo. The RA-6's PGNAA facility is fully working, although the analytic capacity is under improvement

  7. Design of Stopper of Prompt Gamma Neutron Activation Analysis Facility at China Advanced Research Reactor

    Institute of Scientific and Technical Information of China (English)

    2011-01-01

    The PGNAA facility consists of the filtered collimated neutron beam, the shielding of the whole facility, the control system, the detecting equipment and the data acquisition and analysis system. The neutron beam is filtered by a mono-crystalline bismuth filter,

  8. Development of a prompt gamma activation analysis facility using diffracted polychromatic neutron beam

    CERN Document Server

    Byun, S H; Choi, H D

    2002-01-01

    A prompt gamma activation analysis facility has recently been developed at Hanaro, the 24 MW research reactor in the Korea Atomic Energy Research Institute. Polychromatic thermal neutrons are extracted by setting pyrolytic graphite crystals at a Bragg angle of 45 deg. . The detection system comprises a large single n-type HPGe detector, signal electronics and a fast ADC. Neutron beam characterization was performed both theoretically and experimentally. The neutron flux was measured to be 7.9x10 sup 7 n/cm sup 2 s in a 1x1 cm sup 2 beam area at the sample position with a uniformity of 12%. The corresponding Cd-ratio for gold was found to be 266. The beam quality was compared with other representative thermal neutron prompt gamma activation analysis. The detection efficiency was calibrated up to 11 MeV using a set of radionuclides and the (n,gamma) reactions of N and Cl. Finally, the sensitivities and the detection limits were obtained for several elements.

  9. Development of a prompt gamma activation analysis facility using diffracted polychromatic neutron beam

    International Nuclear Information System (INIS)

    A prompt gamma activation analysis facility has recently been developed at Hanaro, the 24 MW research reactor in the Korea Atomic Energy Research Institute. Polychromatic thermal neutrons are extracted by setting pyrolytic graphite crystals at a Bragg angle of 45 deg. . The detection system comprises a large single n-type HPGe detector, signal electronics and a fast ADC. Neutron beam characterization was performed both theoretically and experimentally. The neutron flux was measured to be 7.9x107 n/cm2 s in a 1x1 cm2 beam area at the sample position with a uniformity of 12%. The corresponding Cd-ratio for gold was found to be 266. The beam quality was compared with other representative thermal neutron prompt gamma activation analysis. The detection efficiency was calibrated up to 11 MeV using a set of radionuclides and the (n,γ) reactions of N and Cl. Finally, the sensitivities and the detection limits were obtained for several elements

  10. 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...

  11. 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.

  12. Sample registration software for process automation in the Neutron Activation Analysis (NAA) Facility in Malaysia nuclear agency

    Science.gov (United States)

    Rahman, Nur Aira Abd; Yussup, Nolida; Salim, Nazaratul Ashifa Bt. Abdullah; Ibrahim, Maslina Bt. Mohd; Mokhtar, Mukhlis B.; Soh@Shaari, Syirrazie Bin Che; Azman, Azraf B.; Ismail, Nadiah Binti

    2015-04-01

    Neutron Activation Analysis (NAA) had been established in Nuclear Malaysia since 1980s. Most of the procedures established were done manually including sample registration. The samples were recorded manually in a logbook and given ID number. Then all samples, standards, SRM and blank were recorded on the irradiation vial and several forms prior to irradiation. These manual procedures carried out by the NAA laboratory personnel were time consuming and not efficient. Sample registration software is developed as part of IAEA/CRP project on `Development of Process Automation in the Neutron Activation Analysis (NAA) Facility in Malaysia Nuclear Agency (RC17399)'. The objective of the project is to create a pc-based data entry software during sample preparation stage. This is an effective method to replace redundant manual data entries that needs to be completed by laboratory personnel. The software developed will automatically generate sample code for each sample in one batch, create printable registration forms for administration purpose, and store selected parameters that will be passed to sample analysis program. The software is developed by using National Instruments Labview 8.6.

  13. Sample registration software for process automation in the Neutron Activation Analysis (NAA) Facility in Malaysia nuclear agency

    International Nuclear Information System (INIS)

    Neutron Activation Analysis (NAA) had been established in Nuclear Malaysia since 1980s. Most of the procedures established were done manually including sample registration. The samples were recorded manually in a logbook and given ID number. Then all samples, standards, SRM and blank were recorded on the irradiation vial and several forms prior to irradiation. These manual procedures carried out by the NAA laboratory personnel were time consuming and not efficient. Sample registration software is developed as part of IAEA/CRP project on ‘Development of Process Automation in the Neutron Activation Analysis (NAA) Facility in Malaysia Nuclear Agency (RC17399)’. The objective of the project is to create a pc-based data entry software during sample preparation stage. This is an effective method to replace redundant manual data entries that needs to be completed by laboratory personnel. The software developed will automatically generate sample code for each sample in one batch, create printable registration forms for administration purpose, and store selected parameters that will be passed to sample analysis program. The software is developed by using National Instruments Labview 8.6

  14. Development of Pneumatic Transfer Irradiation Facility (PTS no.2) for Neutron Activation Analysis at HANARO Research Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Chung, Y. S.; Moon, J. H.; Kim, S. H.; Sun, G. M.; Baek, S. Y.; Kim, H. R.; Kim, Y. J

    2008-03-15

    A pneumatic transfer irradiation system (PTS) is one of the most important facilities used during neutron irradiation of a target material for instrumental neutron activation analysis (INAA) in a research reactor. In particular, a fast pneumatic transfer system is essential for the measurement of a short half-life nuclide and a delayed neutron counting system. The pneumatic transfer irradiation system (PTS no.2) involving a manual system and an automatic system for delayed neutron activation analysis (DNAA) were reconstructed with new designs of a functional improvement at the HANARO research reactor in 2006. In this technical report, the conception, design, operation and control of PTS no.2 was described. Also the experimental results and the characteristic parameters measured by a mock-up test, a functional operation test and an irradiation test of these systems, such as the transfer time of irradiation capsule, automatic operation control by personal computer, delayed neutron counting system, the different neutron flux, the temperature of the irradiation position with an irradiation time, the radiation dose rate when the rabbit is returned, etc. are reported to provide a user information as well as a reactor's management and safety.

  15. 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

  16. Chemical Analysis Facility

    Data.gov (United States)

    Federal Laboratory Consortium — FUNCTION: Uses state-of-the-art instrumentation for qualitative and quantitative analysis of organic and inorganic compounds, and biomolecules from gas, liquid, and...

  17. Development of Pneumatic Transfer Irradiation Facility (PTS no.1) for Neutron Activation Analysis at HANARO Research Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Chung, Y. S.; Moon, J. H.; Kim, S. H.; Sun, G. M.; Baek, S. Y.; Kim, H. R.; Kim, Y. J

    2008-03-15

    A pneumatic transfer system (PTS) is one of the most important facilities used during neutron irradiation of a target material for instrumental neutron activation analysis (INAA) in a research reactor. In particular, a fast pneumatic transfer system is essential for the measurement of a short half-life nuclide and a delayed neutron counting system. The pneumatic transfer system (PTS no.1) involving a manual system and an semiautomatic system were reconstructed with new designs of a functional improvement at the HANARO research reactor in 2006. In this technical report, the conception, design, operation and control of these system (PTS no.1) was described. Also the experimental results and the characteristic parameters measured by a mock-up test, a functional operation test and an irradiation test of these systems, such as the transfer time of irradiation capsule, the different neutron flux, the temperature of the irradiation position with an irradiation time, the radiation dose rate when the rabbit is returned, etc. are reported to provide a user information as well as a reactor's management and safety.

  18. Development of Pneumatic Transfer Irradiation Facility (PTS no.3) for Neutron Activation Analysis at HANARO Research Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Chung, Y. S.; Moon, J. H.; Kim, S. H.; Sun, G. M.; Baek, S. Y.; Kim, H. R.; Kim, Y. J

    2008-04-15

    A pneumatic transfer system (PTS) is one of the most important facilities used during neutron irradiation of a target material for instrumental neutron activation analysis (INAA) in a research reactor. In particular, a fast pneumatic transfer system is essential for the measurement of a short half-life nuclide. The pneumatic transfer irradiation system (PTS no.3) involving a manual system and an semi-automatic system were reconstructed with new designs of a functional improvement at the HANARO research reactor and NAA laboratory of RI building in 2006. In this technical report, the design, operation and control of these system (PTS no.3) was described. Also the experimental results and the characteristic parameters measured from a functional operation test and an irradiation test of these systems, such as the transfer time of irradiation capsule, the different neutron flux, the temperature of the irradiation position with an irradiation time, the radiation dose rate when the rabbit is returned, etc. are reported to provide a user information as well as a reactor's management and safety.

  19. Design and Analysis Facility

    Data.gov (United States)

    Federal Laboratory Consortium — Provides engineering design of aircraft components, subsystems and installations using Pro/E, Anvil 1000, CADKEY 97, AutoCAD 13. Engineering analysis tools include...

  20. Quality Assurance Project Plan for Facility Effluent Monitoring Plan activities

    Energy Technology Data Exchange (ETDEWEB)

    Frazier, T.P.

    1994-10-20

    This Quality Assurance Project Plan addresses the quality assurance requirements for the activities associated with the Facility Effluent Monitoring Plans, which are part of the overall Hanford Site Environmental Protection Plan. This plan specifically applies to the sampling and analysis activities and continuous monitoring performed for all Facility Effluent Monitoring Plan activities conducted by Westinghouse Hanford Company. It is generic in approach and will be implemented in conjunction with the specific requirements of the individual Facility Effluent Monitoring Plans.

  1. Addendum to the composite analysis for the E-Area Vaults and Saltstone Disposal Facilities

    International Nuclear Information System (INIS)

    This report documents the composite analysis performed on the two active SRS low-level radioactive waste disposal facilities. The facilities are the Z-Area Saltstone Disposal Facility and the E-Area Vaults Disposal Facility

  2. Addendum to the composite analysis for the E-Area Vaults and Saltstone Disposal Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Cook, J.R.

    2000-03-13

    This report documents the composite analysis performed on the two active SRS low-level radioactive waste disposal facilities. The facilities are the Z-Area Saltstone Disposal Facility and the E-Area Vaults Disposal Facility.

  3. Composite analysis E-area vaults and saltstone disposal facilities

    International Nuclear Information System (INIS)

    This report documents the Composite Analysis (CA) performed on the two active Savannah River Site (SRS) low-level radioactive waste (LLW) disposal facilities. The facilities are the Z-Area Saltstone Disposal Facility and the E-Area Vaults (EAV) Disposal Facility. The analysis calculated potential releases to the environment from all sources of residual radioactive material expected to remain in the General Separations Area (GSA). The GSA is the central part of SRS and contains all of the waste disposal facilities, chemical separations facilities and associated high-level waste storage facilities as well as numerous other sources of radioactive material. The analysis considered 114 potential sources of radioactive material containing 115 radionuclides. The results of the CA clearly indicate that continued disposal of low-level waste in the saltstone and EAV facilities, consistent with their respective radiological performance assessments, will have no adverse impact on future members of the public

  4. Composite analysis E-area vaults and saltstone disposal facilities

    Energy Technology Data Exchange (ETDEWEB)

    Cook, J.R.

    1997-09-01

    This report documents the Composite Analysis (CA) performed on the two active Savannah River Site (SRS) low-level radioactive waste (LLW) disposal facilities. The facilities are the Z-Area Saltstone Disposal Facility and the E-Area Vaults (EAV) Disposal Facility. The analysis calculated potential releases to the environment from all sources of residual radioactive material expected to remain in the General Separations Area (GSA). The GSA is the central part of SRS and contains all of the waste disposal facilities, chemical separations facilities and associated high-level waste storage facilities as well as numerous other sources of radioactive material. The analysis considered 114 potential sources of radioactive material containing 115 radionuclides. The results of the CA clearly indicate that continued disposal of low-level waste in the saltstone and EAV facilities, consistent with their respective radiological performance assessments, will have no adverse impact on future members of the public.

  5. Active use of urban park facilities

    DEFF Research Database (Denmark)

    Lindberg, Michael; Schipperijn, Jasper

    2015-01-01

    Abstract Urban green spaces (UGS), and more specific a higher number of facilities in UGS, have been positively associated with physical activity (PA). However, more detailed studies of which facilities generate high levels of PA, for which type of users, are relevant as existing knowledge is sca...

  6. Quality Assurance Project Plan for Facility Effluent Monitoring Plan activities

    International Nuclear Information System (INIS)

    This Quality Assurance Project Plan addresses the quality assurance requirements for the Facility Monitoring Plans of the overall site-wide environmental monitoring plan. This plan specifically applies to the sampling and analysis activities and continuous monitoring performed for all Facility Effluent Monitoring Plan activities conducted by Westinghouse Hanford Company. It is generic in approach and will be implemented in conjunction with the specific requirements of individual Facility Effluent Monitoring Plans. This document is intended to be a basic road map to the Facility Effluent Monitoring Plan documents (i.e., the guidance document for preparing Facility Effluent Monitoring Plans, Facility Effluent Monitoring Plan determinations, management plan, and Facility Effluent Monitoring Plans). The implementing procedures, plans, and instructions are appropriate for the control of effluent monitoring plans requiring compliance with US Department of Energy, US Environmental Protection Agency, state, and local requirements. This Quality Assurance Project Plan contains a matrix of organizational responsibilities, procedural resources from facility or site manuals used in the Facility Effluent Monitoring Plans, and a list of the analytes of interest and analytical methods for each facility preparing a Facility Effluent Monitoring Plan. 44 refs., 1 figs., 2 tabs

  7. The Pacific Northwest story. [imagery analysis facilities

    Science.gov (United States)

    Johnson, K. A.; Schrumpf, B. J.; Krebs, L.

    1981-01-01

    The establishment of image analysis facilities for the operational utilization of LANDSAT data in Idaho, Oregon, and Washington is discussed. The hardware and software resources are described for each facility along with the range of services.

  8. Activation analysis

    International Nuclear Information System (INIS)

    The neutron activation analysis, which appears to be in limits for further advance, is the most suitable for providing information on the principal as well as the microcomponents in any sample of solid form. Then, instrumental activation analysis is capable of determination of far many elements in various samples. Principally on the neutron activation analysis, the following are described in literature survey from 1982 to middle 1984: bibliography, review, data collection, etc.; problems in spectral analysis and measurement; activation analysis with neutrons; charged particle and photo-nucleus reactions; chemical separation, isotopic dilution activation analysis; molecular activation analysis; standard materials; life and its relation samples; environmental, food, court trial and archaeological samples; space and earth sciences. (Mori, K.)

  9. 303-K Storage Facility report on FY98 closure activities

    Energy Technology Data Exchange (ETDEWEB)

    Adler, J.G.

    1998-07-17

    This report summarizes and evaluates the decontamination activities, sampling activities, and sample analysis performed in support of the closure of the 303-K Storage Facility. The evaluation is based on the validated data included in the data validation package (98-EAP-346) for the 303-K Storage Facility. The results of this evaluation will be used for assessing contamination for the purpose of closing the 303-K Storage Facility as described in the 303-K Storage Facility Closure Plan, DOE/RL-90-04. The closure strategy for the 303-K Storage Facility is to decontaminate the interior of the north half of the 303-K Building to remove known or suspected dangerous waste contamination, to sample the interior concrete and exterior soils for the constituents of concern, and then to perform data analysis, with an evaluation to determine if the closure activities and data meet the closure criteria. The closure criteria for the 303-K Storage Facility is that the concentrations of constituents of concern are not present above the cleanup levels. Based on the evaluation of the decontamination activities, sampling activities, and sample data, determination has been made that the soils at the 303-K Storage Facility meet the cleanup performance standards (WMH 1997) and can be clean closed. The evaluation determined that the 303-K Building cannot be clean closed without additional closure activities. An additional evaluation will be needed to determine the specific activities required to clean close the 303-K Storage Facility. The radiological contamination at the 303-K Storage Facility is not addressed by the closure strategy.

  10. Cold Vacuum Drying Facility hazard analysis report

    Energy Technology Data Exchange (ETDEWEB)

    Krahn, D.E.

    1998-02-23

    This report describes the methodology used in conducting the Cold Vacuum Drying Facility (CVDF) hazard analysis to support the CVDF phase 2 safety analysis report (SAR), and documents the results. The hazard analysis was performed in accordance with DOE-STD-3009-94, Preparation Guide for US Department of Energy Nonreactor Nuclear Facility Safety Analysis Reports, and implements the requirements of US Department of Energy (DOE) Order 5480.23, Nuclear Safety Analysis Reports.

  11. Cold Vacuum Drying Facility hazard analysis report

    International Nuclear Information System (INIS)

    This report describes the methodology used in conducting the Cold Vacuum Drying Facility (CVDF) hazard analysis to support the CVDF phase 2 safety analysis report (SAR), and documents the results. The hazard analysis was performed in accordance with DOE-STD-3009-94, Preparation Guide for US Department of Energy Nonreactor Nuclear Facility Safety Analysis Reports, and implements the requirements of US Department of Energy (DOE) Order 5480.23, Nuclear Safety Analysis Reports

  12. 340 Waste handling Facility Hazard Categorization and Safety Analysis

    International Nuclear Information System (INIS)

    The analysis presented in this document provides the basis for categorizing the facility as less than Hazard Category 3. The final hazard categorization for the deactivated 340 Waste Handling Facility (340 Facility) is presented in this document. This hazard categorization was prepared in accordance with DOE-STD-1 027-92, Change Notice 1, Hazard Categorization and Accident Analysis Techniques for Compliance with Doe Order 5480.23, Nuclear Safety Analysis Reports. The analysis presented in this document provides the basis for categorizing the facility as less than Hazard Category (HC) 3. Routine nuclear waste receiving, storage, handling, and shipping operations at the 340 Facility have been deactivated, however, the facility contains a small amount of radioactive liquid and/or dry saltcake in two underground vault tanks. A seismic event and hydrogen deflagration were selected as bounding accidents. The generation of hydrogen in the vault tanks without active ventilation was determined to achieve a steady state volume of 0.33%, which is significantly less than the lower flammability limit of 4%. Therefore, a hydrogen deflagration is not possible in these tanks. The unmitigated release from a seismic event was used to categorize the facility consistent with the process defined in Nuclear Safety Technical Position (NSTP) 2002-2. The final sum-of-fractions calculation concluded that the facility is less than HC 3. The analysis did not identify any required engineered controls or design features. The Administrative Controls that were derived from the analysis are: (1) radiological inventory control, (2) facility change control, and (3) Safety Management Programs (SMPs). The facility configuration and radiological inventory shall be controlled to ensure that the assumptions in the analysis remain valid. The facility commitment to SMPs protects the integrity of the facility and environment by ensuring training, emergency response, and radiation protection. The full scale

  13. Research activities by INS cyclotron facility

    International Nuclear Information System (INIS)

    Research activities made by the cyclotron facility and the related apparatuses at Institute for Nuclear Study (INS), University of Tokyo, have been reviewed in terms of the associated scientific publications. This publication list, which is to be read as a continuation of INS-Rep.-608 (October, 1986), includes experimental works on low-energy nuclear physics, accelerator technology, instrumental developments, radiation physics and other applications in interdisciplinary fields. The publications are classified into the following four categories. (A) : Internal reports published in INS. (B) : Publications in international scientific journals on experimental research works done by the cyclotron facility and the related apparatuses at INS. Those made by outside users are also included. (C) : Publications in international scientific journals on experimental low-energy nuclear physics, which have been done by the staff of INS Nuclear Physics Division using facilities outside INS. (D) : Contributions to international conferences. (author)

  14. Europlanet Research Infrastructure: Planetary Sample Analysis Facilities

    Science.gov (United States)

    Cloquet, C.; Mason, N. J.; Davies, G. R.; Marty, B.

    2008-09-01

    EuroPlanet The Europlanet Research Infrastructure consortium funded under FP7 aims to provide the EU Planetary Science community greater access for to research infrastructure. A series of networking and outreach initiatives will be complimented by joint research activities and the formation of three Trans National Access distributed service laboratories (TNA's) to provide a unique and comprehensive set of analogue field sites, laboratory simulation facilities, and extraterrestrial sample analysis tools. Here we report on the infrastructure that comprises the third TNA: Planetary Sample Analysis Facilities. The modular infrastructure represents a major commitment of analytical instrumentation by three institutes and together forms a state-of-the-art analytical facility of unprecedented breadth. These centres perform research in the fields of geochemistry and cosmochemistry, studying fluids and rocks in order to better understand the keys cof the universe. Europlanet Research Infrastructure Facilities: Ion Probe facilities at CRPG and OU The Cameca 1270 Ion microprobe is a CNRS-INSU national facility. About a third of the useful analytical time of the ion probe (about 3 months each year) is allocated to the national community. French scientists have to submit their projects to a national committee for selection. The selected projects are allocated time in the following 6 months twice a year. About 15 to 20 projects are run each year. There are only two such instruments in Europe, with cosmochemistry only performed at CRPG. Different analyses can be performed on a routine basis, such as U-Pb dating on Zircon, Monazite or Pechblende, Li, B, C, O, Si isotopic ratios determination on different matrix, 26Al, 60Fe extinct radioactivity ages, light and trace elements contents . The NanoSIMS 50L - producing element or isotope maps with a spatial resolution down to ≈50nm. This is one of the cornerstone facilities of UKCAN, with 75% of available instrument time funded and

  15. Safety analysis report for the Waste Storage Facility. Revision 2

    Energy Technology Data Exchange (ETDEWEB)

    Bengston, S.J.

    1994-05-01

    This safety analysis report outlines the safety concerns associated with the Waste Storage Facility located in the Radioactive Waste Management Complex at the Idaho National Engineering Laboratory. The three main objectives of the report are: define and document a safety basis for the Waste Storage 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.

  16. DEMO Active Maintenance Facility concept progress 2012

    Energy Technology Data Exchange (ETDEWEB)

    Thomas, Justin, E-mail: Justin.Thomas@ccfe.ac.uk [Euratom/CCFE Fusion Association, Culham Science Centre, Abingdon OX14 3DB (United Kingdom); Loving, Antony; Crofts, Oliver; Morgan, Robert [Euratom/CCFE Fusion Association, Culham Science Centre, Abingdon OX14 3DB (United Kingdom); Harman, Jon [EFDA, PPP and T, Boltzmannstraße 2, 85748 Garching (Germany)

    2014-10-15

    The DEMO Active Maintenance Facility (AMF) would be used for the storage, handling and processing of In-Vessel Components (IVC) throughout their time on site, the only exception being the time that they are installed in the vessel. It is anticipated that all handling operations associated with used components will have to be carried out using remote handling techniques. During plasma operations the In-Vessel Components are exposed to high levels of neutron activation. This activation results in high radiation dose rates and decay heating. This presents a significant problem for Remote Handling Equipment (RHE) in the AMF. The high dose rates require the equipment to be sufficiently radiation tolerant to allow it to work reliably for long periods. The decay heating requires forced cooling of newly removed IVC's while they are in storage. The duration of the storage is dependent on the decay heating reducing to a level that has been nominally set at <50 °C without active cooling in room temperature air. This paper summarises the progress made in 2012 on the conceptual design of the AMF and its facilities. The layout and proposed function of the main areas will be described along with the principles applied. The design of the AMF has evolved from a simple representation of the required facilities in 2011 to a concept that can be developed to support maintenance of DEMO.

  17. Buildings, fields of activity, testing facilities

    International Nuclear Information System (INIS)

    Since 1969 the activities of the Materialpruefungsanstalt Stuttgart (MPA) have grown quickly as planned, especially in the field of reactor safety research, which made it necessary to increase the staff to approximately 165 members, to supplement the machines and equipment and to extend the fields of activities occasioning a further departmental reorganization. At present the MPA has the following departments: 1. Teaching (materials testing, materials science and strength of materials) 2. Materials and Welding Technology 3. Materials Science and General Materials Testing with Tribology 4. Design and Strength 5. Creep and Fatigue Testing 6. Central Facilities 7. Vessel and Component Testing. (orig./RW)

  18. Usability Testing and Analysis Facility (UTAF)

    Science.gov (United States)

    Wong, Douglas T.

    2010-01-01

    This slide presentation reviews the work of the Usability Testing and Analysis Facility (UTAF) at NASA Johnson Space Center. It is one of the Space Human Factors Laboratories in the Habitability and Human Factors Branch (SF3) at NASA Johnson Space Center The primary focus pf the UTAF is to perform Human factors evaluation and usability testing of crew / vehicle interfaces. The presentation reviews the UTAF expertise and capabilities, the processes and methodologies, and the equipment available. It also reviews the programs that it has supported detailing the human engineering activities in support of the design of the Orion space craft, testing of the EVA integrated spacesuit, and work done for the design of the lunar projects of the Constellation Program: Altair, Lunar Electric Rover, and Outposts

  19. Hazard analysis in uranium hexafluoride production facility

    International Nuclear Information System (INIS)

    The present work provides a method for preliminary hazard analysis of nuclear fuel cycle facilities. The proposed method identify both chemical and radiological hazards, as well as the consequences associated with accident scenarios. To illustrate the application of the method, a uranium hexafluoride production facility was selected. The main hazards are identified and the potential consequences are quantified. It was found that, although the facility handles radioactive material, the main hazards as associated with releases of toxic chemical substances such as hydrogen fluoride, anhydrous ammonia and nitric acid. It was shown that a contention bung can effectively reduce the consequences of atmospheric release of toxic materials. (author)

  20. Hot Cell Facility (HCF) Safety Analysis Report

    Energy Technology Data Exchange (ETDEWEB)

    MITCHELL,GERRY W.; LONGLEY,SUSAN W.; PHILBIN,JEFFREY S.; MAHN,JEFFREY A.; BERRY,DONALD T.; SCHWERS,NORMAN F.; VANDERBEEK,THOMAS E.; NAEGELI,ROBERT E.

    2000-11-01

    This Safety Analysis Report (SAR) is prepared in compliance with the requirements of DOE Order 5480.23, Nuclear Safety Analysis Reports, and has been written to the format and content guide of DOE-STD-3009-94 Preparation Guide for U. S. Department of Energy Nonreactor Nuclear Safety Analysis Reports. The Hot Cell Facility is a Hazard Category 2 nonreactor nuclear facility, and is operated by Sandia National Laboratories for the Department of Energy. This SAR provides a description of the HCF and its operations, an assessment of the hazards and potential accidents which may occur in the facility. The potential consequences and likelihood of these accidents are analyzed and described. Using the process and criteria described in DOE-STD-3009-94, safety-related structures, systems and components are identified, and the important safety functions of each SSC are described. Additionally, information which describes the safety management programs at SNL are described in ancillary chapters of the SAR.

  1. Hot Cell Facility (HCF) Safety Analysis Report

    International Nuclear Information System (INIS)

    This Safety Analysis Report (SAR) is prepared in compliance with the requirements of DOE Order 5480.23, Nuclear Safety Analysis Reports, and has been written to the format and content guide of DOE-STD-3009-94 Preparation Guide for U. S. Department of Energy Nonreactor Nuclear Safety Analysis Reports. The Hot Cell Facility is a Hazard Category 2 nonreactor nuclear facility, and is operated by Sandia National Laboratories for the Department of Energy. This SAR provides a description of the HCF and its operations, an assessment of the hazards and potential accidents which may occur in the facility. The potential consequences and likelihood of these accidents are analyzed and described. Using the process and criteria described in DOE-STD-3009-94, safety-related structures, systems and components are identified, and the important safety functions of each SSC are described. Additionally, information which describes the safety management programs at SNL are described in ancillary chapters of the SAR

  2. Sampling and Analysis Plan for the 221-U Facility

    International Nuclear Information System (INIS)

    This sampling and analysis plan (SAP) presents the rationale and strategy for the sampling and analysis activities proposed to be conducted to support the evaluation of alternatives for the final disposition of the 221-U Facility. This SAP will describe general sample locations and the minimum number of samples required. It will also identify the specific contaminants of potential concern (COPCs) and the required analysis. This SAP does not define the exact sample locations and equipment to be used in the field due to the nature of unknowns associated with the 221-U Facility

  3. Nuclear fuel cycle facility accident analysis handbook

    International Nuclear Information System (INIS)

    The Accident Analysis Handbook (AAH) covers four generic facilities: fuel manufacturing, fuel reprocessing, waste storage/solidification, and spent fuel storage; and six accident types: fire, explosion, tornado, criticality, spill, and equipment failure. These are the accident types considered to make major contributions to the radiological risk from accidents in nuclear fuel cycle facility operations. The AAH will enable the user to calculate source term releases from accident scenarios manually or by computer. A major feature of the AAH is development of accident sample problems to provide input to source term analysis methods and transport computer codes. Sample problems and illustrative examples for different accident types are included in the AAH

  4. Nuclear fuel cycle facility accident analysis handbook

    Energy Technology Data Exchange (ETDEWEB)

    Ayer, J E; Clark, A T; Loysen, P; Ballinger, M Y; Mishima, J; Owczarski, P C; Gregory, W S; Nichols, B D

    1988-05-01

    The Accident Analysis Handbook (AAH) covers four generic facilities: fuel manufacturing, fuel reprocessing, waste storage/solidification, and spent fuel storage; and six accident types: fire, explosion, tornado, criticality, spill, and equipment failure. These are the accident types considered to make major contributions to the radiological risk from accidents in nuclear fuel cycle facility operations. The AAH will enable the user to calculate source term releases from accident scenarios manually or by computer. A major feature of the AAH is development of accident sample problems to provide input to source term analysis methods and transport computer codes. Sample problems and illustrative examples for different accident types are included in the AAH.

  5. 303-K Storage facility sampling and analysis plan

    Energy Technology Data Exchange (ETDEWEB)

    Adler, J.G.

    1997-07-01

    This document describes the cleanup, sampling, and analysis activities associated with the closure of the 303-K Storage Facility under the Washington Administrative Code (WAC) 173-303-610, ``Dangerous Waste Regulations.`` this document is a supplement to the 303-K Storage Facility Closure Plan (DOE-RL 1995a) (Closure Plan). The objective of these activities is to support clean closure of the 303 K Storage Facility. This document defines the information and activities needed to meet this objective, including: constituents of concern, cleanup performance standards, cleanup activities, sampling locations and methods, field screening locations and methods, field quality control requirements, laboratory analytical methods, and data validation methodology. This document supersedes the Closure Plan if the two conflict

  6. Synthetic multi-element standards: a good tool for calibration and quality control of irradiation facilities used for neutron activation analysis

    International Nuclear Information System (INIS)

    Neutron activation analysis (NAA) is a physical technique used for the absolute measurement of the concentration of substances in solids and liquids. The method uses neutron irradiation which is commonly realised using a nuclear reactor in order to activate (make radioactive) different isotopes of the elements present in the sample. The radionuclides produced in this way emit gamma-rays that are characteristic of the elements present in the sample. Using gamma-ray spectrometry these radionuclides can then be identified and quantified, and hence their concentration in the sample can be determined. Although NAA is a straightforward method it requires a sound control of the many physical parameters involved to obtain accurate results and to guarantee a set accuracy in routine analysis. The accuracy of NAA depends on the specific measurement method used. One can perform NAA in a relative way by co-irradiating a known standard and the unknown sample in the same conditions and by comparing the ratio of gamma-rays they emit. Relative NAA has limited applicability since it requires reference standards with a comparable composition as the unknown. A more generally applicable method is the k0-NAA method. In the k0-NAA method all measurements are relative to the element Au resulting in 198Au when irradiated. The k0-NAA method further relies on the fact that the neutron energy spectrum produced in a given position in the reactor can be parameterised with two parameters: the shape factor of the epithermal neutron flux, indicating the deviation of the epithermal neutron spectrum from the ideal 1/E shape approximated by a 1/E1+a distribution, with E the neutron energy; f: the thermal-to-epithermal neutron flux ratio. The parameters f and a are characteristic for the irradiation facility (reactor and irradiation channels) and may change or fluctuate in time according to the irradiation conditions. The way elements activate (become radioactive) when interacting with neutrons is

  7. EPA Facility Registry Service (FRS): RCRA_ACTIVE

    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 active hazardous...

  8. Seismic risk analysis for General Electric Plutonium Facility, Pleasanton, California

    International Nuclear Information System (INIS)

    This report presents the results of a seismic risk analysis that focuses on all possible sources of seismic activity, with the exception of the postulated Verona Fault. The best estimate curve indicates that the Vallecitos facility will experience 30% g with a return period of roughly 130 years and 60% g with a return period of roughly 700 years

  9. 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

  10. Production Facility System Reliability Analysis Report

    Energy Technology Data Exchange (ETDEWEB)

    Dale, Crystal Buchanan [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Klein, Steven Karl [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2015-10-06

    This document describes the reliability, maintainability, and availability (RMA) modeling of the Los Alamos National Laboratory (LANL) design for the Closed Loop Helium Cooling System (CLHCS) planned for the NorthStar accelerator-based 99Mo production facility. The current analysis incorporates a conceptual helium recovery system, beam diagnostics, and prototype control system into the reliability analysis. The results from the 1000 hr blower test are addressed.

  11. OPTICAL analysis of solar facility heliostats

    Energy Technology Data Exchange (ETDEWEB)

    Igel, E.; Hughes, R.L.

    1977-05-01

    An experimentally verified simple analytical model, based on classical optical aberrations, is derived and predicts the power reception of a central receiver solar facility. A laboratory simulation was made of a typical heliostat, and its images were photographed and measured at several angles of incidence. The analytically predicted image size is in agreement with experiment to within less than 10% over an incident angle range of 60 degrees. Image size for several of the heliostats in the Sandia-ERDA Solar Thermal Test Facility array were calculated throughout a day and compared with ideal images and the size of the receiver. The optical parameters of the system and the motion of the sun were found to severely affect the design and optimization of any solar thermal facility. This analysis shows that it is the aberration astigmatism which governs the solar image size at the receiver. Image growth is minimal when heliostats are used at small angles of incidence, which usually corresponds to a limited operating time of two to three hours. However, image size is markedly increased at large angles of incidence. The principal result is that the predominant sources of image enlargement are identified and measures for minimizing these enlargements are presented. This analysis considers only the idealized optical problem and does not consider the pragmatic errors associated with implementation and operation of a heliostat array.

  12. Analysis - The new legislation for nuclear facilities

    International Nuclear Information System (INIS)

    The ministerial order dated February 7, 2012 settles the legal rules concerning nuclear facilities such as laboratories using nuclear materials or operating research reactors and nuclear power plants. These new rules are more a clearer, legal frame of nuclear activities than an extension of the present legislation. Among the changes we can quote the implementation of sanctions or the concept of global safety that means that the potential impacts on the environment must be taken into account all along the operating life of the plant and also during the dismantling and the management of the resulting radioactive wastes. Undeniably positive this legal framework should not be too rigid for small facilities and it must be considered as an help for plant operators to assume their responsibility. This legal framework can be considered as an harmonization at the European scale in terms of safety requirements because it allows the implementation in the French law of the WENRA standards. This document gathers a series of short articles describing the different aspects of this new regulation: the benefits, its preparation, its progressive implementation and the results that are expected. (A.C.)

  13. Evaluation of energy system analysis techniques for identifying underground facilities

    Energy Technology Data Exchange (ETDEWEB)

    VanKuiken, J.C.; Kavicky, J.A.; Portante, E.C. [and others

    1996-03-01

    This report describes the results of a study to determine the feasibility and potential usefulness of applying energy system analysis techniques to help detect and characterize underground facilities that could be used for clandestine activities. Four off-the-shelf energy system modeling tools were considered: (1) ENPEP (Energy and Power Evaluation Program) - a total energy system supply/demand model, (2) ICARUS (Investigation of Costs and Reliability in Utility Systems) - an electric utility system dispatching (or production cost and reliability) model, (3) SMN (Spot Market Network) - an aggregate electric power transmission network model, and (4) PECO/LF (Philadelphia Electric Company/Load Flow) - a detailed electricity load flow model. For the purposes of most of this work, underground facilities were assumed to consume about 500 kW to 3 MW of electricity. For some of the work, facilities as large as 10-20 MW were considered. The analysis of each model was conducted in three stages: data evaluation, base-case analysis, and comparative case analysis. For ENPEP and ICARUS, open source data from Pakistan were used for the evaluations. For SMN and PECO/LF, the country data were not readily available, so data for the state of Arizona were used to test the general concept.

  14. Facilities of management magnetoresistive transformer of active power

    Directory of Open Access Journals (Sweden)

    Val. S. Vuntesmeri

    2009-03-01

    Full Text Available Management facilities are considered, spectral composition is certain and the form of коммутируемого signal of magnetoresistive transformer of active power is rotined.

  15. Neutronics analysis of the Laboratory Microfusion Facility

    International Nuclear Information System (INIS)

    The radiological safety hazards of the experimental area (EA) for the proposed Inertial Confinement Fusion (ICF) Laboratory Microfusion Facility (LMF) have been examined. The EA includes those structures required to establish the proper pre-shot environment, point the beams, contain the pellet yield, and measure many different facets of the experiments. The radiation dose rates from neutron activation of representative target chamber materials, the laser beam tubes and the argon gas they contain, the air surrounding the chamber, and the concrete walls of the experimental area are given. Combining these results with the allowable dose rates for workers, we show how radiological considerations affect access to the inside of the target chamber and to the diagnostic platform area located outside the chamber. Waste disposal and tritium containment issues are summarized. Other neutronics issues, such as radiation damage to the final optics and neutron heating of materials placed close to the target, are also addressed. 16 refs., 2 figs., 1 tab

  16. Neutronics analysis of the laboratory microfusion facility

    International Nuclear Information System (INIS)

    The radiological safety hazards of the experimental area (EA) for the proposed Inertial Confinement Fusion (ICF) Laboratory Microfusion Facility (LMF) have been examined. The EA includes those structures required to establish the proper pre-shot environment, point the beams, contain the pellet yield, and measure many different facets of the experiments. The radiation dose rates from neutron activation of representative target chamber materials, the laser beam tubes and the argon gas they contain, the air surrounding the chamber, and the concrete walls of the experimental area are given. Combining these results with the allowable dose rates for workers, the authors show how radiological considerations affect access to the inside of the target chamber and to the diagnostic platform area located outside the chamber. Waste disposal and tritium containment issues are summarized. Other neutronics issues, such as radiation damage to the final optics and neutron heating of materials placed close to the target, are also addressed

  17. Exploratory Studies Facility Subsurface Fire Hazards Analysis

    International Nuclear Information System (INIS)

    The primary objective of this Fire Hazard Analysis (FHA) is to confirm the requirements for a comprehensive fire and related hazards protection program for the Exploratory Studies Facility (ESF) are sufficient to minimize the potential for: (1) The occurrence of a fire or related event. (2) A fire that causes an unacceptable on-site or off-site release of hazardous or radiological material that will threaten the health and safety of employees, the public or the environment. (3) Vital US. Department of Energy (DOE) programs suffering unacceptable interruptions as a result of fire and related hazards. (4) Property losses from a fire and related events exceeding limits established by DOE. (5) Critical process controls and safety class systems being damaged as a result of a fire and related events

  18. Exploratory Studies Facility Subsurface Fire Hazards Analysis

    International Nuclear Information System (INIS)

    The primary objective of this Fire Hazard Analysis (FHA) is to confirm the requirements for a comprehensive fire and related hazards protection program for the Exploratory Studies Facility (ESF) are sufficient to minimize the potential for: The occurrence of a fire or related event; A fire that causes an unacceptable on-site or off-site release of hazardous or radiological material that will threaten the health and safety of employees, the public or the environment; Vital U.S. Department of Energy (DOE) programs suffering unacceptable interruptions as a result of fire and related hazards; Property losses from a fire and related events exceeding limits established by DOE; and Critical process controls and safety class systems being damaged as a result of a fire and related events

  19. 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.

  20. Criticality safety analysis for mockup facility

    International Nuclear Information System (INIS)

    Benchmark calculations for SCALE4.4 CSAS6 module have been performed for 31 UO2 fuel, 15MOX fuel and 10 metal material criticality experiments and then calculation biases of the SCALE 4.4 CSAS6 module have been revealed to be 0.00982, 0.00579 and 0.02347, respectively. When CSAS6 is applied to the criticality safety analysis for the mockup facility in which several kinds of nuclear material components are included, the calculation bias of CSAS6 is conservatively taken to be 0.02347. With the aid of this benchmarked code system, criticality safety analyses for the mockup facility at normal and hypothetical accidental conditions have been carried out. It appears that the maximum Keff is 0.28356 well below than the critical limit, Keff=0.95 at normal condition. In a hypothetical accidental condition, the maximum Keff is found to be 0.73527 much lower than the subcritical limit. For another hypothetical accidental condition the nuclear material leaks out of container and spread or lump in the floor, it was assumed that the nuclear material is shaped into a slab and water exists in the empty space of the nuclear material. Keff has been calculated as function of slab thickness and the volume ratio of water to nuclear material. The result shows that the Keff increases as the water volume ratio increases. It is also revealed that the Keff reaches to the maximum value when water if filled in the empty space of nuclear material. The maximum Keff value is 0.93960 lower than the subcritical limit

  1. Forensic activation analysis

    International Nuclear Information System (INIS)

    Basic principles of neutron activation analysis are outlined. Examples of its use in police science include analysis for gunshot residues, toxic element determinations and multielement comparisons. Advantages of neutron activation analysis over other techniques are described. (R.L.)

  2. Facility Safeguardability Analysis In Support of Safeguards-by-Design

    Energy Technology Data Exchange (ETDEWEB)

    Philip Casey Durst; Roald Wigeland; Robert Bari; Trond Bjornard; John Hockert; Michael Zentner

    2010-07-01

    The following report proposes the use of Facility Safeguardability Analysis (FSA) to: i) compare and evaluate nuclear safeguards measures, ii) optimize the prospective facility safeguards approach, iii) objectively and analytically evaluate nuclear facility safeguardability, and iv) evaluate and optimize barriers within the facility and process design to minimize the risk of diversion and theft of nuclear material. As proposed by the authors, Facility Safeguardability Analysis would be used by the Facility Designer and/or Project Design Team during the design and construction of the nuclear facility to evaluate and optimize the facility safeguards approach and design of the safeguards system. Through a process of “Safeguards-by-Design” (SBD), this would be done at the earliest stages of project conceptual design and would involve domestic and international nuclear regulators and authorities, including the International Atomic Energy Agency (IAEA). The benefits of the Safeguards-by-Design approach is that it would clarify at a very early stage the international and domestic safeguards requirements for the Construction Project Team, and the best design and operating practices for meeting these requirements. It would also minimize the risk to the construction project, in terms of cost overruns or delays, which might otherwise occur if the nuclear safeguards measures are not incorporated into the facility design at an early stage. Incorporating nuclear safeguards measures is straight forward for nuclear facilities of existing design, but becomes more challenging with new designs and more complex nuclear facilities. For this reason, the facility designer and Project Design Team require an analytical tool for comparing safeguards measures, options, and approaches, and for evaluating the “safeguardability” of the facility. The report explains how preliminary diversion path analysis and the Proliferation Resistance and Physical Protection (PRPP) evaluation

  3. Cold vacuum drying facility final hazard analysis report

    Energy Technology Data Exchange (ETDEWEB)

    POWERS, T.B.

    1999-06-07

    This report describes the methodology used in conducting the Cold Vacuum Dlying Facility (CVDF) Hazard Analysis to support the CVDF Final Safety Analysis Report and documents the results. The hazard analysis was performed in accordance with DOE-STD-3009-94, ''Preparation Guide for U.S. Department of Energy Nonreactor Nuclear Facility Safety Analysis Reports,'' and implements the requirements of DOE Order 5480.23, ''Nuclear Safety Analysis Reports.''

  4. Cold Vacuum Drying (CVD) Facility Hazards Analysis Report

    Energy Technology Data Exchange (ETDEWEB)

    PATTERSON, P.R.

    1999-10-20

    This report describes the methodology used in conducting the Cold Vacuum Drying Facility (CVDF) hazard Analysis to support the CVDF Final Safety Analysis Report and documents the results. The hazard analysis was performed in accordance with DOE-STD-3009-94, ''Preparation Guide for US. Department of Energy Nonreactor Nuclear Facility Safety Analysis Reports,'' and implements the requirements of DOE Order 5480.23, ''Nuclear Safety Analysis Reports.''

  5. Neutron Activation Analysis

    Energy Technology Data Exchange (ETDEWEB)

    Corliss, William R.

    1968-01-01

    In activation analysis, a sample of an unknown material is first irradiated (activated) with nuclear particles. In practice these nuclear particles are almost always neutrons. The success of activation analysis depends upon nuclear reactions which are completely independent of an atom's chemical associations. The value of activation analysis as a research tool was recognized almost immediately upon the discovery of artificial radioactivity. This book discusses activation analysis experiments, applications and technical considerations.

  6. Environmental analysis of biomass-ethanol facilities

    Energy Technology Data Exchange (ETDEWEB)

    Corbus, D.; Putsche, V.

    1995-12-01

    This report analyzes the environmental regulatory requirements for several process configurations of a biomass-to-ethanol facility. It also evaluates the impact of two feedstocks (municipal solid waste [MSW] and agricultural residues) and three facility sizes (1000, 2000, and 3000 dry tons per day [dtpd]) on the environmental requirements. The basic biomass ethanol process has five major steps: (1) Milling, (2) Pretreatment, (3) Cofermentation, (4) Enzyme production, (5) Product recovery. Each step could have environmental impacts and thus be subject to regulation. Facilities that process 2000 dtpd of MSW or agricultural residues would produce 69 and 79 million gallons of ethanol, respectively.

  7. 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.

  8. Physical Activity Breaks and Facilities in US Secondary Schools

    Science.gov (United States)

    Hood, Nancy E.; Colabianchi, Natalie; Terry-McElrath, Yvonne M.; O'Malley, Patrick M.; Johnston, Lloyd D.

    2014-01-01

    Background: Research on physical activity breaks and facilities (indoor and outdoor) in secondary schools is relatively limited. Methods: School administrators and students in nationally representative samples of 8th (middle school) and 10th/12th grade (high school) students were surveyed annually from 2008-2009 to 2011-2012. School administrators…

  9. Compilation of historical information of 300 Area facilities and activities

    Energy Technology Data Exchange (ETDEWEB)

    Gerber, M.S.

    1992-12-01

    This document is a compilation of historical information of the 300 Area activities and facilities since the beginning. The 300 Area is shown as it looked in 1945, and also a more recent (1985) look at the 300 Area is provided.

  10. Critical Facilities for Active Participation in Learning Networks

    NARCIS (Netherlands)

    Hummel, Hans; Tattersall, Colin; Burgos, Daniel; Brouns, Francis; Kurvers, Hub; Koper, Rob

    2005-01-01

    Please use the following citation: Hummel, H. G. K., Tattersall, C., Burgos, D., Brouns, F. M. R., Kurvers, H. J., & Koper, E. J. R. (2006). Critical facilities for active participation in learning networks. Int. J. Web Based Communities, 2, 1, 81-99. This article is an extended version (with refere

  11. Compilation of historical information of 300 Area facilities and activities

    International Nuclear Information System (INIS)

    This document is a compilation of historical information of the 300 Area activities and facilities since the beginning. The 300 Area is shown as it looked in 1945, and also a more recent (1985) look at the 300 Area is provided

  12. The Remote Handled Immobilization Low-Activity Waste Disposal Facility Environmental Permits and Approval Plan

    International Nuclear Information System (INIS)

    The purpose of this document is to revise Document HNF-SD-ENV-EE-003, ''Permitting Plan for the Immobilized Low-Activity Waste Project, which was submitted on September 4, 1997. That plan accounted for the interim storage and disposal of Immobilized-Low Activity Waste at the existing Grout Treatment Facility Vaults (Project W-465) and within a newly constructed facility (Project W-520). Project W-520 was to have contained a combination of concrete vaults and trenches. This document supersedes that plan because of two subsequent items: (1) A disposal authorization that was received on October 25, 1999, in a U. S. Department of Energy-Headquarters, memorandum, ''Disposal Authorization Statement for the Department of Energy Hanford site Low-Level Waste Disposal facilities'' and (2) ''Breakthrough Initiative Immobilized Low-Activity Waste (ILAW) Disposal Alternative,'' August 1999, from Lucas Incorporated, Richland, Washington. The direction within the U. S. Department of Energy-Headquarters memorandum was given as follows: ''The DOE Radioactive Waste Management Order requires that a Disposal authorization statement be obtained prior to construction of new low-level waste disposal facility. Field elements with the existing low-level waste disposal facilities shall obtain a disposal authorization statement in accordance with the schedule in the complex-wide Low-Level Waste Management Program Plan. The disposal authorization statement shall be issued based on a review of the facility's performance assessment and composite analysis or appropriate CERCLA documentation. The disposal authorization shall specify the limits and conditions on construction, design, operations, and closure of the low-level waste facility based on these reviews. A disposal authorization statement is a part of the required radioactive waste management basis for a disposal facility. Failure to obtain a disposal authorization statement or record of decision shall result in shutdown of an operational

  13. Cold Vacuum Drying (CVD) Facility Design Basis Accident Analysis Documentation

    Energy Technology Data Exchange (ETDEWEB)

    PIEPHO, M.G.

    1999-10-20

    This document provides the detailed accident analysis to support HNF-3553, Annex B, Spent Nuclear Fuel Project Final Safety Analysis Report, ''Cold Vacuum Drying Facility Final Safety Analysis Report (FSAR).'' All assumptions, parameters and models used to provide the analysis of the design basis accidents are documented to support the conclusions in the FSAR.

  14. CANISTER HANDLING FACILITY - VENTILATION CONFINEMENT ZONING ANALYSIS

    International Nuclear Information System (INIS)

    The purpose of this calculation is to calculate the necessary airflow distribution used to size the HVAC equipment for the Canister Handling Facility. These results will be compared to the Heating and Cooling Load Calculation in detailed design. The calculations contained in this document were developed by DandE/Mechanical HVAC and are intended solely for the use of the DandE/Mechanical HVAC department in its work regarding the HVAC system for the Canister Handling Facility. Yucca Mountain Project personnel from the DandE/Mechanical HVAC department should be consulted before use of the calculations for purposes other than those stated herein or used by individuals other than authorized personnel in DandE/Mechanical HVAC department

  15. Activation of Air and Utilities in the National Ignition Facility

    Energy Technology Data Exchange (ETDEWEB)

    Khater, H; Pohl, B; Brererton, S

    2010-04-08

    Detailed 3-D modeling of the NIF facility is developed to accurately simulate the radiation environment within the NIF. Neutrons streaming outside the NIF Target Chamber will activate the air present inside the Target Bay and the Ar gas inside the laser tubes. Smaller levels of activity are also generated in the Switchyard air and in the Ar portion of the SY laser beam path. The impact of neutron activation of utilities located inside the Target Bay is analyzed for variety of shot types. The impact of activating TB utilities on dose received by maintenance personnel post-shot is analyzed. The current NIF facility model includes all important features of the Target Chamber, shielding system, and building configuration. Flow of activated air from the Target Bay is controlled by the HVAC system. The amount of activated Target Bay air released through the stack is very small and does not pose significant hazard to personnel or the environment. Activation of Switchyard air is negligible. Activation of Target Bay utilities result in a manageable dose rate environment post high yield (20 MJ) shots. The levels of activation generated in air and utilities during D-D and THD shots are small and do not impact work planning post shots.

  16. Regional analysis of energy facility siting

    Energy Technology Data Exchange (ETDEWEB)

    Lipfert, F W; Meier, P M; Kleinman, L I

    1980-01-01

    This paper has examined some of the regional environmental parameters of energy facility siting, with emphasis on air quality impacts. An example of a siting optimization study was presented, and it was shown how difficult it presently is to specify an environmental objective function that is universally applicable. The importance of regional background effects was discussed, and long-range transport models were used to analyze the relative importance of local and long-range impacts.

  17. Thermal Analysis of Main Vessel in Uranium Liquor Critical Facility

    Institute of Scientific and Technical Information of China (English)

    2008-01-01

    <正>The thermal stress analysis of No.2 vessel in the Uranium Liquor Critical Facility is carried through, in order to research the thermal stability of the vessel and provide the data for general stress evaluation.

  18. CHANGE OF CONTRACTOR FOR THE FACILITIES MANAGEMENT ACTIVITIES AT CERN

    CERN Multimedia

    2003-01-01

    The Facilities Management contract at CERN, under the responsibility of ST Division, Group FM, is in charge of the maintenance and minor works on tertiary installations (i.e. all structures and installations that have no direct relation to the running of the accelerators) for the following trades: - Technical: heating, ventilation, air conditioning, plumbing, electricity, civil engineering (painting, roofing, glazing, blinds, fencing, masonry etc.), cleansing, passenger and goods lifts, automatic and powered doors, kitchen equipment, roads, signs, keys and locks, office furniture, - Services: waste collection, security, green areas, cleaning and sanitary supplies, disinfection, rodent control and insect control. Starting from the 1st June the present contractor will stop some activities that will be taken under its responsibility by the new one, INGEST Facility. Others activities will be moved on the 1st July. Minor perturbation in the service might occur. The contact number will not change and will be opera...

  19. CHANGE OF CONTRACTOR FOR THE FACILITIES MANAGEMENT ACTIVITIES AT CERN

    CERN Document Server

    2003-01-01

    The Facilities Management contract at CERN, under the responsibility of ST Division, Group FM, is in charge of the maintenance and minor works on tertiary installations (i.e. all structures and installations that have no direct relation to the running of the accelerators) for the following trades: - Technical: heating, ventilation, air conditioning, plumbing, electricity, civil engineering (painting, roofing, glazing, blinds, fencing, masonry etc.), cleansing, passenger and goods lifts, automatic and powered doors, kitchen equipment, roads, signs, keys and locks, office furniture, - Services: waste collection, security, green areas, cleaning and sanitary supplies, disinfection, rodent control and insect control. Starting from the 1st June the present contractor will stop some activities that will be taken under its responsibility by the new one, INGEST Facility. The remaining activities (including cleaning) will be moved on the 1st July. Minor perturbation in the service might occur. The contact number will ...

  20. Safety Assessment for Facilities and Activities. General Safety Requirements

    International Nuclear Information System (INIS)

    This publication describes the generally applicable requirements to be fulfilled in safety assessments for facilities and activities, with special attention paid to defence in depth, quantitative analyses and the application of a graded approach to the ranges of facilities and of activities that are addressed. The requirements provide a consistent and coherent basis for safety assessments, facilitating the transfer of good practices between organizations. A review of Safety Requirements publications was commenced in 2011 following the accident in the Fukushima Daiichi nuclear power plant in Japan. The review revealed no significant areas of weakness and resulted in just a small set of amendments to strengthen the requirements and facilitate their implementation, which are contained in the present publication

  1. Associations between Moderate-to-Vigorous Physical Activity and Neighbourhood Recreational Facilities: The Features of the Facilities Matter

    Directory of Open Access Journals (Sweden)

    Ka Yiu Lee

    2014-12-01

    Full Text Available Objectives: To examine the associations between objectively-assessed moderate-to-vigorous physical activity (MVPA and perceived/objective measures of neighbourhood recreational facilities categorized into indoor or outdoor, public, residential or commercial facilities. The associations between facility perceptions and objectively-assessed numbers of recreational facilities were also examined. Method: A questionnaire was used on 480 adults to measure local facility perceptions, with 154 participants wearing ActiGraph accelerometers for ≥4 days. The objectively-assessed number of neighbourhood recreational facilities were examined using direct observations and Geographical Information System data. Results: Both positive and negative associations were found between MVPA and perceived/objective measures of recreational facilities. Some associations depended on whether the recreational facilities were indoor or outdoor, public or residential facilities. The objectively-assessed number of most public recreational facilities was associated with the corresponding facility perceptions, but the size of effect was generally lower than for residential recreational facilities. Conclusions: The objectively-assessed number of residential outdoor table tennis courts and public indoor swimming pools, the objectively-assessed presence of tennis courts and swimming pools, and the perceived presence of bike lanes and swimming pools were positive determinants of MVPA. It is suggested to categorize the recreational facilities into smaller divisions in order to identify unique associations with MVPA.

  2. Nuclear fuel cycle facility accident analysis handbook

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-03-01

    The purpose of this Handbook is to provide guidance on how to calculate the characteristics of releases of radioactive materials and/or hazardous chemicals from nonreactor nuclear facilities. In addition, the Handbook provides guidance on how to calculate the consequences of those releases. There are four major chapters: Hazard Evaluation and Scenario Development; Source Term Determination; Transport Within Containment/Confinement; and Atmospheric Dispersion and Consequences Modeling. These chapters are supported by Appendices, including: a summary of chemical and nuclear information that contains descriptions of various fuel cycle facilities; details on how to calculate the characteristics of source terms for releases of hazardous chemicals; a comparison of NRC, EPA, and OSHA programs that address chemical safety; a summary of the performance of HEPA and other filters; and a discussion of uncertainties. Several sample problems are presented: a free-fall spill of powder, an explosion with radioactive release; a fire with radioactive release; filter failure; hydrogen fluoride release from a tankcar; a uranium hexafluoride cylinder rupture; a liquid spill in a vitrification plant; and a criticality incident. Finally, this Handbook includes a computer model, LPF No.1B, that is intended for use in calculating Leak Path Factors. A list of contributors to the Handbook is presented in Chapter 6. 39 figs., 35 tabs.

  3. Nuclear fuel cycle facility accident analysis handbook

    International Nuclear Information System (INIS)

    The purpose of this Handbook is to provide guidance on how to calculate the characteristics of releases of radioactive materials and/or hazardous chemicals from nonreactor nuclear facilities. In addition, the Handbook provides guidance on how to calculate the consequences of those releases. There are four major chapters: Hazard Evaluation and Scenario Development; Source Term Determination; Transport Within Containment/Confinement; and Atmospheric Dispersion and Consequences Modeling. These chapters are supported by Appendices, including: a summary of chemical and nuclear information that contains descriptions of various fuel cycle facilities; details on how to calculate the characteristics of source terms for releases of hazardous chemicals; a comparison of NRC, EPA, and OSHA programs that address chemical safety; a summary of the performance of HEPA and other filters; and a discussion of uncertainties. Several sample problems are presented: a free-fall spill of powder, an explosion with radioactive release; a fire with radioactive release; filter failure; hydrogen fluoride release from a tankcar; a uranium hexafluoride cylinder rupture; a liquid spill in a vitrification plant; and a criticality incident. Finally, this Handbook includes a computer model, LPF No.1B, that is intended for use in calculating Leak Path Factors. A list of contributors to the Handbook is presented in Chapter 6. 39 figs., 35 tabs

  4. Sampling and Analysis Plan for the 233-S Plutonium Concentration Facility

    International Nuclear Information System (INIS)

    This Sampling and Analysis Plan (SAP) provides the information and instructions to be used for sampling and analysis activities in the 233-S Plutonium Concentration Facility. The information and instructions herein are separated into three parts and address the Data Quality Objective (DQO) Summary Report, Quality Assurance Project Plan (QAP), and SAP

  5. Facility management and energy efficiency -- analysis and recommendations; Facility Management und Energieeffizienz: Analyse und Handlungsempfehlungen

    Energy Technology Data Exchange (ETDEWEB)

    Staub, P.; Weibel, K.; Zaugg, T. [Pom and Consulting Ltd., Zuerich (Switzerland); Lang, R. [Gruenberg and Partner Ltd., Zuerich (Switzerland); Frei, Ch. [Herzog Kull Group, Aarau (Switzerland)

    2001-07-01

    This final report presents the results of a study made on how facility management (FM) is positioned in enterprises and on how energy management can be integrated into the facility management process. Also, recommendations are made on the actions that are considered necessary to improve the understanding of facility management and energy management. The findings of an analysis made of the results of a survey among 200 enterprises, 20 interviews and 5 case studies are presented. The authors state that, in spite of the relatively small sample taken - mostly larger enterprises - trends in facility management and energy management could be shown. The findings of the survey, such as the relative importance of the integration of energy topics in facility management and the need for standardised indicators and benchmarking, are discussed in detail. Also, it is noted that the success of FM is in part due to delegation of responsibility to smaller business units or even to individual employees. The market potential for FM services is examined, with yearly growth rates of up to 20%. The importance of anchoring FM strategies at the top level of management is stressed, as is the need for promotion of the idea of facility management and training concepts for those responsible for its implementation.

  6. Radioisotope Power System Facility shielding analysis

    International Nuclear Information System (INIS)

    A series of calculations for the Radioisotope Power System Facility have been performed. These analyses have determined the shielding required for storage, testing, and transport of 238Pu heat source modules using the Monte Carlo code MCNP3B. The source terms and the assumptions used have been verified by comparison of calculated dose rates with measured ones. This paper describes the methodology used for shielding designs and the utilization of available variance reduction techniques to improve the computational efficiency. The new version of MCNP (MCNP3B) with a repeated structure capability was used. It decreased the chance for computer model errors and greatly decreased the model setup time. 2 refs., 3 figs., 2 tabs

  7. Spatio-temporal Facility Utilization Analysis from Exhaustive WiFi Monitoring

    DEFF Research Database (Denmark)

    Prentow, Thor Siiger; Ruiz-Ruiz, Antonio; Blunck, Henrik;

    2015-01-01

    realistic data to inform facility planning. In this paper, we propose analysis methods to extract knowledge from large sets of network collected WiFi traces to better inform facility management and planning in large building complexes. The analysis methods, which build on a rich set of temporal and spatial...... to inform facility-planning activities. To evaluate the proposed methods and visualization tools, we present facility utilization analysis results for a large hospital complex covering more than 10 hectares. The evaluation is based on WiFi traces collected in the hospital’s WiFi infrastructure over two...... weeks observing around 18000 different devices recording more than a billion individual WiFi measurements. We highlight the tools’ ability to deduce people’s presences and movements and how they can provide respective insights into the test-bed hospital by investigating utilization patterns globally...

  8. ESF [Exploratory Shaft Facility] flexibility analysis

    International Nuclear Information System (INIS)

    This report directs that uncertainty allowances be included within the ESF facilities. The recommendations herein developed are intended as input to Title II Design criteria. Flexibility is measured first by lineal ft of drift, and then by hoisting rate and capacity of supporting utilities and services. A defined probability of need shows an extra 10,000 ft of drift for the first level of flexibility responding to testing and operations, and over 60,000 ft of drift for the second level of flexibility which recognizes possible need for perimeter drifting to investigate geologic stratigraphy. Observing there will be time constraints, a single shaft muck hoisting rate up to 170 to 250 tons per hour is recommended. The potential hoisting rate recommended for flexibility should be satisfied by a hoist approximately equivalent to, or conveniently upgraded from those being considered for sinking and construction, or 1000 horsepower. The cost of flexibility is limited to engineering planning and design (mostly conceptual) which makes later expansion achievable, and to selected items for initial construction where later upgrading would be impractical, impossible, or very costly. The cost is fixed to the level of flexibility and does not vary with excavated footage. The incremental margin is only a small fraction of the additional footage made available. Flexibility presents a strategy and not a position of design or technology. Examples used in this report are intended to be illustrative only, and not to lead design or cost estimates. 7 tabs

  9. Detailed measurements and modelling of thermo active components using a room size test facility

    DEFF Research Database (Denmark)

    Weitzmann, Peter; Svendsen, Svend

    2005-01-01

    measurements in an office sized test facility with thermo active ceiling and floor as well as modelling of similar conditions in a computer program designed for analysis of building integrated heating and cooling systems. A method for characterizing the cooling capacity of thermo active components is described......This paper describes an investigation of thermo active components based on prefabricated hollow core concrete decks. Recent years have given an increased awareness of the use of thermo active components as an alternative to mechanical cooling systems in office buildings. The investigation covers...

  10. Business administration of PET facilities. A cost analysis of three facilities utilizing delivery FDG

    International Nuclear Information System (INIS)

    PET (positron emission tomography) has been proved to be a powerful imaging tool in clinical oncology. The number of PET facilities in Japan has remarkably increased over the last decade. Furthermore, the approval of delivery fluorodeoxyglucose (FDG) in 2005 resulted in a tremendous expansion of the PET institutions without a cyclotron facility. The aim of this study was to conduct a cost analysis of PET institutions that utilized delivery FDG. Three PET facilities using delivery FDG were investigated about the costs for PET service. Fixed costs included depreciation costs for construction and medical equipments such as positron camera. Variable costs consisted of costs for medical materials including delivery FDG. The break-even point was analyzed in each of three institutions. In the three hospitals (A, B and C), the annual number of PET scan was 1,591, 1,637 and 914, while cost per scan was accounted as 110,262 yen, 111,091 yen, and 134,192 yen, respectively. The break-even point was calculated to be 2,583, 2,679 and 2,081, respectively. PET facilities utilizing delivery FDG seemed to have difficulty in business administration. Such a situation suggests the possibility that the current supply of PET facilities might exceed actual demand for the service. The efficiency of resource allocation should be taken into consideration in the future health service researches on PET. (author)

  11. 13. seminar 'Activation analysis'

    International Nuclear Information System (INIS)

    Collection of the abstracts of contributions to the seminar covering broad ranges of application of activation analysis and improvements of systems and process steps. Most of them have been prepared separately for the energy data bases. (RB)

  12. Analysis of the zone approach for plutonium facilities

    International Nuclear Information System (INIS)

    In order to examine the effect of different inspection strategies on inspection effort, an analysis was carried out of the zone approach for the international safeguards verifications of a model nuclear fuel cycle. The fuel cycle includes the fabrication of mixed-oxide fresh fuel for nine light-water reactors and one experimental breeder reactor and the subsequent reprocessing of the spent fuel. There are thus two zones to be considered, a plutonium zone and an irradiated fuel zone. The zone approach entails many fewer verifications of nuclear material flows between different material balance areas (facilities) than the facility-oriented approach, and it requires an annual simultaneous physical inventory verification (PIV) and monthly simultaneous interim inventory verifications for timeliness at all the facilities. Therefore, the zone approach yields snapshots of the disposition of the nuclear materials at the time of the simultaneous inventory verifications, but less verified information than a facility-oriented approach encompassing frequent flow verification

  13. Insider threat to secure facilities: data analysis

    Energy Technology Data Exchange (ETDEWEB)

    1979-12-07

    This report is the culmination of a project in which data from several industries confronting internal security threats were collected and analyzed. The industries and threats involved are deemed to be analogous in one or more respects to potential threats confronting decision makers in the nuclear industry. The analog internal threats consist of bank frauds and embezzlements over $10,000, computer crimes of various types and insider drug thefts from drug manufactures and distributors. These data have been subjected to careful analysis utilizing both descriptive and formal statistical techniques. A number of findings are quite suggestive as to the general nature of the internal threat and are discussed and interpreted in terms of thenuclear industry analogy.

  14. Wageningen UR Unmanned Aerial Remote Sensing Facility - Overview of activities

    Science.gov (United States)

    Bartholomeus, Harm; Keesstra, Saskia; Kooistra, Lammert; Suomalainen, Juha; Mucher, Sander; Kramer, Henk; Franke, Jappe

    2016-04-01

    To support environmental management there is an increasing need for timely, accurate and detailed information on our land. Unmanned Aerial Systems (UAS) are increasingly used to monitor agricultural crop development, habitat quality or urban heat efficiency. An important reason is that UAS technology is maturing quickly while the flexible capabilities of UAS fill a gap between satellite based and ground based geo-sensing systems. In 2012, different groups within Wageningen University and Research Centre have established an Unmanned Airborne Remote Sensing Facility. The objective of this facility is threefold: a) To develop innovation in the field of remote sensing science by providing a platform for dedicated and high-quality experiments; b) To support high quality UAS services by providing calibration facilities and disseminating processing procedures to the UAS user community; and c) To promote and test the use of UAS in a broad range of application fields like habitat monitoring, precision agriculture and land degradation assessment. The facility is hosted by the Laboratory of Geo-Information Science and Remote Sensing (GRS) and the Department of Soil Physics and Land Management (SLM) of Wageningen University together with the team Earth Informatics (EI) of Alterra. The added value of the Unmanned Aerial Remote Sensing Facility is that compared to for example satellite based remote sensing more dedicated science experiments can be prepared. This includes for example higher frequent observations in time (e.g., diurnal observations), observations of an object under different observation angles for characterization of BRDF and flexibility in use of camera's and sensors types. In this way, laboratory type of set ups can be tested in a field situation and effects of up-scaling can be tested. In the last years we developed and implemented different camera systems (e.g. a hyperspectral pushbroom system, and multispectral frame cameras) which we operated in projects all

  15. Documented Safety Analysis for the Waste Storage Facilities March 2010

    Energy Technology Data Exchange (ETDEWEB)

    Laycak, D T

    2010-03-05

    This Documented Safety Analysis (DSA) for the Waste Storage Facilities was developed in accordance with 10 CFR 830, Subpart B, 'Safety Basis Requirements,' and utilizes the methodology outlined in DOE-STD-3009-94, Change Notice 3. The Waste Storage Facilities consist of Area 625 (A625) and the Decontamination and Waste Treatment Facility (DWTF) Storage Area portion of the DWTF complex. These two areas are combined into a single DSA, as their functions as storage for radioactive and hazardous waste are essentially identical. The B695 Segment of DWTF is addressed under a separate DSA. This DSA provides a description of the Waste Storage Facilities and the operations conducted therein; identification of hazards; analyses of the hazards, including inventories, bounding releases, consequences, and conclusions; and programmatic elements that describe the current capacity for safe operations. The mission of the Waste Storage Facilities is to safely handle, store, and treat hazardous waste, transuranic (TRU) waste, low-level waste (LLW), mixed waste, combined waste, nonhazardous industrial waste, and conditionally accepted waste generated at LLNL (as well as small amounts from other DOE facilities).

  16. Documented Safety Analysis for the Waste Storage Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Laycak, D

    2008-06-16

    This documented safety analysis (DSA) for the Waste Storage Facilities was developed in accordance with 10 CFR 830, Subpart B, 'Safety Basis Requirements', and utilizes the methodology outlined in DOE-STD-3009-94, Change Notice 3. The Waste Storage Facilities consist of Area 625 (A625) and the Decontamination and Waste Treatment Facility (DWTF) Storage Area portion of the DWTF complex. These two areas are combined into a single DSA, as their functions as storage for radioactive and hazardous waste are essentially identical. The B695 Segment of DWTF is addressed under a separate DSA. This DSA provides a description of the Waste Storage Facilities and the operations conducted therein; identification of hazards; analyses of the hazards, including inventories, bounding releases, consequences, and conclusions; and programmatic elements that describe the current capacity for safe operations. The mission of the Waste Storage Facilities is to safely handle, store, and treat hazardous waste, transuranic (TRU) waste, low-level waste (LLW), mixed waste, combined waste, nonhazardous industrial waste, and conditionally accepted waste generated at LLNL (as well as small amounts from other DOE facilities).

  17. A systems analysis approach to nuclear facility siting

    International Nuclear Information System (INIS)

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

  18. Fire Hazard Analysis for the Cold Vacuum Drying (CVD) Facility

    International Nuclear Information System (INIS)

    This Fire Hazard Analysis assesses the risk from fire within individual fire areas in the Cold Vacuum Drying Facility at the Hanford Site in relation to existing or proposed fire protection features to ascertain whether the objectives of DOE Order 5480.7A Fire Protection are met

  19. Modeling and Analysis of Facility Systems for A Hybrid Materials Test Program

    Science.gov (United States)

    Congiardo, Jared F.

    2007-01-01

    Analytic modeling and analysis processes employed at NASA-SSC in rocket propulsion systems testing are discussed in this paper with application to test facility propellant supply system design, activation and test of a hybrid rocket motor provided. This paper discusses the analytic model employed, its utilization across project phases and reviews performance results.

  20. Cold Vacuum Drying facility design basis accident analysis documentation

    Energy Technology Data Exchange (ETDEWEB)

    CROWE, R.D.

    2000-08-08

    This document provides the detailed accident analysis to support HNF-3553, Annex B, Spent Nuclear Fuel Project Final Safety Analysis Report (FSAR), ''Cold Vacuum Drying Facility Final Safety Analysis Report.'' All assumptions, parameters, and models used to provide the analysis of the design basis accidents are documented to support the conclusions in the FSAR. The calculations in this document address the design basis accidents (DBAs) selected for analysis in HNF-3553, ''Spent Nuclear Fuel Project Final Safety Analysis Report'', Annex B, ''Cold Vacuum Drying Facility Final Safety Analysis Report.'' The objective is to determine the quantity of radioactive particulate available for release at any point during processing at the Cold Vacuum Drying Facility (CVDF) and to use that quantity to determine the amount of radioactive material released during the DBAs. The radioactive material released is used to determine dose consequences to receptors at four locations, and the dose consequences are compared with the appropriate evaluation guidelines and release limits to ascertain the need for preventive and mitigative controls.

  1. Activation analysis in Greece

    International Nuclear Information System (INIS)

    A review of research and development on NAA as well as examples of applications of this method are presented, taken from work carried out over the last 21 years at the Radioanalytical Laboratory of the Department of Chemistry in the Greek Nuclear Research Center ''Demokritos''. Improved and faster radiochemical NAA methods have been developed for the determination of Au, Ni, Cl, As, Cu, U, Cr, Eu, Hg and Mo in several materials, for the simultaneous determination of Br and I; Mg, Sr and Ni; As and Cu; As, Sb and Hg; Mn, Sr and Ba; Cd and Zn; Se and As; Mo and Cr in biological materials. Instrumental NAA methods have also been developed for the determination of Ag, Cl and Na in lake waters, Al, Ca, Mg and V in wines, 7 trace elements in biological materials, 17 trace elements in sediments and 20 minor and trace elements in ceramics. A comprehensive computer program for routine activation analysis using Ge(Li) detectors have been worked out. A rather extended charged-particle activation analysis program is carried out for the last 10 years, including particle induced X-ray emission (PIXE) analysis, particle induced prompt gamma-ray emission analysis (PIGE), other nuclear reactions and proton activation analysis. A special neutron activation method, the delayed fission neutron counting method is used for the analysis of fissionable elements, as U, Th, Pu, in samples of the whole nuclear fuel cycle including geological, enriched and nuclear safeguards samples

  2. Fuel Storage Facility Final Safety Analysis Report. Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    Linderoth, C.E.

    1984-03-01

    The Fuel Storage Facility (FSF) is an integral part of the Fast Flux Test Facility. Its purpose is to provide long-term storage (20-year design life) for spent fuel core elements used to provide the fast flux environment in FFTF, and for test fuel pins, components and subassemblies that have been irradiated in the fast flux environment. This Final Safety Analysis Report (FSAR) and its supporting documentation provides a complete description and safety evaluation of the site, the plant design, operations, and potential accidents.

  3. Fire Hazard Analysis for the Cold Vacuum Drying facility (CVD) Facility

    CERN Document Server

    Singh, G

    2000-01-01

    The CVDF is a nonreactor nuclear facility that will process the Spent Nuclear Fuels (SNF) presently stored in the 105-KE and 105-KW SNF storage basins. Multi-canister overpacks (MCOs) will be loaded (filled) with K Basin fuel transported to the CVDF. The MCOs will be processed at the CVDF to remove free water from the fuel cells (packages). Following processing at the CVDF, the MCOs will be transported to the CSB for interim storage until a long-term storage solution can be implemented. This operation is expected to start in November 2000. A Fire Hazard Analysis (FHA) is required for all new facilities and all nonreactor nuclear facilities, in accordance with U.S. Department of Energy (DOE) Order 5480.7A, Fire Protection. This FHA has been prepared in accordance with DOE 5480.7A and HNF-PRO-350, Fire Hazard Analysis Requirements. Additionally, requirements or criteria contained in DOE, Richland Operations Office (RL) RL Implementing Directive (RLID) 5480.7, Fire Protection, or other DOE documentation are cite...

  4. PROMPT DOSE ANALYSIS FOR THE NATIONAL IGNITION FACILITY

    Energy Technology Data Exchange (ETDEWEB)

    Khater, H; Dauffy, L; Sitaraman, S; Brereton, S

    2008-09-23

    Detailed 3-D modeling of the NIF facility is developed to accurately understand the prompt radiation environment within NIF. Prompt dose values are calculated for different phases of NIF operation. Results of the analysis were used to determine the final thicknesses of the Target Bay (TB) and secondary doors as well as the required shield thicknesses for all unused penetrations. Integrated dose values at different locations within the facility are needed to formulate the personnel access requirements within different parts of the facility. The conclusions of this presentation are: (1) The current NIF facility model includes all important features of the Target Chamber, shielding system, and building configuration; (2) All shielding requirements for Phase I operation are met; (3) Negligible dose values (a fraction of mrem) are expected in normally occupied areas during Phase I; (4) In preparation for the Ignition Campaign and Phase IV of operation, all primary and secondary shield doors will be installed; (5) Unused utility penetrations in the Target Bay and Switchyard walls ({approx}50%) will be shielded by 1 foot thick concrete to reduce prompt dose inside and outside the NIF facility; (6) During Phase IV, a 20 MJ shot will produce acceptable dose levels in the occupied areas as well as at the nearest site boundary; (7) A comprehensive radiation monitoring plan will be put in place to monitor dose values at large number of locations; and (8) Results of the dose monitoring will be used to modify personnel access requirements if needed.

  5. The economic impacts of noxious facilities on wages and property values: An exploratory analysis

    Energy Technology Data Exchange (ETDEWEB)

    Nieves, L.A.; Hemphill, R.C.; Clark, D.E.

    1991-05-01

    Recent assessments of socioeconomic impacts resulting from the location of potentially hazardous facilities have concentrated on the issue of negative public perceptions and their resulting economic consequences. This report presents an analysis designed to answer the question: Can economic impacts resulting from negative perceptions of noxious facilities'' be identified and measured To identify the impacts of negative perceptions, data on noxious facilities sited throughout the United States were compiled, and secondary economic and demographic data sufficient to analyze the economic impacts on the surrounding study areas were assembled. This study uses wage rate and property value differentials to measure impacts on social welfare so that the extent to which noxious facilities and their associated activities have affected surrounding areas can be determined.

  6. The economic impacts of noxious facilities on wages and property values: An exploratory analysis

    Energy Technology Data Exchange (ETDEWEB)

    Nieves, L.A.; Hemphill, R.C.; Clark, D.E.

    1991-05-01

    Recent assessments of socioeconomic impacts resulting from the location of potentially hazardous facilities have concentrated on the issue of negative public perceptions and their resulting economic consequences. This report presents an analysis designed to answer the question: Can economic impacts resulting from negative perceptions of ``noxious facilities`` be identified and measured? To identify the impacts of negative perceptions, data on noxious facilities sited throughout the United States were compiled, and secondary economic and demographic data sufficient to analyze the economic impacts on the surrounding study areas were assembled. This study uses wage rate and property value differentials to measure impacts on social welfare so that the extent to which noxious facilities and their associated activities have affected surrounding areas can be determined.

  7. Large-coil-test-facility fault-tree analysis

    International Nuclear Information System (INIS)

    An operating-safety study is being conducted for the Large Coil Test Facility (LCTF). The purpose of this study is to provide the facility operators and users with added insight into potential problem areas that could affect the safety of personnel or the availability of equipment. This is a preliminary report, on Phase I of that study. A central feature of the study is the incorporation of engineering judgements (by LCTF personnel) into an outside, overall view of the facility. The LCTF was analyzed in terms of 32 subsystems, each of which are subject to failure from any of 15 generic failure initiators. The study identified approximately 40 primary areas of concern which were subjected to a computer analysis as an aid in understanding the complex subsystem interactions that can occur within the facility. The study did not analyze in detail the internal structure of the subsystems at the individual component level. A companion study using traditional fault tree techniques did analyze approximately 20% of the LCTF at the component level. A comparison between these two analysis techniques is included in Section 7

  8. Nuclear Rocket Facility Decommissioning Project: Controlled Explosive Demolition of Neutron-Activated Shield Wall

    Energy Technology Data Exchange (ETDEWEB)

    Michael R. Kruzic

    2008-06-01

    Located in Area 25 of the Nevada Test Site (NTS), the Test Cell A (TCA) Facility (Figure 1) was used in the early to mid-1960s for testing of nuclear rocket engines, as part of the Nuclear Rocket Development Program, to further space travel. Nuclear rocket testing resulted in the activation of materials around the reactors and the release of fission products and fuel particles. The TCA facility, known as Corrective Action Unit 115, was decontaminated and decommissioned (D&D) from December 2004 to July 2005 using the Streamlined Approach for Environmental Restoration (SAFER) process, under the Federal Facility Agreement and Consent Order. The SAFER process allows environmental remediation and facility closure activities (i.e., decommissioning) to occur simultaneously, provided technical decisions are made by an experienced decision maker within the site conceptual site model. Facility closure involved a seven-step decommissioning strategy. First, preliminary investigation activities were performed, including review of process knowledge documentation, targeted facility radiological and hazardous material surveys, concrete core drilling and analysis, shield wall radiological characterization, and discrete sampling, which proved to be very useful and cost-effective in subsequent decommissioning planning and execution and worker safety. Second, site setup and mobilization of equipment and personnel were completed. Third, early removal of hazardous materials, including asbestos, lead, cadmium, and oil, was performed ensuring worker safety during more invasive demolition activities. Process piping was to be verified void of contents. Electrical systems were de-energized and other systems were rendered free of residual energy. Fourth, areas of high radiological contamination were decontaminated using multiple methods. Contamination levels varied across the facility. Fixed beta/gamma contamination levels ranged up to 2 million disintegrations per minute (dpm)/100

  9. Forensic Activation Analysis

    International Nuclear Information System (INIS)

    The high sensitivity of high-flux (reactor) thermal-neutron activation analysis (NAA) for the detection and quantitative measurement of a large number of elements has led, in recent years, to a considerable degree of application of the method in the area of scientific crime investigation (criminalistics). Thus, in a Forensic Activation Analysis Bibliography recently compiled by the author, some 135 publications in this field are listed - and more are appearing quite rapidly. The nondestructive character of the purely-instrumental form of the method is an added advantage in forensic work, since evidence samples involved in actual criminal cases are not destroyed during analysis, but are preserved intact for possible presentation in court. Quite aside from, or in addition to, use in court, NAA results can be very helpful in the investigative stage of particular criminal cases. The ultra sensitivity of the method often enables one to analyze evidence specimens that are too tiny for meaningful analysis by more conventional elemental analysis methods. Also, this high sensitivity often enables one to characterize, or individualize, evidence specimens as to the possibility of common origin - via the principle of multi-element trace-constituent characterization

  10. Analysis of optics damage growth at the National Ignition Facility

    Science.gov (United States)

    Liao, Z. M.; Nostrand, M.; Whitman, P.; Bude, J.

    2015-11-01

    Optics damage growth modeling and analysis at the National Ignition Facility (NIF) has been performed on fused silica. We will show the results of single shot growth comparisons, damage site lifetime comparisons as well as growth metrics for each individual NIF beamline. These results help validate the consistency of the damage growth models and allow us to have confidence in our strategic planning in regards to projected optic usage.

  11. Advanced materials analysis facility at CSIRO HIAF laboratory

    Energy Technology Data Exchange (ETDEWEB)

    Kenny, M.J.; Wielunski, L.S.; Baxter, G.R. [CSIRO, Lindfield, NSW (Australia). Applied Physics Div.; Sie, S.H.; Suter, G.F. [CSIRO, North Ryde, NSW (Australia). Exploration and Mining Div.

    1993-12-31

    The HIAF facility at North Ryde, based on a 3 MV Tandetron accelerator has been operating for several years. Initially three ion sources were in operation:- conventional duoplasmatrons for proton and helium beams and a sputter ion source for heavy ions. An electrostatic focusing system was designed and built in-house for providing microbeams. The research emphasis has been largely on microbeam PIXE with particular reference to the mining industry. An AMS system was added in 1990 which prevented the inclusion of the charge exchange canal required for helium beams. The facility has been operated by CSIRO Division of Exploration and Mining. At the beginning of 1992, the lon Beam Technology Group of CSIRO Division of Applied Physics was relocated at Lindfield and became a major user of the HIAF facility. Because the research activities of this group involved Rutherford Backscattering and Channeling, it was necessary to add a helium ion source and a new high vacuum beam line incorporating a precision goniometer. These facilities became operational in the second quarter of 1992. Currently a PIXE system is being added to the chamber containing the goniometer, making the accelerator an extremely versatile one for a wide range of IBA techniques. 3 refs.

  12. Risk management activities at the DOE Class A reactor facilities

    Energy Technology Data Exchange (ETDEWEB)

    Sharp, D.A. [Westinghouse Savannah River Co., Aiken, SC (United States); Hill, D.J. [Argonne National Lab., IL (United States); Linn, M.A. [Oak Ridge National Lab., TN (United States); Atkinson, S.A. [EG and G Idaho, Inc., Idaho Falls, ID (United States); Hu, J.P. [Brookhaven National Lab., Upton, NY (United States)

    1993-12-31

    The probabilistic risk assessment (PRA) and risk management group of the Association for Excellence in Reactor Operation (AERO) develops risk management initiatives and standards to improve operation and increase safety of the DOE Class A reactor facilities. Principal risk management applications that have been implemented at each facility are reviewed. The status of a program to develop guidelines for risk management programs at reactor facilities is presented.

  13. Risk management activities at the DOE Class A reactor facilities

    Energy Technology Data Exchange (ETDEWEB)

    Sharp, D.A. (Westinghouse Savannah River Co., Aiken, SC (United States)); Hill, D.J. (Argonne National Lab., IL (United States)); Linn, M.A. (Oak Ridge National Lab., TN (United States)); Atkinson, S.A. (EG and G Idaho, Inc., Idaho Falls, ID (United States)); Hu, J.P. (Brookhaven National Lab., Upton, NY (United States))

    1993-01-01

    The probabilistic risk assessment (PRA) and risk management group of the Association for Excellence in Reactor Operation (AERO) develops risk management initiatives and standards to improve operation and increase safety of the DOE Class A reactor facilities. Principal risk management applications that have been implemented at each facility are reviewed. The status of a program to develop guidelines for risk management programs at reactor facilities is presented.

  14. Risk management activities at the DOE Class A reactor facilities

    International Nuclear Information System (INIS)

    The probabilistic risk assessment (PRA) and risk management group of the Association for Excellence in Reactor Operation (AERO) develops risk management initiatives and standards to improve operation and increase safety of the DOE Class A reactor facilities. Principal risk management applications that have been implemented at each facility are reviewed. The status of a program to develop guidelines for risk management programs at reactor facilities is presented

  15. BUSTED BUTTE TEST FACILITY GROUND SUPPORT CONFIRMATION ANALYSIS

    International Nuclear Information System (INIS)

    The main purpose and objective of this analysis is to confirm the validity of the ground support design for Busted Butte Test Facility (BBTF). The highwall stability and adequacy of highwall and tunnel ground support is addressed in this analysis. The design of the BBTF including the ground support system was performed in a separate document (Reference 5.3). Both in situ and seismic loads are considered in the evaluation of the highwall and the tunnel ground support system. In this analysis only the ground support designed in Reference 5.3 is addressed. The additional ground support installed (still work in progress) by the constructor is not addressed in this analysis. This additional ground support was evaluated by the A/E during a site visit and its findings and recommendations are addressed in this analysis

  16. A decision analysis of an exploratory studies facility

    International Nuclear Information System (INIS)

    An Exploratory Studies Facility (ESF) is planned to support the characterization of a potential site for a high-level nuclear waste repository at Yucca Mountain, NV. The selection of a design for the ESF is a critical decision, because the ESF design may affect the accuracy of characterization testing and subsequent repository design. The assist the design process, a comparative evaluation was conducted to rank 34 alternative relied on techniques from formal decision analysis, including decision trees and multiattribute utility analysis (MUA). The results helped to identify favorable design features and convinced the Department of Energy to adopt the top-ranked option as the preferred ESF design

  17. Spatial Distribution Characteristics of Healthcare Facilities in Nanjing: Network Point Pattern Analysis and Correlation Analysis

    Directory of Open Access Journals (Sweden)

    Jianhua Ni

    2016-08-01

    Full Text Available The spatial distribution of urban service facilities is largely constrained by the road network. In this study, network point pattern analysis and correlation analysis were used to analyze the relationship between road network and healthcare facility distribution. The weighted network kernel density estimation method proposed in this study identifies significant differences between the outside and inside areas of the Ming city wall. The results of network K-function analysis show that private hospitals are more evenly distributed than public hospitals, and pharmacy stores tend to cluster around hospitals along the road network. After computing the correlation analysis between different categorized hospitals and street centrality, we find that the distribution of these hospitals correlates highly with the street centralities, and that the correlations are higher with private and small hospitals than with public and large hospitals. The comprehensive analysis results could help examine the reasonability of existing urban healthcare facility distribution and optimize the location of new healthcare facilities.

  18. Spatial Distribution Characteristics of Healthcare Facilities in Nanjing: Network Point Pattern Analysis and Correlation Analysis.

    Science.gov (United States)

    Ni, Jianhua; Qian, Tianlu; Xi, Changbai; Rui, Yikang; Wang, Jiechen

    2016-01-01

    The spatial distribution of urban service facilities is largely constrained by the road network. In this study, network point pattern analysis and correlation analysis were used to analyze the relationship between road network and healthcare facility distribution. The weighted network kernel density estimation method proposed in this study identifies significant differences between the outside and inside areas of the Ming city wall. The results of network K-function analysis show that private hospitals are more evenly distributed than public hospitals, and pharmacy stores tend to cluster around hospitals along the road network. After computing the correlation analysis between different categorized hospitals and street centrality, we find that the distribution of these hospitals correlates highly with the street centralities, and that the correlations are higher with private and small hospitals than with public and large hospitals. The comprehensive analysis results could help examine the reasonability of existing urban healthcare facility distribution and optimize the location of new healthcare facilities. PMID:27548197

  19. Spatial Distribution Characteristics of Healthcare Facilities in Nanjing: Network Point Pattern Analysis and Correlation Analysis

    Science.gov (United States)

    Ni, Jianhua; Qian, Tianlu; Xi, Changbai; Rui, Yikang; Wang, Jiechen

    2016-01-01

    The spatial distribution of urban service facilities is largely constrained by the road network. In this study, network point pattern analysis and correlation analysis were used to analyze the relationship between road network and healthcare facility distribution. The weighted network kernel density estimation method proposed in this study identifies significant differences between the outside and inside areas of the Ming city wall. The results of network K-function analysis show that private hospitals are more evenly distributed than public hospitals, and pharmacy stores tend to cluster around hospitals along the road network. After computing the correlation analysis between different categorized hospitals and street centrality, we find that the distribution of these hospitals correlates highly with the street centralities, and that the correlations are higher with private and small hospitals than with public and large hospitals. The comprehensive analysis results could help examine the reasonability of existing urban healthcare facility distribution and optimize the location of new healthcare facilities. PMID:27548197

  20. Californium-252 neutron activation facility at the Savannah River Laboratory

    International Nuclear Information System (INIS)

    A neutron irradiation facility has been established to develop new analytical methods and for the support of research programs. A major component of this facility is a 252Cf source which provides both fission spectrum and thermal neutrons. (U.S.)

  1. DOE standard: Integration of environment, safety, and health into facility disposition activities. Volume 2: Appendices

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-05-01

    This volume contains the appendices that provide additional environment, safety, and health (ES and H) information to complement Volume 1 of this Standard. Appendix A provides a set of candidate DOE ES and H directives and external regulations, organized by hazard types that may be used to identify potentially applicable directives to a specific facility disposition activity. Appendix B offers examples and lessons learned that illustrate implementation of ES and H approaches discussed in Section 3 of Volume 1. Appendix C contains ISMS performance expectations to guide a project team in developing and implementing an effective ISMS and in developing specific performance criteria for use in facility disposition. Appendix D provides guidance for identifying potential Applicable or Relevant and Appropriate Requirements (ARARs) when decommissioning facilities fall under the Comprehensive Environmental Response, Compensation, Liability Act (CERCLA) process. Appendix E discusses ES and H considerations for dispositioning facilities by privatization. Appendix F is an overview of the WSS process. Appendix G provides a copy of two DOE Office of Nuclear Safety Policy and Standards memoranda that form the bases for some of the guidance discussed within the Standard. Appendix H gives information on available hazard analysis techniques and references. Appendix I provides a supplemental discussion to Sections 3.3.4, Hazard Baseline Documentation, and 3.3.6, Environmental Permits. Appendix J presents a sample readiness evaluation checklist.

  2. DOE standard: Integration of environment, safety, and health into facility disposition activities. Volume 2: Appendices

    International Nuclear Information System (INIS)

    This volume contains the appendices that provide additional environment, safety, and health (ES and H) information to complement Volume 1 of this Standard. Appendix A provides a set of candidate DOE ES and H directives and external regulations, organized by hazard types that may be used to identify potentially applicable directives to a specific facility disposition activity. Appendix B offers examples and lessons learned that illustrate implementation of ES and H approaches discussed in Section 3 of Volume 1. Appendix C contains ISMS performance expectations to guide a project team in developing and implementing an effective ISMS and in developing specific performance criteria for use in facility disposition. Appendix D provides guidance for identifying potential Applicable or Relevant and Appropriate Requirements (ARARs) when decommissioning facilities fall under the Comprehensive Environmental Response, Compensation, Liability Act (CERCLA) process. Appendix E discusses ES and H considerations for dispositioning facilities by privatization. Appendix F is an overview of the WSS process. Appendix G provides a copy of two DOE Office of Nuclear Safety Policy and Standards memoranda that form the bases for some of the guidance discussed within the Standard. Appendix H gives information on available hazard analysis techniques and references. Appendix I provides a supplemental discussion to Sections 3.3.4, Hazard Baseline Documentation, and 3.3.6, Environmental Permits. Appendix J presents a sample readiness evaluation checklist

  3. Dry Transfer Facility No.1 - Ventilation Confinement Zoning Analysis

    International Nuclear Information System (INIS)

    The purpose of this analysis is to establish the preliminary Ventilation Confinement Zone (VCZ) for the Dry Transfer Facility (DTF). The results of this document is used to determine the air quantities for each VCZ that will eventually be reflected in the development of the Ventilation Flow Diagrams. The calculations contained in this document were developed by D and E/Mechanical-HVAC and are intended solely for the use of the D and E/Mechanical-HVAC department in its work regarding the HVAC system for the Dry Transfer Facility. Yucca Mountain Project personnel from the D and E/Mechanical-HVAC department should be consulted before use of the calculation for purposes other than those stated herein or used by individuals other than authorized personnel in D and E/Mechanical-HVAC department

  4. Safety analysis and code development for nuclear fuel cycle facilities

    International Nuclear Information System (INIS)

    Development effort of computer codes applicable to nuclear fuel cycle facilities for assisting the task of NISA has been carried out. The work consists of 1) verification of criticality safety analysis codes : MVP and SCALE, 2) studies on burn-up credit applied methods, 3) preparation of non-uniformity effect calculation for criticality safety, 4) development of the new convenient library for shielding calculation based on JENDL-3.3 nuclear data, 5) development of a numerical simulation code DYMPL for analyzing abnormal transients of PUREX processes, 6) radiation dose evaluation code development for reprocessing facilities, 7) updating the dose evaluation data for the probabilistic environmental assessment code MACCS2-JF by emergency scenario. (author)

  5. Analysis on the application and actual condition of facilities preservation system in each industry

    International Nuclear Information System (INIS)

    In order to secure the maximum of a company's benefit through increasing the efficiency and the productivity of it. the facility preservation system has been developed and used so that can find it's maximum efficiency with a series of activities which make a plan for, install, maintain, and improve for it. Factories are managed to be classified by operation and maintenance with great interest in the facility preservation in South Korea. and the facilities has taken up much part in the management. But it has not been researched how the facilities affects the management of a company. According to that reasons, the facility preservation is underestimated compared with what it is and is regarded just as a cost. This report has an object to construct a fundamental electronic-database on the facility preservation in order to obtain excellent results in KAERI with researches into the introduction of the TPM technology in South Korea, and analysis the effect of the TPM on a company

  6. Study on activation analysis

    International Nuclear Information System (INIS)

    High purity aluminum has been analyzed by neutron activation analysis. The determination of copper contents is aluminum has been used to evaluate its purity level. A new sensitive method has been developed by using graphite thermal column to reduce or eliminate the interference of 24Na which is generated from 27Al (n,α) 24Na reaction by fast neutron. Influence for activity of 24Na due to above reaction is found to be between 2.3 - 2.8 %. Copper contents in the high purity aluminum come out 0.542±0.084 ppm. In addition, contents of 23 other impurity elements (<0.1 - 0.01 ppm) are measured using general method after detection limit and optimum conditions are established. (author)

  7. Noble Gas Measurement and Analysis Technique for Monitoring Reprocessing Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Charlton, William S

    1999-09-01

    An environmental monitoring technique using analysis of stable noble gas isotopic ratios on-stack at a reprocessing facility was developed. This technique integrates existing technologies to strengthen safeguards at reprocessing facilities. The isotopic ratios are measured using a mass spectrometry system and are compared to a database of calculated isotopic ratios using a Bayesian data analysis method to determine specific fuel parameters (e.g., burnup, fuel type, fuel age, etc.). These inferred parameters can be used by investigators to verify operator declarations. A user-friendly software application (named NOVA) was developed for the application of this technique. NOVA included a Visual Basic user interface coupling a Bayesian data analysis procedure to a reactor physics database (calculated using the Monteburns 3.01 code system). The integrated system (mass spectrometry, reactor modeling, and data analysis) was validated using on-stack measurements during the reprocessing of target fuel from a U.S. production reactor and gas samples from the processing of EBR-II fast breeder reactor driver fuel. These measurements led to an inferred burnup that matched the declared burnup with sufficient accuracy and consistency for most safeguards applications. The NOVA code was also tested using numerous light water reactor measurements from the literature. NOVA was capable of accurately determining spent fuel type, burnup, and fuel age for these experimental results. Work should continue to demonstrate the robustness of this system for production, power, and research reactor fuels.

  8. Noble Gas Measurement and Analysis Technique for Monitoring Reprocessing Facilities

    International Nuclear Information System (INIS)

    An environmental monitoring technique using analysis of stable noble gas isotopic ratios on-stack at a reprocessing facility was developed. This technique integrates existing technologies to strengthen safeguards at reprocessing facilities. The isotopic ratios are measured using a mass spectrometry system and are compared to a database of calculated isotopic ratios using a Bayesian data analysis method to determine specific fuel parameters (e.g., burnup, fuel type, fuel age, etc.). These inferred parameters can be used by investigators to verify operator declarations. A user-friendly software application (named NOVA) was developed for the application of this technique. NOVA included a Visual Basic user interface coupling a Bayesian data analysis procedure to a reactor physics database (calculated using the Monteburns 3.01 code system). The integrated system (mass spectrometry, reactor modeling, and data analysis) was validated using on-stack measurements during the reprocessing of target fuel from a U.S. production reactor and gas samples from the processing of EBR-II fast breeder reactor driver fuel. These measurements led to an inferred burnup that matched the declared burnup with sufficient accuracy and consistency for most safeguards applications. The NOVA code was also tested using numerous light water reactor measurements from the literature. NOVA was capable of accurately determining spent fuel type, burnup, and fuel age for these experimental results. Work should continue to demonstrate the robustness of this system for production, power, and research reactor fuels

  9. Life cycle cost estimation and systems analysis of waste management facilities

    International Nuclear Information System (INIS)

    This paper presents general conclusions from application of a system cost analysis method developed by the United States Department of Energy (DOE), Waste Management Division (WM), Waste Management Facilities Costs Information (WMFCI) program. The WMFCI method has been used to assess the DOE complex-wide management of radioactive, hazardous, and mixed wastes. The Idaho Engineering Laboratory, along with its subcontractor Morrison Knudsen Corporation, has been responsible for developing and applying the WMFCI cost analysis method. The cost analyses are based on system planning level life-cycle costs. The costs for life-cycle waste management activities estimated by WMFCI range from bench-scale testing and developmental work needed to design and construct a facility, facility permitting and startup, operation and maintenance, to the final decontamination, decommissioning, and closure of the facility. For DOE complex-wide assessments, cost estimates have been developed at the treatment, storage, and disposal module level and rolled up for each DOE installation. Discussions include conclusions reached by studies covering complex-wide consolidation of treatment, storage, and disposal facilities, system cost modeling, system costs sensitivity, system cost optimization, and the integration of WM waste with the environmental restoration and decontamination and decommissioning secondary wastes

  10. Environmental criteria in industrial facility siting decisions: An analysis

    Science.gov (United States)

    Briassoulis, Helen

    1995-03-01

    Environmental criteria are increasingly being employed in industrial facility siting, usually in multicriteria decision contexts, together with technical, socioeconomic and other considerations. This paper analyzes the criteria that have appeared in the published literature with the aim to offer guidance for their selection in a particular facility location problem. A number of alternative classification schemes are presented, first based on the most prevalent classification dimensions which are: the economy-environment relationship, purpose of the criterion, complexity, spatial and temporal scale, and level of measurement. The major scheme adopted draws from the economy-environment relationship and assigns environmental critera to one of seven categories: general characterizations of the environment, characteristics of individual environmental components, measures of the magnitude and intensity of the activity, measures of the nature and volume of wastes which are produced, characteristics of impacts on separate environmental media and receptors, general characterizations of environmental quality, and impacts on humans. Within each of these categories the criteria are analyzed in terms of the other classification dimensions. Common characteristics among the various criteria as well as future trends in their development are identified. This paper also discusses the most important factors conditioning the choice of criteria in a particular facility siting context and outlines a systematic procedure for their selection in real-world applications.

  11. Waste Receiving and Processing (WRAP) Facility Final Safety Analysis Report (FSAR)

    International Nuclear Information System (INIS)

    The Waste Receiving and Processing Facility (WRAP), 2336W Building, on the Hanford Site is designed to receive, confirm, repackage, certify, treat, store, and ship contact-handled transuranic and low-level radioactive waste from past and present U.S. Department of Energy activities. The WRAP facility is comprised of three buildings: 2336W, the main processing facility (also referred to generically as WRAP); 2740W, an administrative support building; and 2620W, a maintenance support building. The support buildings are subject to the normal hazards associated with industrial buildings (no radiological materials are handled) and are not part of this analysis except as they are impacted by operations in the processing building, 2336W. WRAP is designed to provide safer, more efficient methods of handling the waste than currently exist on the Hanford Site and contributes to the achievement of as low as reasonably achievable goals for Hanford Site waste management

  12. Receiving Basin for Offsite Fuels and the Resin Regeneration Facility Safety Analysis Report, Executive Summary

    International Nuclear Information System (INIS)

    The Safety Analysis Report documents the safety authorization basis for the Receiving Basin for Offsite Fuels (RBOF) and the Resin Regeneration Facility (RRF) at the Savannah River Site (SRS). The present mission of the RBOF and RRF is to continue in providing a facility for the safe receipt, storage, handling, and shipping of spent nuclear fuel assemblies from power and research reactors in the United States, fuel from SRS and other Department of Energy (DOE) reactors, and foreign research reactors fuel, in support of the nonproliferation policy. The RBOF and RRF provide the capability to handle, separate, and transfer wastes generated from nuclear fuel element storage. The DOE and Westinghouse Savannah River Company, the prime operating contractor, are committed to managing these activities in such a manner that the health and safety of the offsite general public, the site worker, the facility worker, and the environment are protected

  13. Waste Receiving and Processing (WRAP) Facility Final Safety Analysis Report (FSAR)

    Energy Technology Data Exchange (ETDEWEB)

    TOMASZEWSKI, T.A.

    2000-04-25

    The Waste Receiving and Processing Facility (WRAP), 2336W Building, on the Hanford Site is designed to receive, confirm, repackage, certify, treat, store, and ship contact-handled transuranic and low-level radioactive waste from past and present U.S. Department of Energy activities. The WRAP facility is comprised of three buildings: 2336W, the main processing facility (also referred to generically as WRAP); 2740W, an administrative support building; and 2620W, a maintenance support building. The support buildings are subject to the normal hazards associated with industrial buildings (no radiological materials are handled) and are not part of this analysis except as they are impacted by operations in the processing building, 2336W. WRAP is designed to provide safer, more efficient methods of handling the waste than currently exist on the Hanford Site and contributes to the achievement of as low as reasonably achievable goals for Hanford Site waste management.

  14. Receiving Basin for Offsite Fuels and the Resin Regeneration Facility Safety Analysis Report, Executive Summary

    Energy Technology Data Exchange (ETDEWEB)

    Shedrow, C.B.

    1999-11-29

    The Safety Analysis Report documents the safety authorization basis for the Receiving Basin for Offsite Fuels (RBOF) and the Resin Regeneration Facility (RRF) at the Savannah River Site (SRS). The present mission of the RBOF and RRF is to continue in providing a facility for the safe receipt, storage, handling, and shipping of spent nuclear fuel assemblies from power and research reactors in the United States, fuel from SRS and other Department of Energy (DOE) reactors, and foreign research reactors fuel, in support of the nonproliferation policy. The RBOF and RRF provide the capability to handle, separate, and transfer wastes generated from nuclear fuel element storage. The DOE and Westinghouse Savannah River Company, the prime operating contractor, are committed to managing these activities in such a manner that the health and safety of the offsite general public, the site worker, the facility worker, and the environment are protected.

  15. Waste Encapsulation and Storage Facility mission analysis report

    International Nuclear Information System (INIS)

    This report defines the mission for the Waste Encapsulation and Storage Facility (WESF). It contains summary information regarding the mission analysis which was performed by holding workshops attended by relevant persons involved in the WESF operations. The scope of the WESF mission is to provide storage of Cesium (Cs) and Strontium (Sr) capsules, previously produced at WESF, until every capsule has been removed from the facility either to another storage location, for disposal or for beneficial use by public or private enterprises. Since the disposition of the capsules has not yet been determined, they may be stored at WESF for many years, even decades. The current condition of the WESF facility must be upgraded and maintained to provide for storage which is safe, cost effective, and fully compliant with DOE direction as well as federal, state, and local laws and regulations. The Cs capsules produced at WESF were originally released to private enterprises for uses such as the sterilization of medical equipment; but because of the leakage of one capsule, all are being returned. The systems, subsystems, and equipment not required for the storage mission will be available for use by other projects or private enterprises. Beyond the storage of the Cs and Sr capsules, no future mission for the WESF has been identified

  16. Asymmetrical sabotage tactics, nuclear facilities/materials, and vulnerability analysis

    International Nuclear Information System (INIS)

    Full text: The emerging paradigm of a global community wherein post-modern political violence is a fact of life that must be dealt with by safety and security planners is discussed. This paradigm shift in the philosophy of terrorism is documented by analysis of the emerging pattern of asymmetrical tactics being employed by terrorists. Such philosophical developments in violent political movements suggest a shift in the risks that security and safety personnel must account for in their planning for physical protection of fixed site nuclear source facilities like power generation stations and the eventual storage and transportation of the by-products of these facilities like spent nuclear fuel and other high level wastes. This paper presents a framework for identifying these new political realities and related threat profiles, suggests ways in which security planners and administrators can design physical protection practices to meet these emerging threats, and argues for global adoption of standards for the protection of nuclear facilities that could be used as a source site from which terrorists could inflict a mass contamination event and for standards related to the protection of the waste materials that can be used in the production of radiological weapons of mass victimization. (author)

  17. The Argonne Wakefield Accelerator Facility Status and Recent Activities

    CERN Document Server

    Conde, Manoel; Gai, Wei; Jing, Chunguang; Konecny, Richard; Liu Wan Ming; Power, John G; Wang, Haitao; Yusof, Zikri

    2005-01-01

    The Argonne Wakefield Accelerator Facility (AWA) is dedicated to the study of electron beam physics and the development of accelerating structures based on electron beam driven wakefields. In order to carry out these studies, the facility employs a photocathode RF gun capable of generating electron beams with high bunch charges (up to 100 nC) and short bunch lengths. This high intensity beam is used to excite wakefields in the structures under investigation. The wakefield structures presently under development are dielectric loaded cylindrical waveguides with operating frequencies of 7.8 or 15.6 GHz. The facility is also used to investigate the generation and propagation of high brightness electron beams. Presently under investigation, is the use of photons with energies lower than the work function of the cathode surface (Schottky-enabled photoemission), aimed at generating electron beams with low thermal emittance. Novel electron beam diagnostics are also developed and tested at the facility. The AWA electr...

  18. A test facility of active alignment system at KEK

    International Nuclear Information System (INIS)

    A test facility with one control axis has been constructed at KEK to investigate a super-accurate alignment technique for the JLC (Japan Linear Collider) project. The facility consists of a stabilized laser system and a vibration control stage equipped with piezo transducers. Results of the first test show that the distance of about 28 cm is kept stable to 50 nm or better up to the frequency of 20 Hz, against the sine wave disturbance with a 500 nm amplitude

  19. Criticality analysis for uranium-scrap recycling facilities

    International Nuclear Information System (INIS)

    KNFC planned to build a uranium scrap recycling facility in order to make its fuel manufacturing process efficient. An engineering design has been done by Human and Technologies Corp. during 6 months of the last year. A criticality analysis has been performed with Kyunghee University and report was reviewed by KINS. This paper summarized a criticality analysis part of this work for licensing. A criticality analysis was done for all processes in scrap recycling system with data from design specifications based on reasonable assumptions. As the first step, parametric study was done for a normal operational condition in order to find crucial variables which would be sensitive to the criticality safety. Hypothetical accident was also simulated with double contingency principle and multi-parameter control principle. Calculation was performed with Monte Carlo code, MCNP-4C/2 with point data cross section data library

  20. Inventory difference analysis at Los Alamos Plutonium Facility

    International Nuclear Information System (INIS)

    The authors have developed a prototype computer program that reads directly the inventory entries from a Microsoft Access data base. Based on historical data, the program then displays temporal trends and constructs a library of rules that encapsulates the system behavior. The following analysis of inventory data is illustrated by using a combination of realistic and simulated facility examples. Potential payoffs of this methodology include a reduction in time and resources needed to perform statistical tests and broad applicability to Department of Energy needs--for example, treaty verification

  1. Seismic analysis of the mirror fusion test facility shielding vault

    International Nuclear Information System (INIS)

    This report presents a seismic analysis of the vault in Building 431 at Lawrence Livermore National Laboratory which houses the mirror Fusion Test Facility. The shielding vault structure is approximately 120 ft long by 80 ft wide and is constructed of concrete blocks approximately 7 x 7 x 7 ft. The north and south walls are approximately 53 ft high and the east wall is approximately 29 ft high. These walls are supported on a monolithic concrete foundation that surrounds a 21-ft deep open pit. Since the 53-ft walls appeared to present the greatest seismic problem they were the first investigated

  2. Fast Flux Test Facility final safety analysis report. Amendment 73

    Energy Technology Data Exchange (ETDEWEB)

    Gantt, D.A.

    1993-08-01

    This report provides Final Safety Analysis Report (FSAR) Amendment 73 for incorporation into the Fast Flux Test Facility (FFTR) FSAR set. This page change incorporates Engineering Change Notices (ECNs) issued subsequent to Amendment 72 and approved for incorparoration before May 6, 1993. These changes include: Chapter 3, design criteria structures, equipment, and systems; chapter 5B, reactor coolant system; chapter 7, instrumentation and control systems; chapter 9, auxiliary systems; chapter 11, reactor refueling system; chapter 12, radiation protection and waste management; chapter 13, conduct of operations; chapter 17, technical specifications; chapter 20, FFTF criticality specifications; appendix C, local fuel failure events; and appendix Fl, operation at 680{degrees}F inlet temperature.

  3. UK fusion technology experimental activities at the ASP 14 MeV neutron irradiation facility

    Energy Technology Data Exchange (ETDEWEB)

    Packer, L.W., E-mail: lee.packer@ccfe.ac.uk [EURATOM/Culham Centre for Fusion Energy (CCFE) Fusion Association, Culham Science Centre, Abingdon, OX14 3DB (United Kingdom); Gilbert, M. [EURATOM/Culham Centre for Fusion Energy (CCFE) Fusion Association, Culham Science Centre, Abingdon, OX14 3DB (United Kingdom); Hughes, S. [Atomic Weapons Establishment (AWE), Aldermaston, Reading, Berkshire, RG7 4PR (United Kingdom); Lilley, S.; Pampin, R.; Sublet, J.-C. [EURATOM/Culham Centre for Fusion Energy (CCFE) Fusion Association, Culham Science Centre, Abingdon, OX14 3DB (United Kingdom)

    2012-08-15

    Highlights: Black-Right-Pointing-Pointer A technical overview of the ASP 14 MeV facility in presented, including the accelerator, the irradiation cell and the recently re-commissioned fast sample extraction system. Black-Right-Pointing-Pointer Activation experimental results obtained using high purity elemental- and fusion-relevant material foils, are detailed. These include a list of measured short-lived reaction products from 54 experiments conducted using gamma spectrometry methods. Black-Right-Pointing-Pointer Derived results from Zr and Au experiments are highlighted; the need to improve the data is identified using C/E plots derived from the European Activation File 2010 cross section evaluation. - Abstract: In support of the technological requirements for fusion, the UK fusion technology programme is conducting several experiments using the ASP DT neutron irradiation facility at Aldermaston. The present experimental programme covers two key areas of technology development: improving the quality of nuclear cross-section data required for fusion-related materials; and benchmarking fusion nuclear analysis tools such as the shutdown activation dose system MC-R2S. The first of these areas is the focus of this paper. The work presented here gives a technical overview of the ASP facility, including the accelerator, the irradiation cell, the recently re-commissioned fast sample extraction system and ancillary radiation metrology equipment. Results from preliminary activation experiments using high purity elemental- and fusion-relevant material foils, are presented. These include measurements of short-lived activation products conducted via gamma spectrometry methods.

  4. 12 CFR 204.122 - Secondary market activities of international banking facilities.

    Science.gov (United States)

    2010-01-01

    ... 12 Banks and Banking 2 2010-01-01 2010-01-01 false Secondary market activities of international banking facilities. 204.122 Section 204.122 Banks and Banking FEDERAL RESERVE SYSTEM BOARD OF GOVERNORS OF...) Interpretations § 204.122 Secondary market activities of international banking facilities. (a) Questions have...

  5. Facile Preparation of Ag/NiO Composite Nanosheets and Their Antibacterial Activity

    Science.gov (United States)

    Shi, Cui-E.; Pan, Lu; Wang, Cheng-Run; He, Yi; Wu, Yong-Feng; Xue, Sai-Sai

    2016-01-01

    Sheet-like precursors of NiO and Ag/NiO with different Ag contents were synthesized by a facile and easily controlled hydrothermal method. The NiO and Ag/NiO composite nanosheets were prepared by calcination of the corresponding precursors at 400°C for 3 h. The as-synthesized samples were characterized by thermogravimetric analysis, x-ray diffraction, transmission electron microscopy, and scanning electron microscopy. The antibacterial activity of NiO and Ag/NiO composites to several gram-positive and gram-negative bacteria was examined. Results showed that NiO nanosheets hardly exhibited antibacterial activity; however, Ag/NiO composites displayed higher activity even with low Ag content.

  6. Safety analysis of the 700-horsepower combustion test facility

    Energy Technology Data Exchange (ETDEWEB)

    Berkey, B.D.

    1981-05-01

    The objective of the program reported herein was to provide a Safety Analysis of the 700 h.p. Combustion Test Facility located in Building 93 at the Pittsburgh Energy Technology Center. Extensive safety related measures have been incorporated into the design, construction, and operation of the Combustion Test Facility. These include: nitrogen addition to the coal storage bin, slurry hopper, roller mill and pulverizer baghouse, use of low oxygen content combustion gas for coal conveying, an oxygen analyzer for the combustion gas, insulation on hot surfaces, proper classification of electrical equipment, process monitoring instrumentation and a planned remote television monitoring system. Analysis of the system considering these factors has resulted in the determination of overall probabilities of occurrence of hazards as shown in Table I. Implementation of the recommendations in this report will reduce these probabilities as indicated. The identified hazards include coal dust ignition by hot ductwork and equipment, loss of inerting within the coal conveying system leading to a coal dust fire, and ignition of hydrocarbon vapors or spilled oil, or slurry. The possibility of self-heating of coal was investigated. Implementation of the recommendations in this report will reduce the ignition probability to no more than 1 x 10/sup -6/ per event. In addition to fire and explosion hazards, there are potential exposures to materials which have been identified as hazardous to personal health, such as carbon monoxide, coal dust, hydrocarbon vapors, and oxygen deficient atmosphere, but past monitoring experience has not revealed any problem areas. The major environmental hazard is an oil spill. The facility has a comprehensive spill control plan.

  7. Activation analysis in Europe: present and future perspectives

    International Nuclear Information System (INIS)

    A survey is given of the present-day European contribution to activation analysis, covering neutron activation analysis (NAA), charged particle activation analysis (CPAA) and photon activation analysis (PAA). Attention is paid to the available irradiation facilities, in particular nuclear reactors, cyclotrons and Van de Graaff accelerators, and linear electron accelerators. Mention is made of progress in fundamental fields, but the attention is especially focussed on practical applications: environmental, geochemical/cosmochemical, biological/medical, and high-purity materials. Eventually, the role of activation analysis in research projects of the Commission of the European Communities (CEC) and in the Reference Materials program of the Community Bureau of Reference (BCR) is emphasized

  8. Introduction of Prompt Gamma Thermal Neutron Activation Analysis at CARR

    Institute of Scientific and Technical Information of China (English)

    WANG; Xing-hua; XIAO; Cai-jin; ZHANG; Gui-ying; YAO; Yong-gang; JIN; Xiang-chun; WANG; Ping-sheng; HUA; Long; NI; Bang-fa

    2013-01-01

    CARR will provide with maximal neutron flux in Asia,the third of the world.By using the high quality neutron beam and the advanced international experience,Prompt Gamma Neutron Activation Analysis(PGNAA)facility will be setup at high level.PGNAA on CARR will promote the development of nuclear analysis technology and improve Chinese status in the nuclear analysis field.

  9. Distribution of physical activity facilities in Scotland by small area measures of deprivation and urbanicity

    Directory of Open Access Journals (Sweden)

    Ogilvie David

    2010-10-01

    Full Text Available Abstract Background The aim of this study was to examine the distribution of physical activity facilities by area-level deprivation in Scotland, adjusting for differences in urbanicity, and exploring differences between and within the four largest Scottish cities. Methods We obtained a list of all recreational physical activity facilities in Scotland. These were mapped and assigned to datazones. Poisson and negative binomial regression models were used to investigate associations between the number of physical activity facilities relative to population size and quintile of area-level deprivation. Results The results showed that prior to adjustment for urbanicity, the density of all facilities lessened with increasing deprivation from quintiles 2 to 5. After adjustment for urbanicity and local authority, the effect of deprivation remained significant but the pattern altered, with datazones in quintile 3 having the highest estimated mean density of facilities. Within-city associations were identified between the number of physical activity facilities and area-level deprivation in Aberdeen and Dundee, but not in Edinburgh or Glasgow. Conclusions In conclusion, area-level deprivation appears to have a significant association with the density of physical activity facilities and although overall no clear pattern was observed, affluent areas had fewer publicly owned facilities than more deprived areas but a greater number of privately owned facilities.

  10. Systems Analysis of Safeguards Effectiveness in a Uranium Conversion Facility

    Energy Technology Data Exchange (ETDEWEB)

    Elayat, H A; Lambert, H; O' Connell, W J

    2004-06-16

    The U.S. Department of Energy (DOE) is interested in developing tools and methods for potential U.S. use in designing and evaluating safeguards systems. For this goal several DOE National Laboratories are defining the characteristics of typical facilities of several size scales, and the safeguards measures and instrumentation that could be applied. Lawrence Livermore National Laboratory is providing systems modeling and analysis of facility and safeguards operations, diversion path generation, and safeguards system effectiveness. The constituent elements of diversion scenarios are structured using directed graphs (digraphs) and fault trees. Safeguards indicator probabilities are based on sampling statistics and/or measurement accuracies. Scenarios are ranked based on value and quantity of material removed and the estimated probability of non-detection. Significant scenarios, especially those involving timeliness or randomly varying order of events, are transferred to simulation analysis. Simulations show the range of conditions encountered by the safeguards measurements and inspections, e.g., the quantities of intermediate materials in temporary storage and the time sequencing of material flow. Given a diversion campaign, simulations show how much the range of the same parameters observed by the safeguards system can differ from the base-case range. The combination of digraphs, fault trees, statistics and simulation constitute a method for evaluation of the estimated benefit of alternate or additional safeguards equipment or features. A generic example illustrates the method.

  11. Optimization model for air quality analysis in energy facility siting

    Energy Technology Data Exchange (ETDEWEB)

    Emanuel, W. R.; Murphy, B. D.; Huff, D. D.; Begovich, C. L.; Hurt, J. F.

    1977-09-01

    The siting of energy facilities on a regional scale is discussed with particular attention to environmental planning criteria. A multiple objective optimization model is proposed as a framework for the analysis of siting problems. Each planning criterion (e.g., air quality, water quality, or power demand) is treated as an objective function to be minimized or maximized subject to constraints in this optimization procedure. The formulation of the objective functions is illustrated by the development of a siting model for the minimization of human exposure to air pollutants. This air quality siting model takes the form of a linear programming problem. A graphical analysis of this type of problem, which provides insight into the nature of the siting model, is given. The air quality siting model is applied to an illustrative siting example for the Tennessee Valley area.

  12. Operation And Maintenance In Facilities Management Practices: A Gap Analysis In Malaysia

    Directory of Open Access Journals (Sweden)

    Zawawi Zuraihana Ahmad

    2016-01-01

    Full Text Available Facilities management in Malaysia has started as early as 1990s during the development of mega projects such as Putrajaya in 1999 [8, 9]. During this period, Malaysia was introduced to an integrated property management and maintenance services known as facilities management. However, its implementation according to the standard practice is still being disputed. The purpose of facilities management standard practices is to provide the facility management profession with a leading reference on facilities management activities and standards. Therefore, the determination of how far the gap in FM current practice is essential to help our FM industry. Thus, the aim of this study is to establish the gap between the current practices and the standard practices and also how far the gap should be satisfied. A set of questionnaire was designed upon literature and previous research done to gather the required information. The study is subjected to FM organizations in private sectors and only the personnel at management level are assessed. There were certified that most of the practices that assessed by means of gap analysis had an acceptable result which the gap between the current practices and the standard practices are not too far.

  13. Service activities of chemical analysis division

    International Nuclear Information System (INIS)

    Progress of the Division during the year of 1988 was described on the service activities for various R and D projects carrying out in the Institute, for the fuel fabrication and conversion plant, and for the post-irradiation examination facility. Relevant analytical methodologies developed for the chemical analysis of an irradiated fuel, safeguards chemical analysis, and pool water monitoring were included such as chromatographic separation of lanthanides, polarographic determination of dissolved oxygen in water, and automation on potentiometric titration of uranium. Some of the laboratory manuals revised were also included in this progress report. (Author)

  14. Assessment of activity-based pyroprocess costs for an engineering-scale facility in Korea

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Sung Ki; Ko, Won Il [Nuclear Fuel Cycle Analysis Department, Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of); Bang, Sung Sig [Dept. of Business and Technology Management, Korea Advanced Institute of Science and Technology, Daejeon (Korea, Republic of)

    2015-12-15

    This study set the pyroprocess facility at an engineering scale as a cost object, and presented the cost consumed during the unit processes of the pyroprocess. For the cost calculation, the activity based costing (ABC) method was used instead of the engineering cost estimation method, which calculates the cost based on the conceptual design of the pyroprocess facility. The calculation results demonstrate that the pyroprocess facility's unit process cost is $194/kgHM for pretreatment, $298/kgHM for electrochemical reduction, $226/kgHM for electrorefining, and $299/kgHM for electrowinning. An analysis demonstrated that the share of each unit process cost among the total pyroprocess cost is as follows: 19% for pretreatment, 29% for electrochemical reduction, 22% for electrorefining, and 30% for electrowinning. The total unit cost of the pyroprocess was calculated at $1,017/kgHM. In the end, electrochemical reduction and the electrowinning process took up most of the cost, and the individual costs for these two processes was found to be similar. This is because significant raw material cost is required for the electrochemical reduction process, which uses platinum as an anode electrode. In addition, significant raw material costs are required, such as for Li3PO4, which is used a lot during the salt purification process.

  15. Activation analysis in forensic studies

    International Nuclear Information System (INIS)

    Application of neutron activation analysis in forensics are grouped into 3 categories: firearms-discharge applications, elemental analysis of other nonbiological evidence materials (paint, other), and elemental analysis of biological evidence materials (multielemental analysis of hair, analysis of hair for As and Hg). 18 refs

  16. Surface Fire Hazards Analysis Technical Report-Constructor Facilities

    International Nuclear Information System (INIS)

    The purpose of this Fire Hazards Analysis Technical Report (hereinafter referred to as Technical Report) is to assess the risk from fire within individual fire areas to ascertain whether the U.S. Department of Energy (DOE) fire safety objectives are met. The objectives identified in DOE Order 420.1, Change 2, Facility Safety, Section 4.2, establish requirements for a comprehensive fire and related hazards protection program for facilities sufficient to minimize the potential for: The occurrence of a fire or related event; A fire that causes an unacceptable on-site or off-site release of hazardous or radiological material that will threaten the health and safety of employees, the public, or the environment; Vital DOE programs suffering unacceptable interruptions as a result of fire and related hazards; Property losses from a fire and related events exceeding defined limits established by DOE; and Critical process controls and safety class systems being damaged as a result of a fire and related events

  17. Radiation Shielding Analysis of Electron Beam Accelerator Facility

    International Nuclear Information System (INIS)

    The objective of this technical report are to establish the radiation shielding technology of a high-energy electron accelerator to the facilities which utilize with electron beam. The technologies of electron beam irradiation(300 KeV -10 MeV) demand on the diverse areas of material processing, surface treatment, treatments on foods or food processing, improvement of metal properties, semiconductors, and ceramics, sterilization of medical goods and equipment, treatment and control of contamination and pollution, and so on. In order to acquire safety design for the protection of personnel from the radiations produced by electron beam accelerators, it is important to develop the radiation shielding analysis technology. The shielding analysis are carried out by which define source term, calculation modelling and computer calculations for 2 MeV and 10 MeV accelerators. And the shielding analysis for irradiation dump shield with 10 MeV accelerators are also performed by solving the complex 3-D geometry and long computer run time problem. The technology development of shielding analysis will be contributed to extend the further high energy accelerator development

  18. Business administration of PET facilities. A nationwide survey for prices of PET screening and a cost analysis of three facilities

    International Nuclear Information System (INIS)

    The purpose of this study is to analyze the business administration of positron emission tomography (PET) facilities based on the survey of the price of PET cancer screening and cost analysis of PET examination. The questionnaire survey of the price of PET cancer screening was implemented for all PET facilities in Japan. Cost data of PET examination, including fixed costs and variable costs, were obtained from three different medical institutions. The marked price of the PET cancer screening was yen111,499 in average, and the most popular range of prices was between yen80,000 and yen90,000. Costs of PET per examination were accounted for yen110,675, yen79,158 and yen111,644 in facility A, B and C, respectively. The results suggested that facilities with two or more PET/CT per a cyclotron could only secure profits. In Japan, the boom in PET facility construction could not continue in accordance with increasing number of PET facilities. It would become more essential to analyze the appropriate distribution of PET facilities and the adequate amount of PET procedures from the perspective of efficient utilization of the PET equipments and supply of PET-related healthcare. (author)

  19. Preliminary Closure Plan for the Immobilized Low Activity Waste (ILAW) Disposal Facility

    Energy Technology Data Exchange (ETDEWEB)

    BURBANK, D.A.

    2000-08-31

    This document describes the preliminary plans for closure of the Immobilized Low-Activity Waste (ILAW) disposal facility to be built by the Office of River Protection at the Hanford site in southeastern Washington. The facility will provide near-surface disposal of up to 204,000 cubic meters of ILAW in engineered trenches with modified RCRA Subtitle C closure barriers.

  20. Preliminary Closure Plan for the Immobilized Low Activity Waste (ILAW) Disposal Facility

    International Nuclear Information System (INIS)

    This document describes the preliminary plans for closure of the Immobilized Low-Activity Waste (ILAW) disposal facility to be built by the Office of River Protection at the Hanford site in southeastern Washington. The facility will provide near-surface disposal of up to 204,000 cubic meters of ILAW in engineered trenches with modified RCRA Subtitle C closure barriers

  1. 25 CFR 170.152 - What transit facilities and activities are eligible for IRR Program funding?

    Science.gov (United States)

    2010-04-01

    ... IRR Program funding? 170.152 Section 170.152 Indians BUREAU OF INDIAN AFFAIRS, DEPARTMENT OF THE... funding? Transit facilities and activities eligible for IRR Program funding include, but are not limited... facilities for use in mass transportation; (f) Third-party contracts for otherwise eligible...

  2. National Ignition Facility Shot Data Analysis Module Guidelines

    Energy Technology Data Exchange (ETDEWEB)

    Azevedo, S; Glenn, S; Lopez, A; Warrick, A; Beeler, R

    2007-10-03

    This document provides the guidelines for software development of modules to be included in Shot Data Analysis (SDA) for the National Ignition Facility (NIF). An Analysis Module is a software entity that groups a set of (typically cohesive) functions, procedures and data structures for performing an analysis task relevant to NIF shot operations. Each module must have its own unique identification (module name), clear interface specifications (data inputs and outputs), and internal documentation. It is vitally important to the NIF Program that all shot-related data be processed and analyzed in a consistent way that is reviewed by scientific and engineering experts. SDA is part of a NIF Integrated Product Team (IPT) whose goal is to provide timely and accurate reporting of shot results to NIF campaign experimentalists. Other elements of the IPT include the Campaign Management Tool (CMT) for configuring experiments, a data archive and provisioning system called CMS, a calibration and configuration database (CDMS), and a shot data visualization tool (SDV). We restrict our scope at this time to guidelines for modules written in Interactive Data Language, or IDL1. This document has sections describing example IDL modules and where to find them, how to set up a development environment, IDL programming guidelines, shared IDL procedures for general use, and revision control.

  3. Safety analysis report for the Cold Vacuum Drying Facility, phase 1, supporting civil/structural construction

    International Nuclear Information System (INIS)

    The US Department of Energy established the K Basins Spent Nuclear Fuel Project to address safety and environmental concerns associated with deteriorating spent nuclear fuel presently stored under water in the Hanford Site's K Basins, which are located near the Columbia River. Recommendations for a series of aggressive projects to construct and operate systems and facilities to manage the safe removal of K Basins fuel were made in WHC-EP-0830, Hanford Spent Nuclear Fuel Recommended Path Forward,' and its subsequent update, WHC-SD-SNF-SP-005, Hanford Spent Nuclear Fuel Project Integrated Process Strategy for K Basins Fuel. The integrated process strategy recommendations include the following process steps: fuel preparation activities at the K Basins, including removing the fuel elements from their K Basin canisters, separating fuel particulate from fuel elements and fuel fragments greater than 0.6 cm (0.25 in.) in any dimension, removing excess sludge from the fuel and fuel fragments by means of flushing, as necessary, and packaging the fuel into multicanister overpacks; removal of free water by draining and vacuum drying at the Cold Vacuum Drying Facility (CVDF), a new facility in the 100 K Area of the Hanford Site. This report is contains the safety analysis for the Cold Vacuum Drying Facility, Phase 1

  4. Analysis of facilities in OFF research in participating countries of CORE Organic

    OpenAIRE

    Nykänen, Arja; Canali, Stefano

    2006-01-01

    Report lists the following research facilities: research farms, experimental fields, on-farm studies, networks, animal research facilities, leaching fields and long-term experiments. Other facilities like facilities for laboratory analyses, food processing, greenhouses, climate chambers and growth cabinets are left out from this analysis, because they are seldom exclusively used for OFF research and because their use for OFF research does not require particular characteristics. On the other h...

  5. Analysis on the Present Status of Conceptually Designed Pyroprocessing Facilities for Determining a Reference Pyroprocessing Facility

    International Nuclear Information System (INIS)

    In this report, pyro processing facility concepts suggested by US, Japan, and Republic of Korea have been summarized and analyzed, and the determination principles were established to determine a reference pyro processing facility concept. Three proposals for a reference pyro processing facility concept were suggested based on these principles. The 1st proposal is based on the GEN-IV PR/PP model except the metal fuel fabrication process. It may be possible to later add the metal fuel fabrication process, UO2 recovery process of Japan, and continuous electrorefining process invented in Republic of Korea to be the generic model including all pyroprocessing facility concepts in the world. The 2nd proposal is based on INL and ANL model which is simple for the most part and has basic essential processes. The 3rd proposal is determined to be the ESPF of KAERI, which is almost identical with that of the 2nd proposal except in regards to utilization of an input accountability tank and continuous electrorefining process and the 3rd proposal is planned to be realized in 7 years. After the review of the IAEA and discussions at 3rd Working Group Meeting held in IAEA headquarters, the 3rd proposal has been determined as the final version of a reference pyroprocessing facility concept

  6. IFMIF - International Fusion Materials Irradiation Facility Conceptual Design Activity/Interim Report

    Energy Technology Data Exchange (ETDEWEB)

    Rennich, M.J.

    1995-12-01

    Environmental acceptability, safety, and economic viability win ultimately be the keys to the widespread introduction of fusion power. This will entail the development of radiation- resistant and low- activation materials. These low-activation materials must also survive exposure to damage from neutrons having an energy spectrum peaked near 14 MeV with annual radiation doses in the range of 20 displacements per atom (dpa). Testing of candidate materials, therefore, requires a high-flux source of high energy neutrons. The problem is that there is currently no high-flux source of neutrons in the energy range above a few MeV. The goal, is therefore, to provide an irradiation facility for use by fusion material scientists in the search for low-activation and damage-resistant materials. An accellerator-based neutron source has been established through a number of international studies and workshops` as an essential step for materials development and testing. The mission of the International Fusion Materials Irradiation Facility (IFMIF) is to provide an accelerator-based, deuterium-lithium (D-Li) neutron source to produce high energy neutrons at sufficient intensity and irradiation volume to test samples of candidate materials up to about a full lifetime of anticipated use in fusion energy reactors. would also provide calibration and validation of data from fission reactor and other accelerator-based irradiation tests. It would generate material- specific activation and radiological properties data, and support the analysis of materials for use in safety, maintenance, recycling, decommissioning, and waste disposal systems.

  7. 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

  8. Activation studies of the light ion beam target development facility

    International Nuclear Information System (INIS)

    Biological dose calculations have been performed for the target chamber of the Target Development Facility (TDF). Placement of an neutron moderator structure in the interior of the target chamber for the moderation of the high energy neutrons has been investigated as a viable option for lowering the biological dose rates of the chamber wall materials, Al6061-T6 and 2 1/4Cr-1Mo steel. Two moderator materials are considered, one made of H-451 graphite and the other of titanium hydride. In particular, a 40% porosity, 1 m thick graphite structure within the aluminum wall reduces the dose rate at the chamber wall outer surface to 13.1 mrem/h at 1 week after shutdown as compared to 1.29 rem/h without the moderator. A suitable maintenance schedule based on the 40% porosity graphite moderator design and on the allowable average dose of 1.25 rem per quarter is presented. (orig.)

  9. Glovebox dismantling activities and decommissioning plan for plutonium fuel fabrication facility

    International Nuclear Information System (INIS)

    The gloveboxes and process equipment used at plutonium fuel handling facilities have had to be replaced due to deterioration or the need to make changes. So far, their removal and replacement has taken place more than 30 times in Plutonium Fuel Center, Japan Nuclear Cycle Development Institute (JNC). In most recent dismantling activities, we removed four giant gloveboxes (total size, 110 cubic meters) which possessed equipment to recover plutonium from mixed oxide (MOX) fuel scraps. We have implemented a number of procedural improvements in dismantling activities and collected various kinds of data, including type and amount of primary and secondary waste from dismantling, relation between waste volume and work force, etc. Plutonium Fuel Fabricating Facility (PFFF) is one of the three plutonium fuel handling facilities in Plutonium Fuel Center, JNC. Its final mission to produce MOX fuels for the advanced thermal reactor 'Fugen' Nuclear Power Station was successfully finished in 2002. Then, we started preparatory activities to draw up a Deactivation and Decommissioning (DD) plan for this facility and to construct a database with the experimental data of glovebox dismantling activities acquired in the past thirty years. The DD schedule for this facility can be broken down into three phases. Phase 1 (to 2010): Stabilization of all the special nuclear materials in the facility and remove them from the facility. Establish new and effective decontamination and volume reduction technologies in order to improve existing methods. Phase 2 (2010-2015): Applying the above-mentioned technologies to some of the glovebox dismantling activities and confirm their adaptability for the project. Draw up a detailed DD plan which meets to various regulations. Phase 3 (2015-2020): Dismantling of all the remaining gloveboxes in the facility and promote research and development of DD technologies for future projects. Decontamination of inner surfaces of the building in order to reuse the

  10. Experiment archive, analysis, and visualization at the National Ignition Facility

    International Nuclear Information System (INIS)

    Highlights: ► We show the computing architecture to manage scientific data from NIF experiments. ► NIF laser “shots” generate GBs of data for sub-microsec events separated by hours. ► Results are archived, analyzed and displayed with parallel and scalable code. ► Data quality and pedigree, based on calibration of each part, are tracked. ► Web-based visualization tools present data across shots and diagnostics. - Abstract: The National Ignition Facility (NIF) at the Lawrence Livermore National Laboratory is the world's most energetic laser, providing a scientific research center to study inertial confinement fusion and matter at extreme energy densities and pressures. A target shot involves over 30 specialized diagnostics measuring critical x-ray, optical and nuclear phenomena to quantify ignition results for comparison with computational models. The Shot Analysis and Visualization System (SAVI) acquires and analyzes target diagnostic data for display within a time-budget of 30 min. Laser and target diagnostic data are automatically loaded into the NIF archive database through clustered software data collection agents. The SAVI Analysis Engine distributes signal and image processing tasks to a Linux cluster where computation is performed. Intermediate results are archived at each step of the analysis pipeline. Data is archived with metadata and pedigree. Experiment results are visualized through a web-based user interface in interactive dashboards tailored to single or multiple shot perspectives. The SAVI system integrates open-source software, commercial workflow tools, relational database and messaging technologies into a service-oriented and distributed software architecture that is highly parallel, scalable, and flexible. The architecture and functionality of the SAVI system will be presented along with examples.

  11. Analysis of a sewage treatment facility using hybrid Petri nets

    NARCIS (Netherlands)

    Ghasemieh, Hamed; Remke, Anne; Haverkort, Boudewijn R.

    2013-01-01

    Waste water treatment facilities clean sewage water from households and industry in several cleaning steps. Such facilities are dimensioned to accommodate a maximum intake. However, in the case of very bad weather conditions or failures of system components the system might not suffice to accommoda

  12. Reactor Accident Analysis Methodology for the Advanced Test Reactor Critical Facility Documented Safety Analysis Upgrade

    International Nuclear Information System (INIS)

    The regulatory requirement to develop an upgraded safety basis for a DOE Nuclear Facility was realized in January 2001 by issuance of a revision to Title 10 of the Code of Federal Regulations Section 830 (10 CFR 830). Subpart B of 10 CFR 830, ''Safety Basis Requirements,'' requires a contractor responsible for a DOE Hazard Category 1, 2, or 3 nuclear facility to either submit by April 9, 2001 the existing safety basis which already meets the requirements of Subpart B, or to submit by April 10, 2003 an upgraded facility safety basis that meets the revised requirements. 10 CFR 830 identifies Nuclear Regulatory Commission (NRC) Regulatory Guide 1.70, ''Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants'' as a safe harbor methodology for preparation of a DOE reactor documented safety analysis (DSA). The regulation also allows for use of a graded approach. This report presents the methodology that was developed for preparing the reactor accident analysis portion of the Advanced Test Reactor Critical Facility (ATRC) upgraded DSA. The methodology was approved by DOE for developing the ATRC safety basis as an appropriate application of a graded approach to the requirements of 10 CFR 830

  13. Analysis of Precision of Activation Analysis Method

    DEFF Research Database (Denmark)

    Heydorn, Kaj; Nørgaard, K.

    1973-01-01

    The precision of an activation-analysis method prescribes the estimation of the precision of a single analytical result. The adequacy of these estimates to account for the observed variation between duplicate results from the analysis of different samples and materials, is tested by the statistic T...

  14. Analysis of the National Ignition Facility ignition hohlraum energetics experiments

    International Nuclear Information System (INIS)

    A series of 40 experiments on the National Ignition Facility (NIF) [E. I. Moses et al., Phys. Plasmas 16, 041006 (2009)] to study energy balance and implosion symmetry in reduced- and full-scale ignition hohlraums was shot at energies up to 1.3 MJ. This paper reports the findings of the analysis of the ensemble of experimental data obtained that has produced an improved model for simulating ignition hohlraums. Last year the first observation in a NIF hohlraum of energy transfer between cones of beams as a function of wavelength shift between those cones was reported [P. Michel et al., Phys. Plasmas 17, 056305 (2010)]. Detailed analysis of hohlraum wall emission as measured through the laser entrance hole (LEH) has allowed the amount of energy transferred versus wavelength shift to be quantified. The change in outer beam brightness is found to be quantitatively consistent with LASNEX [G. B. Zimmerman and W. L. Kruer, Comments Plasma Phys. Controlled Fusion 2, 51 (1975)] simulations using the predicted energy transfer when possible saturation of the plasma wave mediating the transfer is included. The effect of the predicted energy transfer on implosion symmetry is also found to be in good agreement with gated x-ray framing camera images. Hohlraum energy balance, as measured by x-ray power escaping the LEH, is quantitatively consistent with revised estimates of backscatter and incident laser energy combined with a more rigorous non-local-thermodynamic-equilibrium atomic physics model with greater emissivity than the simpler average-atom model used in the original design of NIF targets.

  15. Overview of the Facility Safeguardability Analysis (FSA) Process

    Energy Technology Data Exchange (ETDEWEB)

    Bari, Robert A.; Hockert, John; Wonder, Edward F.; Johnson, Shirley J.; Wigeland, Roald; Zentner, Michael D.

    2011-10-10

    The safeguards system of the International Atomic Energy Agency (IAEA) provides the international community with credible assurance that a State is fulfilling its nonproliferation obligations. The IAEA draws such conclusions from the evaluation of all available information. Effective and cost-efficient IAEA safeguards at the facility level are, and will remain, an important element of this “State-level” approach. Efficiently used, the Safeguards by Design (SBD) methodologies , , , now being developed can contribute to effective and cost-efficient facility-level safeguards. The Facility Safeguardability Assessment (FSA) introduced here supports SBD in three areas. 1. It describes necessary interactions between the IAEA, the State regulator, and the owner / designer of a new or modified facility to determine where SBD efforts can be productively applied, 2. It presents a screening approach intended to identify potential safeguard issues for; a) design changes to existing facilities; b) new facilities similar to existing facilities with approved safeguards approaches, and c) new designs, 3. It identifies resources (the FSA toolkit), such as good practice guides, design guidance, and safeguardability evaluation methods that can be used by the owner/designer to develop solutions for potential safeguards issues during the interactions with the State regulator and IAEA. FSA presents a structured framework for the application of the SBD tools developed in other efforts. The more a design evolves, the greater the probability that new safeguards issues could be introduced. Likewise, for first-of-a-kind facilities or research facilities that involve previously unused processes or technologies, it is reasonable to expect that a number of possible safeguards issues might exist. Accordingly, FSA is intended to help the designer and its safeguards experts identify early in the design process: • Areas where elements of previous accepted safeguards approach(es) may be applied

  16. An analysis of heating, ventilation and air conditioning system for nuclear facilities

    International Nuclear Information System (INIS)

    An analysis of HVAC system was made on various nuclear facilities such as the existing nuclear power plants in Korea, Post Irradiation Examination Facility at KAERI and Midwest Fuel Recovery Plant in USA, to get basic data and information for the design of the spent fuel interim storage facility to be implemented as one of the radwaste management projects. With the results of this study, the HVAC system to be applied to the spent fuel interim storage facility was selected and the major design considerations of the facility were suggested. (Author)

  17. Accidental safety analysis methodology development in decommission of the nuclear facility

    Energy Technology Data Exchange (ETDEWEB)

    Park, G. H.; Hwang, J. H.; Jae, M. S.; Seong, J. H.; Shin, S. H.; Cheong, S. J.; Pae, J. H.; Ang, G. R.; Lee, J. U. [Seoul National Univ., Seoul (Korea, Republic of)

    2002-03-15

    Decontamination and Decommissioning (D and D) of a nuclear reactor cost about 20% of construction expense and production of nuclear wastes during decommissioning makes environmental issues. Decommissioning of a nuclear reactor in Korea is in a just beginning stage, lacking clear standards and regulations for decommissioning. This work accident safety analysis in decommissioning of the nuclear facility can be a solid ground for the standards and regulations. For source term analysis for Kori-1 reactor vessel, MCNP/ORIGEN calculation methodology was applied. The activity of each important nuclide in the vessel was estimated at a time after 2008, the year Kori-1 plant is supposed to be decommissioned. And a methodology for risk analysis assessment in decommissioning was developed.

  18. Stanford Synchrotron Radiation Laboratory 1991 activity report. Facility developments January 1991--March 1992

    International Nuclear Information System (INIS)

    SSRL is a national facility supported primarily by the Department of Energy for the utilization of synchrotron radiation for basic and applied research in the natural sciences and engineering. It is a user-oriented facility which welcomes proposals for experiments from all researchers. The synchrotron radiation is produced by the 3.5 GeV storage ring, SPEAR, located at the Stanford Linear Accelerator Center (SLAC). SPEAR is a fully dedicated synchrotron radiation facility which operates for user experiments 7 to 9 months per year. SSRL currently has 24 experimental stations on the SPEAR storage ring. There are 145 active proposals for experimental work from 81 institutions involving approximately 500 scientists. There is normally no charge for use of beam time by experimenters. This report summarizes the activity at SSRL for the period January 1, 1991 to December 31, 1991 for research. Facility development through March 1992 is included

  19. The interim storage facility with dry storage casks and its safeguards activity

    International Nuclear Information System (INIS)

    Recyclable-Fuel Storage Company (RFS) is constructing an interim storage facility of spent fuel at Recyclable-Fuel Storage Center (RFSC) in Aomori Prefecture. Metallic dry casks are employed to contain the spent fuel from nuclear power plants and to serve for about 50 years in RFSC. Metallic dry casks have already been used for dry cask storage facility at Tokai No.2 power station of Japan Atomic Power Company. But, RFSC is not exactly the same as the dry cask storage facility at Tokai No.2 power station, for example, cask transportation between facilities and no hot cells. Therefore, additional safeguards activities are necessary. The outline of the design and handling of metallic dry casks at RFSC and the currently developing status of safeguards activity such as containment and surveillance for the cask receipt and storage at RFSC, etc are described. (author)

  20. Stanford Synchrotron Radiation Laboratory 1991 activity report. Facility developments January 1991--March 1992

    Energy Technology Data Exchange (ETDEWEB)

    Cantwell, K.; St. Pierre, M. [eds.

    1992-12-31

    SSRL is a national facility supported primarily by the Department of Energy for the utilization of synchrotron radiation for basic and applied research in the natural sciences and engineering. It is a user-oriented facility which welcomes proposals for experiments from all researchers. The synchrotron radiation is produced by the 3.5 GeV storage ring, SPEAR, located at the Stanford Linear Accelerator Center (SLAC). SPEAR is a fully dedicated synchrotron radiation facility which operates for user experiments 7 to 9 months per year. SSRL currently has 24 experimental stations on the SPEAR storage ring. There are 145 active proposals for experimental work from 81 institutions involving approximately 500 scientists. There is normally no charge for use of beam time by experimenters. This report summarizes the activity at SSRL for the period January 1, 1991 to December 31, 1991 for research. Facility development through March 1992 is included.

  1. Immobilized low-activity waste interim storage facility, Project W-465 conceptual design report

    Energy Technology Data Exchange (ETDEWEB)

    Pickett, W.W.

    1997-12-30

    This report outlines the design and Total Estimated Cost to modify the four unused grout vaults for the remote handling and interim storage of immobilized low-activity waste (ILAW). The grout vault facilities in the 200 East Area of the Hanford Site were constructed in the 1980s to support Tank Waste disposal activities. The facilities were to serve project B-714 which was intended to store grouted low-activity waste. The existing 4 unused grout vaults, with modifications for remote handling capability, will provide sufficient capacity for approximately three years of immobilized low activity waste (ILAW) production from the Tank Waste Remediation System-Privatization Vendors (TWRS-PV). These retrofit modifications to the grout vaults will result in an ILAW interim storage facility (Project W465) that will comply with applicable DOE directives, and state and federal regulations.

  2. Immobilized low-activity waste interim storage facility, Project W-465 conceptual design report

    International Nuclear Information System (INIS)

    This report outlines the design and Total Estimated Cost to modify the four unused grout vaults for the remote handling and interim storage of immobilized low-activity waste (ILAW). The grout vault facilities in the 200 East Area of the Hanford Site were constructed in the 1980s to support Tank Waste disposal activities. The facilities were to serve project B-714 which was intended to store grouted low-activity waste. The existing 4 unused grout vaults, with modifications for remote handling capability, will provide sufficient capacity for approximately three years of immobilized low activity waste (ILAW) production from the Tank Waste Remediation System-Privatization Vendors (TWRS-PV). These retrofit modifications to the grout vaults will result in an ILAW interim storage facility (Project W465) that will comply with applicable DOE directives, and state and federal regulations

  3. Waste management facility accident analysis (WASTE ACC) system: software for analysis of waste management alternatives

    International Nuclear Information System (INIS)

    This paper describes the Waste Management Facility Accident Analysis (WASTEunderscoreACC) software, which was developed at Argonne National Laboratory (ANL) to support the US Department of Energy's (DOE's) Waste Management (WM) Programmatic Environmental Impact Statement (PEIS). WASTEunderscoreACC is a decision support and database system that is compatible with Microsoft reg-sign Windows trademark. It assesses potential atmospheric releases from accidents at waste management facilities. The software provides the user with an easy-to-use tool to determine the risk-dominant accident sequences for the many possible combinations of process technologies, waste and facility types, and alternative cases described in the WM PEIS. In addition, its structure will allow additional alternative cases and assumptions to be tested as part of the future DOE programmatic decision-making process. The WASTEunderscoreACC system demonstrates one approach to performing a generic, systemwide evaluation of accident risks at waste management facilities. The advantages of WASTEunderscoreACC are threefold. First, the software gets waste volume and radiological profile data that were used to perform other WM PEIS-related analyses directly from the WASTEunderscoreMGMT system. Second, the system allows for a consistent analysis across all sites and waste streams, which enables decision makers to understand more fully the trade-offs among various policy options and scenarios. Third, the system is easy to operate; even complex scenario runs are completed within minutes

  4. Safety analysis of the Los Alamos critical experiments facility

    International Nuclear Information System (INIS)

    The safety of Pajarito Site critical assembly operations depends upon protection built into the facility, upon knowledgeable personnel, and upon good practice as defined by operating procedures and experimental plans. Distance, supplemented by shielding in some cases, would protect personnel against an extreme accident generating 1019 fissions. During the facility's 28-year history, the direct cost of criticality accidents has translated to a risk of less than $200 per year

  5. Facile synthesis and photocatalytic activity of zinc oxide hierarchical microcrystals

    KAUST Repository

    Xu, Xinjiang

    2013-04-04

    ZnO microcrystals with hierarchical structure have been synthesized by a simple solvothermal approach. The microcrystals were studied by means of X-ray diffraction, transmission electron microscopy, and scanning electron microscopy. Research on the formation mechanism of the hierarchical microstructure shows that the coordination solvent and precursor concentration have considerable influence on the size and morphology of the microstructures. A possible formation mechanism of the hierarchical structure was suggested. Furthermore, the catalytic activity of the ZnO microcrystals was studied by treating low concentration Rhodamine B (RhB) solution under UV light, and research results show the hierarchical microstructures of ZnO display high catalytic activity in photocatalysis, the catalysis process follows first-order reaction kinetics, and the apparent rate constant k = 0.03195 min-1.

  6. Facile synthesis of novel benzotriazole derivatives and their antibacterial activities

    Indian Academy of Sciences (India)

    Jun Wan; Peng-Cheng Lv; Na-Na Tian; Hai-Liang Zhu

    2010-07-01

    A series of benzotriazole derivatives (compounds 1-27) were synthesized, and 24 (compounds 1-5, 9-27) of which were first reported. Their chemical structures were confirmed by means of 1H NMR, IR and elemental analyses, coupled with one selected single crystal structure (compound 1). All the compounds were assayed for antibacterial activities against three Gram positive bacterial strains (Bacillus subtilis, Staphylococcus aureus and Streptococcus faecalis) and three Gram negative bacterial strains (Escherichia coli, Pseudomonas aeruginosa and Enterobacter cloacae) by MTT method. Among the compounds tested, most of them exhibited potent antibacterial activity against the six bacterial strains. Most importantly, compound 3-benzotriazol-1-yl-1-(4-bromo-phenyl)-2-[1,2,4]triazol-1-ylpropan-1-one (19) showed the most favourable antibacterial activity against B. subtilis, S. aureus, S. faecalis, P. aeruginosa, E. coli and E. cloacae with MIC of 1.56 g/mL, 1.56 g/mL, 1.56 g/mL, 3.12 g/mL, 6.25 g/mL and 6.25 g/mL, respectively.

  7. Analysis of a nuclear accident: fission and activation product releases from the Fukushima Daiichi nuclear facility as remote indicators of source identification, extent of release, and state of damaged spent nuclear fuel.

    Science.gov (United States)

    Schwantes, Jon M; Orton, Christopher R; Clark, Richard A

    2012-08-21

    Researchers evaluated radionuclide measurements of environmental samples taken from the Fukushima Daiichi nuclear facility and reported on the Tokyo Electric Power Co. Website following the 2011 tsunami-initiated catastrophe. This effort identified Units 1 and 3 as the major source of radioactive contamination to the surface soil near the facility. Radionuclide trends identified in the soils suggested that: (1) chemical volatility driven by temperature and reduction potential within the vented reactors' primary containment vessels dictated the extent of release of radiation; (2) all coolant had likely evaporated by the time of venting; and (3) physical migration through the fuel matrix and across the cladding wall were minimally effective at containing volatile species, suggesting damage to fuel bundles was extensive. Plutonium isotopic ratios and their distance from the source indicated that the damaged reactors were the major contributor of plutonium to surface soil at the source, decreasing rapidly with distance from the facility. Two independent evaluations estimated the fraction of the total plutonium inventory released to the environment relative to cesium from venting Units 1 and 3 to be ∼0.002-0.004%. This study suggests significant volatile radionuclides within the spent fuel at the time of venting, but not as yet observed and reported within environmental samples, as potential analytes of concern for future environmental surveys around the site. The majority of the reactor inventories of isotopes of less volatile elements like Pu, Nb, and Sr were likely contained within the damaged reactors during venting.

  8. Analysis of a nuclear accident: fission and activation product releases from the Fukushima Daiichi nuclear facility as remote indicators of source identification, extent of release, and state of damaged spent nuclear fuel.

    Science.gov (United States)

    Schwantes, Jon M; Orton, Christopher R; Clark, Richard A

    2012-08-21

    Researchers evaluated radionuclide measurements of environmental samples taken from the Fukushima Daiichi nuclear facility and reported on the Tokyo Electric Power Co. Website following the 2011 tsunami-initiated catastrophe. This effort identified Units 1 and 3 as the major source of radioactive contamination to the surface soil near the facility. Radionuclide trends identified in the soils suggested that: (1) chemical volatility driven by temperature and reduction potential within the vented reactors' primary containment vessels dictated the extent of release of radiation; (2) all coolant had likely evaporated by the time of venting; and (3) physical migration through the fuel matrix and across the cladding wall were minimally effective at containing volatile species, suggesting damage to fuel bundles was extensive. Plutonium isotopic ratios and their distance from the source indicated that the damaged reactors were the major contributor of plutonium to surface soil at the source, decreasing rapidly with distance from the facility. Two independent evaluations estimated the fraction of the total plutonium inventory released to the environment relative to cesium from venting Units 1 and 3 to be ∼0.002-0.004%. This study suggests significant volatile radionuclides within the spent fuel at the time of venting, but not as yet observed and reported within environmental samples, as potential analytes of concern for future environmental surveys around the site. The majority of the reactor inventories of isotopes of less volatile elements like Pu, Nb, and Sr were likely contained within the damaged reactors during venting. PMID:22680069

  9. Standardizing Activation Analysis: New Software for Photon Activation Analysis

    International Nuclear Information System (INIS)

    Photon Activation Analysis (PAA) of environmental, archaeological and industrial samples requires extensive data analysis that is susceptible to error. For the purpose of saving time, manpower and minimizing error, a computer program was designed, built and implemented using SQL, Access 2007 and asp.net technology to automate this process. Based on the peak information of the spectrum and assisted by its PAA library, the program automatically identifies elements in the samples and calculates their concentrations and respective uncertainties. The software also could be operated in browser/server mode, which gives the possibility to use it anywhere the internet is accessible. By switching the nuclide library and the related formula behind, the new software can be easily expanded to neutron activation analysis (NAA), charged particle activation analysis (CPAA) or proton-induced X-ray emission (PIXE). Implementation of this would standardize the analysis of nuclear activation data. Results from this software were compared to standard PAA analysis with excellent agreement. With minimum input from the user, the software has proven to be fast, user-friendly and reliable.

  10. Los Alamos National Laboratory corregated metal pipe saw facility preliminary safety analysis report. Volume I

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1990-09-19

    This Preliminary Safety Analysis Report addresses site assessment, facility design and construction, and design operation of the processing systems in the Corrugated Metal Pipe Saw Facility with respect to normal and abnormal conditions. Potential hazards are identified, credible accidents relative to the operation of the facility and the process systems are analyzed, and the consequences of postulated accidents are presented. The risk associated with normal operations, abnormal operations, and natural phenomena are analyzed. The accident analysis presented shows that the impact of the facility will be acceptable for all foreseeable normal and abnormal conditions of operation. Specifically, under normal conditions the facility will have impacts within the limits posted by applicable DOE guidelines, and in accident conditions the facility will similarly meet or exceed the requirements of all applicable standards. 16 figs., 6 tabs.

  11. FACILE SYNTHESIS, DOCKING STUDIES AND ANTIOXIDANT ACTIVITY OF FGVR

    Directory of Open Access Journals (Sweden)

    Himaja M

    2011-08-01

    Full Text Available A rational designing of linear Tetrapeptide FGVR was done and was synthesized by solution phase peptide synthesis. The docking studies of designed linear tetrapeptide FGVR was carried out by using Schrodinger Software Solutions, USA. Qikprop results show the ligand FGVR mostly act as antihypertensive and anti coagulant properties. The solution phase synthesis of FGVR is carried out by using 1-Ethyl-3-(3-dimethylaminopropyl carbodiimide (EDC as coupling agents and N-Methyl morpholine (NMM as base. Structure of synthesized FGVR was confirmed by FTIR, 1H NMR and Mass spectral data, and evaluated for antioxidant property by using 1,1-diphenyl-2-picryl-hydrazil (DPPH. method and the synthesized peptides FGVR possess moderate antioxidant activity.

  12. RESEARCH AND DEVELOPMENT ACTIVITIES AT SAVANNAH RIVER SITE'S H CANYON FACILITY

    Energy Technology Data Exchange (ETDEWEB)

    Sexton, Lindsay; Fuller, Kenneth

    2013-07-09

    The Savannah River Site's (SRS) H Canyon Facility is the only large scale, heavily shielded, nuclear chemical separations plant still in operation in the U.S. The facility's operations historically recovered uranium-235 (U-235) and neptunium-237 (Np-237) from aluminum-clad, enriched-uranium fuel tubes from Site nuclear reactors and other domestic and foreign research reactors. Today the facility, in conjunction with HB Line, is working to provide the initial feed material to the Mixed Oxide Facility also located on SRS. Many additional campaigns are also in the planning process. Furthermore, the facility has started to integrate collaborative research and development (R&D) projects into its schedule. H Canyon can serve as the appropriate testing location for many technologies focused on monitoring the back end of the fuel cycle, due to the nature of the facility and continued operation. H Canyon, in collaboration with the Savannah River National Laboratory (SRNL), has been working with several groups in the DOE complex to conduct testing demonstrations of novel technologies at the facility. The purpose of conducting these demonstrations at H Canyon will be to demonstrate the capabilities of the emerging technologies in an operational environment. This paper will summarize R&D testing activities currently taking place in H Canyon and discuss the possibilities for future collaborations.

  13. Application of prompt gamma-ray activation analysis

    Energy Technology Data Exchange (ETDEWEB)

    Chung, Yong Sam; Park, Kwang Won; Moon, Jong Hwa; Kim, Sun Ha; Baek, Sung Ryel [Korea Atomic Energy Research Institute, Taejeon (Korea)

    2002-03-01

    This technical report is written for the promotion to utilization of prompt gamma-ray activation analysis facility to be installed in HANARO reactor. It is described for a practical aspects including experiment and equipments, methodology, current status of the research and development and its applications. 102 refs., 32 figs., 25 tabs. (Author)

  14. 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.

  15. 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.

  16. Siting a radioactive waste facility; A pathways analysis case study

    Energy Technology Data Exchange (ETDEWEB)

    Holton, G.A. (JBF Associates, Knoxville, TN (USA)); Meyer, K.R. (Radiological Assessment Corp., Albuquerque, NM (US)); Meyer, H.R. (Chem-Nuclear Systems, Inc., Albuquerque, NM (USA))

    1987-01-01

    A radioactive waste disposal facility was proposed to be sited in Oregon. The waste being considered contained 250 pCi/g of uranium consisting of U-234, U-235, U-236 and U-238 isotopes. No Ra-226 or Th-230 were specified to be present in the waste. As part of the siting effort, the proposed facility had to be qualified with regard to meeting requirements for certain types of administrative exemptions established by the State of Oregon. These exemptions included a quantity exemption, a concentration exemption, several radionuclide-specific exemptions, and a pathways exemption. Presented herein is an exposure assessment that was performed to obtain a pathways exemption.

  17. High-yield neutron activation system for the National Ignition Facility

    Energy Technology Data Exchange (ETDEWEB)

    Barnes, Cris W.; Murphy, Thomas J.; Oertel, John A.

    2001-01-01

    The most accurate absolutely calibrated measurement of the total yield of neutrons from experiments on the National Ignition Facility will be from activation of threshold nuclear reactions. The high-yield neutron activation system is being designed to provide high-accuracy (similar to the {+-}7% achieved on other fusion experiments) linear measurements over a 9-order-of-magnitude dynamic range from the facility limit of {approx}10{sup 19} neutrons/shot down to a minimum of {approx}3x10{sup 10} neutrons/shot. The system design requirements are presented, and a conceptual design to meet those requirements described.

  18. Facile Synthesis and Antimicrobial Evaluation of Some New Heterocyclic Compounds Incorporating a Biologically Active Sulfamoyl Moiety

    Directory of Open Access Journals (Sweden)

    Elham S. Darwish

    2014-01-01

    Full Text Available A facile and convenient synthesis of new heterocyclic compounds containing a sulfamoyl moiety suitable for use as antimicrobial agents was reported. The precursor 3-oxo-3-phenyl-N-(4-sulfamoylphenylpropionamide was coupled smoothly with arenediazonium salt producing hydrazones which reacted with malononitrile or triethylorthoformate affording pyridazine and triazine derivatives, respectively. Also, the reactivity of the same precursor with DMF-DMA was followed by aminotriazole; aromatic aldehydes was followed by hydrazine hydrate, triethylorthoformate, or thiourea affording triazolo[1,5-a]pyrimidine, pyrazole, acrylamide, and dihydropyrimidine derivatives, respectively. On the other hand, treatment of the precursor propionamide with phenyl isothiocyanate and KOH in DMF afforded the intermediate salt which was treated with dilute HCl followed by 2-bromo-1-phenylethanone affording carboxamide derivative. While the same intermediate salt reacted in situ with chloroacetone, ethyl 2-chloroacetate, 3-(2-bromoacetyl-2H-chromen-2-one, methyl iodide, or 2-oxo-N-phenylpropane hydrazonoyl chloride afforded the thiophene, ketene N,S-acetal, and thiadiazole derivatives, respectively. The structure of the new products was established based on elemental and spectral analysis. Antimicrobial evaluation of some selected examples from the synthesized products was carried out whereby four compounds were found to have moderate activities and one compound showed the highest activity.

  19. Survey on Neutron Activation Analysis Activities at the Dalat Nuclear Research Centre

    International Nuclear Information System (INIS)

    The Dalat Nuclear Research Centre (D.N.R.C.) during the past few years has been involved in conducting an activation analysis service. Work has been carried out in collaboration with other organizations. However, no rigid research programme of our own has been established and thus the Radiochemistry Division of the D.N.R.C. has no personnel and special facilities permanently engaged in this field. The equipment and facilities used are shared with other activities within the Division and the whole Centre. The activities in neutron activation analysis at the D.N.R.C. are sporadically revived by requests for analysis. Up to now, such analyses have been performed free of charge. Most of the work was carried out on biological materials such as vegetables, raw natural rubber (RES smoked sheets of different qualities, crepes and dried rubber films obtained from concentrated natural latex) from hevea tree leaves from various clones

  20. Analysis of the formation, expression, and economic impacts of risk perceptions associated with nuclear facilities

    Energy Technology Data Exchange (ETDEWEB)

    Allison, T.; Hunter, S.; Calzonetti, F.J.

    1992-10-01

    This report investigates how communities hosting nuclear facilities form and express perceptions of risk and how these risk perceptions affect local economic development. Information was collected from site visits and interviews with plant personnel, officials of local and state agencies, and community activists in the hosting communities. Six commercial nuclear fuel production facilities and five nuclear facilities operated for the US Department of Energy by private contractors were chosen for analysis. The results presented in the report indicate that the nature of risk perceptions depends on a number of factors. These factors are (1) level of communication by plant officials within the local community, (2) track record of the facility. operator, (3) process through which community and state officials receive information and form opinions, (4) level of economic links each plant has with the local community, and (15) physical characteristics of the facility itself. This report finds that in the communities studied, adverse ask perceptions have not affected business location decisions, employment levels in the local community, tourism, or agricultural development. On the basis of case-study findings, this report recommends that nuclear facility siting programs take the following observations into account when addressing perceptions of risk. First, the quality of a facility`s participation with community activists, interest groups, and state agencies helps to determine the level of perceived risk within a community. Second, the development of strong economic links between nuclear facilities and their host communities will produce a higher level of acceptance of the nuclear facilities.

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

    International Nuclear Information System (INIS)

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1994-09-01

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

  3. Beam positioning stability analysis on large laser facilities

    Institute of Scientific and Technical Information of China (English)

    Fang; Liu; Zhigang; Liu; Liunian; Zheng; Hongbiao; Huang; Jianqiang; Zhu

    2013-01-01

    Beam positioning stability in a laser-driven inertial confinement fusion(ICF) facility is a vital problem that needs to be fixed. Each laser beam in the facility is transmitted in lots of optics for hundreds of meters, and then targeted in a micro-sized pellet to realize controllable fusion. Any turbulence in the environment in such long-distance propagation would affect the displacement of optics and further result in beam focusing and positioning errors. This study concluded that the errors on each of the optics contributed to the target, and it presents an efficient method of enhancing the beam stability by eliminating errors on error-sensitive optics. Optimizations of the optical system and mechanical supporting structures are also presented.

  4. Overview of the Facility Safeguardability Analysis (FSA) Process

    Energy Technology Data Exchange (ETDEWEB)

    Bari, Robert A.; Hockert, John; Wonder, Edward F.; Johnson, Scott J.; Wigeland, Roald; Zentner, Michael D.

    2012-08-01

    Executive Summary The safeguards system of the International Atomic Energy Agency (IAEA) is intended to provide the international community with credible assurance that a State is fulfilling its safeguards obligations. Effective and cost-efficient IAEA safeguards at the facility level are, and will remain, an important element of IAEA safeguards as those safeguards evolve towards a “State-Level approach.” The Safeguards by Design (SBD) concept can facilitate the implementation of these effective and cost-efficient facility-level safeguards (Bjornard, et al. 2009a, 2009b; IAEA, 1998; Wonder & Hockert, 2011). This report, sponsored by the National Nuclear Security Administration’s Office of Nuclear Safeguards and Security, introduces a methodology intended to ensure that the diverse approaches to Safeguards by Design can be effectively integrated and consistently used to cost effectively enhance the application of international safeguards.

  5. Analysis of fuel management in the KIPT neutron source facility

    Energy Technology Data Exchange (ETDEWEB)

    Zhong Zhaopeng, E-mail: zzhong@anl.gov [Nuclear Engineering Division, Argonne National Laboratory, 9700 South Cass Avenue, Argonne, IL 60439 (United States); Gohar, Yousry; Talamo, Alberto [Nuclear Engineering Division, Argonne National Laboratory, 9700 South Cass Avenue, Argonne, IL 60439 (United States)

    2011-05-15

    Research highlights: > Fuel management of KIPT ADS was analyzed. > Core arrangement was shuffled in stage wise. > New fuel assemblies was added into core periodically. > Beryllium reflector could also be utilized to increase the fuel life. - Abstract: Argonne National Laboratory (ANL) of USA and Kharkov Institute of Physics and Technology (KIPT) of Ukraine have been collaborating on the conceptual design development of an experimental neutron source facility consisting of an electron accelerator driven sub-critical assembly. The neutron source driving the sub-critical assembly is generated from the interaction of 100 KW electron beam with a natural uranium target. The sub-critical assembly surrounding the target is fueled with low enriched WWR-M2 type hexagonal fuel assemblies. The U-235 enrichment of the fuel material is <20%. The facility will be utilized for basic and applied research, producing medical isotopes, and training young specialists. With the 100 KW electron beam power, the total thermal power of the facility is {approx}360 kW including the fission power of {approx}260 kW. The burnup of the fissile materials and the buildup of fission products continuously reduce the system reactivity during the operation, decrease the neutron flux level, and consequently impact the facility performance. To preserve the neutron flux level during the operation, the fuel assemblies should be added and shuffled for compensating the lost reactivity caused by burnup. Beryllium reflector could also be utilized to increase the fuel life time in the sub-critical core. This paper studies the fuel cycles and shuffling schemes of the fuel assemblies of the sub-critical assembly to preserve the system reactivity and the neutron flux level during the operation.

  6. Safety Analysis Report: X17B2 beamline Synchrotron Medical Research Facility

    International Nuclear Information System (INIS)

    This report contains a safety analysis for the X17B2 beamline synchrotron medical research facility. Health hazards, risk assessment and building systems are discussed. Reference is made to transvenous coronary angiography

  7. 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

  8. Safety Analysis Report: X17B2 beamline Synchrotron Medical Research Facility

    Energy Technology Data Exchange (ETDEWEB)

    Gmuer, N.F.; Thomlinson, W.

    1990-02-01

    This report contains a safety analysis for the X17B2 beamline synchrotron medical research facility. Health hazards, risk assessment and building systems are discussed. Reference is made to transvenous coronary angiography. (LSP)

  9. 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.

  10. Experimental facility for analysis of biomass combustion characteristics

    Directory of Open Access Journals (Sweden)

    Miljković Biljana M.

    2015-01-01

    Full Text Available The objective of the present article is to present an experimental facility which was designed and built at the Faculty of Technical Sciences in order to study the combustion of different sorts of biomass and municipal solid waste. Despite its apparent simplicity, direct combustion is a complex process from a technological point of view. Conventional combustion equipment is not designed for burning agricultural residues. Devices for agricultural waste combustion are still in the development phase, which means that adequate design solution is presently not available at the world market. In order to construct a boiler and achieve optimal combustion conditions, it is necessary to develop a mathematical model for biomass combustion. Experimental facility can be used for the collection of data necessary for detailed modelling of real grate combustor of solid biomass fuels. Due to the complexity of the grate combustion process, its mathematical models and simulation software tools must be developed and verified using experimental data. This work highlights the properties required for the laboratory facility designed for the examination of biomass combustion and discusses design and operational issues.

  11. The activity record against the 2011 off the pacific coast of Tohoku Earthquake in the Department of Hot Laboratories and Facilities. Part 2. Damage situations and restoration activities for facilities

    International Nuclear Information System (INIS)

    The Department of Hot Laboratories and Facilities in the Nuclear Science Research Institute was supporting research activities on the safety and basic researches for nuclear fuel materials and reactor structural materials and so on. Our department was in charge of operation and management of 11 research facilities including 4 hot laboratories, in which nuclear fuel materials such as uranium and plutonium, and various radioactive isotopes were handled. This document describes the activity record of the detailed damage situations and their restorations of 11 facilities against the 2011 off the Pacific coast of Tohoku earthquake. About the restoration situation of facilities, restoration activities of 8 facilities out of 11 facilities were completed by March 31st, 2013. This document is a continuation of the Part 1 Emergency Activities at Onset (JAEA-Review 2011-048) which was described just after the earthquake. (author)

  12. Style, content and format guide for writing safety analysis documents. Volume 1, Safety analysis reports for DOE nuclear facilities

    Energy Technology Data Exchange (ETDEWEB)

    1994-06-01

    The purpose of Volume 1 of this 4-volume style guide is to furnish guidelines on writing and publishing Safety Analysis Reports (SARs) for DOE nuclear facilities at Sandia National Laboratories. The scope of Volume 1 encompasses not only the general guidelines for writing and publishing, but also the prescribed topics/appendices contents along with examples from typical SARs for DOE nuclear facilities.

  13. Charged-particle activation analysis

    International Nuclear Information System (INIS)

    The paper discusses the methodology and application of nuclear activation with ion beams (19 via 16O(3He,p)18F, 12C(3He,α)11C and 14N(p,α)11C respectively. Recently, triton activation has been shown to be inherently still superior to 3He activation for the determination of oxygen [16O(3H,n)18F]. Lithium, boron, carbon and sulphur can be detected rapidly, nondestructively and with high sensitivity (approximately 0.25ppm for Li and B) via ''quasi-prompt'' activation based on the detection of short-lived, high-energy beta emitters (10ms1H(7Li,n)7Be for example. Nondestructive multielement analysis: Proton activation has the inherent potential for meeting requirements of broad elemental coverage, sensitivity (ppm and sub-ppm range) and selectivity. Up to 30 elements have been determined in Al, Co, Ag, Nb, Rh, Ta and biological samples, using 12-MeV proton activation followed by gamma-ray spectrometry. These capabilities are further enhanced with the counting of X-ray emitters, 28 elements (269) and accuracy using proton activation. 204Pb/206Pb ratios can also be determined with a relative precision of a few per cent. Although charged-particle activation analysis is a well-established trace analysis technique, broad potential capabilities remain to be explored, e.g. those arising from ultrashort-lived nuclides, heavy ion interactions and the combination of delayed and prompt methods. (author)

  14. Automated activation-analysis system

    International Nuclear Information System (INIS)

    An automated delayed neutron counting and instrumental neutron activation analysis system has been developed at Los Alamos National Laboratory's Omega West Reactor (OWR) to analyze samples for uranium and 31 additional elements with a maximum throughput of 400 samples per day. The system and its mode of operation for a large reconnaissance survey are described

  15. An Extended Industry Analysis of the Water Facilities Design Industry in British Columbia

    OpenAIRE

    Ibrahim, Imtiaz

    2012-01-01

    This paper presents an extended industry analysis of British Columbia’s water facilities design industry. The paper analyzes the industry using two models to determine the competitive position, profitability, linkages and competitive scopes of typical engineering consulting firms with water facilities design practices in British Columbia. Strategies to be pursued are then recommended based on these analyses. The extended industry analysis is first conducted using the Five Forces model. This m...

  16. DETERMINANTS OF FARMER-TO-CONSUMER DIRECT MARKET VISITS BY TYPE OF FACILITY: A LOGIT ANALYSIS

    OpenAIRE

    Govindasamy, Ramu; Nayga, Rodolfo M.

    1997-01-01

    This study identifies several socioeconomic and demographic characteristics of individuals who visited farmer-to-consumer direct markets in New Jersey. The analysis was performed for each type of direct marketing facility: pick-your-own farms, roadside stands, farmers' markets, and direct farm markets. Logit analysis results indicate that various factors affect visitation to each type of facility. Factors examined include consumers' consumption and variety of fruits and vegetables, price expe...

  17. Comparing perceived and objectively measured access to recreational facilities as predictors of physical activity in adolescent girls.

    Science.gov (United States)

    Scott, Molly M; Evenson, Kelly R; Cohen, Deborah A; Cox, Christine E

    2007-05-01

    A number of studies in recent years have identified both self-report and objectively measured accessibility of recreational facilities as important predictors of physical activity in youth. Yet, few studies have: (1) examined the relationship between the number and proximity of objectively measured neighborhood physical activity facilities and respondents' perceptions and (2) compared objective and self-report measures as predictors of physical activity. This study uses data on 1,367 6th-grade girls who participated in the Trial of Activity for Adolescent Girls (TAAG) to explore these issues. Girls reported whether nine different types of recreational facilities were easily accessible. These facilities included basketball courts, golf courses, martial arts studios, playing fields, tracks, skating rinks, swimming pools, tennis courts, and dance/gymnastic clubs. Next, geographic information systems (GIS) were used to identify all the parks, schools, and commercial sites for physical activity located within a mile of each girl's home. These sites were then visited to inventory the types of facilities available. Girls wore accelerometers to measure their weekly minutes of non-school metabolic equivalent weighted moderate-to-vigorous physical activity (MW-MVPA). The number of facilities within a half-mile of girls' homes strongly predicted the perception of easy access to seven out of nine facility types. Both individual facility perceptions and the total number of facilities perceived were associated with increased physical activity. For each additional facility perceived, girls clocked 3% more metabolic equivalent weighted moderate-to-vigorous physical activity (p basketball court within a mile of their homes, objective facility measures were otherwise unrelated to physical activity. The results from this study suggest that raising the profile of existing facilities may help increase physical activity among adolescent girls. PMID:17401691

  18. 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.

  19. Research and development activities for transmutation physics experimental facility in J-PARC

    International Nuclear Information System (INIS)

    The Japan Atomic Energy Agency (JAEA) has the plan to construct Transmutation Physics Experimental Facility (TEF-P) under a framework of J-PARC (Japan Proton Accelerator Research Complex) project. TEF-P is a critical assembly which can load Minor Actinide (MA) fuels to perform reactor physics experiments for transmutation systems such as Accelerator-Driven System (ADS) or Fast Reactor (FR). The facility can also use proton beam from the J-PARC accelerator to investigate the controllability of ADS. Current status and activities for TEF-P are described. (author)

  20. Release of radioisotopes and activated materials from nuclear installations and facilities

    Energy Technology Data Exchange (ETDEWEB)

    Manfredi, P.F.; Millaud, J. E.

    2001-11-21

    This report discusses the problems of release of items from facilities and installations where radiation-based activities have been carried out. Several situations are reviewed and their release problems are discussed in detail. Particular attention is devoted to the assessment of the activity of the items to be released. A correct assessment of the activity will help the decision about the final use of the items removed from the radiation-related facility, either re-use, entering the public market, recycling, disposal and storage under different procedures. Even the final destination of the building which hosted the facility needs to be decided on the basis of an accurate assessment of the residual activity. The assessment of the activity, besides being fundamental in guaranteeing a safe approach to the procedures related to the release may result in a substantial profit. This is the case of items whose level of activity is so low that they can be put on the public market, reused or recycled for final product subject to very stringent radiation safety requirements. It will be shown that detector techniques play a fundamental role in the release process. In particular, the low-level counting techniques are fundamental in establishing whether or not the unrestrained release is feasible or not.

  1. Analysis of factors related to man-induced hazard for nuclear facilities

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Young Soon; Jung, Jea Hee; Lee, Keun O; Son, Ki Sang; Wang, Sang Chul; Lee, Chang Jin; Ku, Min Ho; Park, Nam Young [Seoul National Univ. of Technology, Seoul (Korea, Republic of)

    2003-03-15

    This study is to show a guide for installing hazardous facilities adjoined atomic power plant after finding out how much these facilities could impact to the atomic plant. Nuclear power plant is an important facility which is closely connected with public life, industrial activity, and the conduct of public business, so it should not be damaged. Therefore, if there are hazardous and harmful facilities near the plant, then they must be evaluated by the size, the type, and the shape. First of all, any factors that could cause man induced accident must be investigated. And they must be exactly evaluated from how much it will damage the plant facilities. The purpose of this study is to set a technical standard for the installation of these facilities by evaluating the man induced accident. Also, it is to make out the evaluation methods by investigating the hazardous facilities which are placed near the plant. Our country is now using CFR standard : reg. guide and IAEA safety series. However, not only the standard of technology which is related to man induced accident but also the evaluation methods for facilities are not yet layed down. As It was mentioned above, we should evaluate these facilities adequately, and these methods must be made out.

  2. Analysis of the formation, expression, and economic impacts of risk perceptions associated with nuclear facilities

    International Nuclear Information System (INIS)

    This report investigates how communities hosting nuclear facilities form and express perceptions of risk and how these risk perceptions affect local economic development. Information was collected from site visits and interviews with plant personnel, officials of local and state agencies, and community activists in the hosting communities. Six commercial nuclear fuel production facilities and five nuclear facilities operated for the US Department of Energy by private contractors were chosen for analysis. The results presented in the report indicate that the nature of risk perceptions depends on a number of factors. These factors are (1) level of communication by plant officials within the local community, (2) track record of the facility. operator, (3) process through which community and state officials receive information and form opinions, (4) level of economic links each plant has with the local community, and (15) physical characteristics of the facility itself. This report finds that in the communities studied, adverse ask perceptions have not affected business location decisions, employment levels in the local community, tourism, or agricultural development. On the basis of case-study findings, this report recommends that nuclear facility siting programs take the following observations into account when addressing perceptions of risk. First, the quality of a facility's participation with community activists, interest groups, and state agencies helps to determine the level of perceived risk within a community. Second, the development of strong economic links between nuclear facilities and their host communities will produce a higher level of acceptance of the nuclear facilities

  3. A new shunt DC active filter of power supply in a steady high magnetic field facility

    Institute of Scientific and Technical Information of China (English)

    WANG Lei; LIU Xiao-Ning; WANG Can

    2011-01-01

    A DC active power filter is an indispensable part in a high power and high stability power supply system, especially in the power supply system of the Steady High Magnetic Field Facility, which requires that the current ripple should be limited to 50 parts per million. In view of the disadvantages of the series DC active power filter and shunt Pulse Width Modulation DC active filter, this paper puts forward a novel DC active filter by combining the advantages of the transistor regulator and the shunt type. The structure and principle of the new shunt linear active filter are introduced. Meanwhile, the design of several key components that construct the new shunt linear active filter is also analyzed. The simulation model and an experimental prototype of the shunt linear active filter are developed, and the results verify that the parameter design is reasonable and the shunt active filter has a good filter effect.

  4. Upgrades to the Radiochemistry Analysis of Gas Samples (RAGS) diagnostic at the National Ignition Facility

    Science.gov (United States)

    Jedlovec, Donald; Christensen, Kim; Velsko, Carol; Cassata, Bill; Stoeffl, Wolfgang; Shaughnessy, Dawn; Lugten, John; Golod, Tony; Massey, Warren

    2015-08-01

    The Radiochemical Analysis of Gaseous Samples (RAGS) diagnostic apparatus operates at the National Ignition Facility (NIF). At the NIF, xenon is injected into the target chamber as a tracer, used as an analyte in the NIF targets, and generated as a fission product from 14 MeV neutron fission of depleted uranium contained in the NIF hohlraum. Following a NIF shot, the RAGS apparatus used to collect the gas from the NIF target chamber and then to cryogenically fractionate xenon gas. Radio-xenon and other activation products are collected and counted via gamma spectrometry, with the results used to determine critical physics parameters including: capsule areal density, fuel-ablator mix, and nuclear cross sections.

  5. Optics damage modeling and analysis at the National Ignition Facility

    Science.gov (United States)

    Liao, Z. M.; Raymond, B.; Gaylord, J.; Fallejo, R.; Bude, J.; Wegner, P.

    2014-10-01

    Comprehensive modeling of laser-induced damage in optics for the National Ignition Facility (NIF) has been performed on fused silica wedge focus lenses with a metric that compares the modeled damage performance to online inspections. The results indicate that damage models are successful in tracking the performance of the fused silica final optics when properly accounting for various optical finishes and mitigation processes. This validates the consistency of the damage models and allows us to further monitor and evaluate different system parameters that potentially can affect optics performance.

  6. The new prompt gamma-ray activation facility at the Paul Scherrer Institute, Switzerland

    CERN Document Server

    Crittin, M; Schenker, J L

    2000-01-01

    Since October 1997, a new Prompt Gamma-ray Activation (PGA) facility at the neutron spallation source SINQ of the Paul Scherrer Institute (PSI) in Villigen, Switzerland, is operational. The detection system includes a Compton-suppression spectrometer and a pair spectrometer. An interesting feature of this PGA facility is the capillary-based neutron focusing optics which permits scanning of samples and nuclear spectroscopy of isotopes having small capture cross sections. During the beam periods 1997 and 1998, measurements were undertaken to characterize the PGA facility (gamma-ray background, efficiencies of the two spectrometers, analytical sensitivities and detection limits for several elements, performances of the neutron lens). Elemental analyses of standards were also performed.

  7. Safety research activities for Japanese regulations of spent fuel interim storage facilities

    International Nuclear Information System (INIS)

    Japan Nuclear Energy Safety Organization (JNES) carries out (a) preparation of technical documents, (b) technical evaluations of standards (prepared by academic societies), etc. and (c) other R and D activities, to support Nuclear and Industrial Safety Agency (NISA: which prepares necessary regulations for Spent Fuel Interim Storage Facilities). In 2010 fiscal year, JNES completed technical evaluation of the standard (prepared by Atomic Energy Society of Japan) used for the storage facility (dual purpose cask system) being constructed in Mutsu-City and R and D for UT test of welded canister lids which is required for concrete cask storage facilities. And also, JNES is preparing dynamic test of spent fuel to examine the integrity of spent fuel at cask drop accidents and PWR spent fuel storage test to prove long term integrity of spent fuel and cask itself. The results of these tests will be reported in 2011 and 2012 fiscal year. (author)

  8. Survey of active and inactive mines for possible use as in situ test facilities

    Energy Technology Data Exchange (ETDEWEB)

    1976-09-01

    A survey of active and inactive mines which might be useful for radioactive waste storage in situ test experiments was conducted. It was performed for Union Carbide Corporation, Nuclear Division, Office of Waste Isolation. The report covers available information gathered from literature, U.S. Bureau of Mines, the Mining Enforcement and Safety Agency, and a limited number of personal contacts with constructors or operators of facilities. This survey is preliminary in nature and the objective is to develop potential candidate facilities for in situ experiments which warrant further investigation. Included are descriptions of 244 facilities, with all the data about each one which was available within the time restraint of the study. These facility descriptions are additionally indexed by depth of mine, nature of the country rock, mineral mined, and type of entry. A total of 14 inactive mines and 34 active mines has been selected as those most worthy of further investigation for possible service as nuclear waste isolation test facilities. This investigation, being preliminary and having been performed in a very short time period, must be qualified, and the description of the qualification is presented in the body of this report. Qualifications deal primarily with the hazard of having omitted facilities and having incomplete data in some instances. Results indicate sedimentary rock mines of minerals of evaporite origin as a first ranking of preference for in situ testing, followed by other sedimentary rocks and then by mines producing minerals from any type rock where the mine is above the local water table. These are general rules and of course there can be exceptions to them.

  9. Evaporation Of Hanford Waste Treatment Plant Direct Feed Low Activity Waste Effluent Management Facility Core Simulant

    Energy Technology Data Exchange (ETDEWEB)

    Adamson, D. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Nash, C. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Mcclane, D. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); McCabe, D. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

    2016-09-01

    The Hanford Waste Treatment and Immobilization Plant (WTP) Low Activity Waste (LAW) vitrification facility will generate an aqueous condensate recycle stream (LAW Melter Off-Gas Condensate, LMOGC) from the off-gas system. The baseline plan for disposition of this stream during full WTP operations is to send it to the WTP Pretreatment Facility, where it will be blended with LAW, concentrated by evaporation, and recycled to the LAW vitrification facility. However, during the Direct Feed LAW (DFLAW) scenario, planned disposition of this stream is to evaporate it in a new evaporator, in the Effluent Management Facility (EMF), and then return it to the LAW melter. It is important to understand the composition of the effluents from the melter, and new evaporator so that the disposition of these streams can be accurately planned and accommodated. Furthermore, alternate disposition of the LMOGC stream would eliminate recycling of problematic components, and would reduce the need for closely integrated operation of the LAW melter and the Pretreatment Facilities. Long-term implementation of this option after WTP start-up would decrease the LAW vitrification mission duration and quantity of glass waste, amongst the other operational complexities such a recycle stream presents. In order to accurately plan for the disposition path, it is key to experimentally determine the fate of contaminants. To do this, testing is needed to accurately account for the buffering chemistry of the components, determine the achievable evaporation end point, identify insoluble solids that form, and determine the distribution of key regulatory-impacting constituents.

  10. Economic Feasibility Analysis of the Application of Geothermal Energy Facilities to Public Building Structures

    Directory of Open Access Journals (Sweden)

    Sangyong Kim

    2014-03-01

    Full Text Available This study aims to present an efficient plan for the application of a geothermal energy facility at the building structure planning phase. Energy consumption, energy cost and the primary energy consumption of buildings were calculated to enable a comparison of buildings prior to the application of a geothermal energy facility. The capacity for energy savings and the costs related to the installation of such a facility were estimated. To obtain more reliable criteria for economic feasibility, the lifecycle cost (LCC analysis incorporated maintenance costs (reflecting repair and replacement cycles based on construction work specifications of a new renewable energy facility and initial construction costs (calculated based on design drawings for its practical installation. It is expected that the findings of this study will help in the selection of an economically viable geothermal energy facility at the building construction planning phase.

  11. Radioactive waste package assay facility. Volume 2. Investigation of active neutron and active gamma interrogation

    International Nuclear Information System (INIS)

    Volume 2 of this report describes the theoretical and experimental work carried out at Harwell on active neutron and active gamma interrogation of 500 litre cemented intermediate level waste drums. The design of a suitable neutron generating target in conjunction with a LINAC was established. Following theoretical predictions of likely neutron responses, an experimental assay assembly was built. Responses were measured for simulated drums of ILW, based on CAGR, Magnox and PCM wastes. Good correlations were established between quantities of 235-U, nat-U and D2O contained in the drums, and the neutron signals. Expected sensitivities are -1g of fissile actinide and -100g of total actinide. A measure of spatial distribution is obtainable. The neutron time spectra obtained during neutron interrogation were more complex than expected, and more analysis is needed. Another area of discrepancy is the difference between predicted and measured thermal neutron flux in the drum. Clusters of small 3He proportional counters were found to be much superior for fast neutron detection than larger diameter counters. It is necessary to ensure constancy of electron beam position relative to target(s) and drum, and prudent to measure the target neutron or gamma output as appropriate. 59 refs., 77 figs., 11 tabs

  12. A facile reflux procedure to increase active surface sites form highly active and durable supported palladium@platinum bimetallic nanodendrites

    Science.gov (United States)

    Wang, Qin; Li, Yingjun; Liu, Baocang; Xu, Guangran; Zhang, Geng; Zhao, Qi; Zhang, Jun

    2015-11-01

    A series of well-dispersed bimetallic Pd@Pt nanodendrites uniformly supported on XC-72 carbon black are fabricated by using different capping agents. These capping agents are essential for the branched morphology control. However, the surfactant adsorbed on the nanodendrites surface blocks the access of reactant molecules to the active surface sites, and the catalytic activities of these bimetallic nanodendrites are significantly restricted. Herein, a facile reflux procedure to effectively remove the capping agent molecules without significantly affecting their sizes is reported for activating supported nanocatalysts. More significantly, the structure and morphology of the nanodendrites can also be retained, enhancing the numbers of active surface sites, catalytic activity and stability toward methanol and ethanol electro-oxidation reactions. The as-obtained hot water reflux-treated Pd@Pt/C catalyst manifests superior catalytic activity and stability both in terms of surface and mass specific activities, as compared to the untreated catalysts and the commercial Pt/C and Pd/C catalysts. We anticipate that this effective and facile removal method has more general applicability to highly active nanocatalysts prepared with various surfactants, and should lead to improvements in environmental protection and energy production.

  13. Cross-sectional association of the number of neighborhood facilities assessed using postal code with objectively measured physical activity: the Saku cohort study.

    Science.gov (United States)

    Yasunaga, Akitomo; Murakami, Haruka; Morita, Akemi; Deura, Kijyo; Aiba, Naomi; Watanabe, Shaw; Miyachi, Motohiko

    2016-01-01

    Objectives The aim of this study was to examine the association between the number of neighborhood facilities that were assessed according to postal code and objectively measured physical activity by using an accelerometer in community-dwelling Japanese people.Methods The participants included 1,274 Japanese people aged 30-84 years from the Saku cohort study. As neighborhood facilities related to physical activity, we extracted information regarding train stations, supermarkets/convenience stores, postal offices/banks, hospitals/clinics, public offices/community centers, cultural facilities/public children's houses, parks, and sports facilities by using each participant's postal code from the online version of the iTownPages directory published by Nippon Telegraph and Telephone Corporation (NTT) and the official homepage of the Saku City Government Office. We measured each participant's physical activity level using an accelerometer, and calculated the average daily step count and the average weekly period of moderate-to-vigorous intensity (≥3 metabolic equivalents of tasks [METs]) physical activity. The association between two selected physical activity-related variables and the numbers of eight types of neighborhood facilities were analyzed by multivariate logistic regression analysis for people aged 30-64 years and for those aged over 65 years.Results On multivariate logistic regression analysis, meeting the 23 METs h/week of moderate-to-vigorous intensity physical activity was significantly and positively associated with the number of supermarkets/convenience stores in the neighborhood in both age groups. In addition, meeting the desired daily step count outlined in the Japanese National Health Promotion guidelines was positively related to the number of postal offices/banks for people aged over 65 years.Conclusion The results of this study suggest that a sufficient number of neighborhood facilities (i.e., stores, banks, and postal offices) is closely

  14. The safety attitudes of people who use multi-purpose recreation facilities as a physical activity setting.

    Science.gov (United States)

    Finch, Caroline F; Otago, Leonie; White, Peta; Donaldson, Alex; Mahoney, Mary

    2011-06-01

    Multi-purpose recreation facilities (MPRFs) are a popular setting for physical activity and it is therefore important that they are safe for all patrons. However, the attitudes of MPRF users towards safety are a potential barrier to the success of injury prevention programmes implemented within MPRFs. This article reports a survey of the safety attitudes of over 700 users of four indoor MPRFs. Factor analysis of 12 five-point Likert scale statements showed that the attitudes clustered around three major dimensions - the importance of safety, the benefits of safety and the perceptions of injury risk. Together, these three dimensions accounted for 49% of the variability in the attitudes. More than 85% of respondents agreed/strongly agreed that: safety was an important aspect of physical activity participation; being injured affected enjoyment of physical activity; people should adopt appropriate safety measures for all physical activity; and individuals were responsible for their own safety. The MPRF users, particularly women and older people, were generally safety conscious, believed in adopting safety measures, and were willing to take responsibility for their own safety. Facility managers can be confident that if they provide evidence-based injury prevention interventions in these settings, then users will respond appropriately and adopt the promoted behaviours.

  15. Fire hazards analysis of transuranic waste storage and assay facility

    Energy Technology Data Exchange (ETDEWEB)

    Busching, K.R., Westinghouse Hanford

    1996-07-31

    This document analyzes the fire hazards associated with operations at the Central Waste Complex. It provides the analysis and recommendations necessary to ensure compliance with applicable fire codes.

  16. Guidelines for job and task analysis for DOE nuclear facilities

    International Nuclear Information System (INIS)

    The guidelines are intended to be responsive to the need for information on methodology, procedures, content, and use of job and task analysis since the establishment of a requirement for position task analysis for Category A reactors in DOE 5480.1A, Chapter VI. The guide describes the general approach and methods currently being utilized in the nuclear industry and by several DOE contractors for the conduct of job and task analysis and applications to the development of training programs or evaluation of existing programs. In addition other applications for job and task analysis are described including: operating procedures development, personnel management, system design, communications, and human performance predictions

  17. Battery Test Facility- Electrochemical Analysis and Diagnostics Laboratory

    Data.gov (United States)

    Federal Laboratory Consortium — The Electrochemical Analysis and Diagnostics Laboratory (EADL) provides battery developers with reliable, independent, and unbiased performance evaluations of their...

  18. A Strategic Analysis of a Facility Supply Distributor in British Columbia

    OpenAIRE

    Brooks, Derek

    2014-01-01

    This paper presents a business level strategic analysis of RST Corporation’s facility supplydivision, in British Columbia Canada.The facility supply industry is in decline. Firms find it increasingly difficult to achieveprofitability. Despite its decline, this industry will provide opportunities for a smaller number offirms with the correct strategy to take advantage of them. This paper explores the industryenvironment, RST’s resources, current strategy, and performance. It then goes on to de...

  19. Final safety analysis report (FSAR) for waste receiving and processing (WRAP) facility

    International Nuclear Information System (INIS)

    This safety analysis report provides a summary description of the WRAP Facility, focusing on significant safety-related characteristics of the location and facility design. This report demonstrates that adherence to the safety basis wi11 ensure necessary operational safety considerations have been addressed sufficiently and justifies the adequacy of the safety basis in protecting the health and safety of the public, workers, and the environment

  20. An Analysis of Marketing Strategies of an Integrated Facility Services Company : The Case of ISS, Sweden

    OpenAIRE

    Amanze, Collins Nwakanma; B.K.A, Sondengam

    2008-01-01

    TOPIC: An Analysis of Marketing Strategies of an Integrated Facility Services Company: The Case of ISS, Sweden AUTHORS: Collins Nwakanma Amanze, Sondengam B.K.A SUPERVISOR: Anders Hederstierna COURSE: Master Thesis in Business Administration DEPARTMENT: School of Management, Blekinge Institute of Technology, Sweden PROGRAMME: Masters in Business Administration (MBA) PURPOSE: The purpose of our research is to understand how Integrated Facility service companies (using ISS, Sweden as our focus)...

  1. 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

  2. Analysis of marketing communications in the selected accommodation facilities

    OpenAIRE

    Uhrová, Pavlína

    2010-01-01

    The aim of this thesis is an analysis of marketing communication in selected accommodation and suggest possible changes. For this purpose I chose the hotel U Sladka. Estimation of marketing communication was made on the basis of information supplied by directors, employees and the hotel's own observations. An analysis of the present situation results that the hotel uses these elements of promotion: advertising, sales promotion, public relations, sponsorship, trade fairs and personal selling.D...

  3. Applied research and development of neutron activation analysis

    Energy Technology Data Exchange (ETDEWEB)

    Chung, Yong Sam; Moon, Jong Hwa; Kim, Sun Ha; Baek, Sung Ryel; Kim, Young Gi; Jung, Hwan Sung; Park, Kwang Won; Kang, Sang Hun; Lim, Jong Myoung

    2003-05-01

    The aims of this project are to establish the quality control system of Neutron Activation Analysis(NAA) due to increase of industrial needs for standard analytical method and to prepare and identify the standard operation procedure of NAA through practical testing for different analytical items. R and D implementations of analytical quality system using neutron irradiation facility and gamma-ray measurement system and automation of NAA facility in HANARO research reactor are as following ; 1) Establishment of NAA quality control system for the maintenance of best measurement capability and the promotion of utilization of HANARO research reactor 2) Improvement of analytical sensitivity for industrial applied technologies and establishment of certified standard procedures 3) Standardization and development of Prompt Gamma-ray Activation Analysis (PGAA) technology.

  4. Applied research and development of neutron activation analysis

    International Nuclear Information System (INIS)

    The aims of this project are to establish the quality control system of Neutron Activation Analysis(NAA) due to increase of industrial needs for standard analytical method and to prepare and identify the standard operation procedure of NAA through practical testing for different analytical items. R and D implementations of analytical quality system using neutron irradiation facility and gamma-ray measurement system and automation of NAA facility in HANARO research reactor are as following ; 1) Establishment of NAA quality control system for the maintenance of best measurement capability and the promotion of utilization of HANARO research reactor 2) Improvement of analytical sensitivity for industrial applied technologies and establishment of certified standard procedures 3) Standardization and development of Prompt Gamma-ray Activation Analysis (PGAA) technology

  5. Practical aspects of operating a neutron activation analysis laboratory

    International Nuclear Information System (INIS)

    This book is intended to advise in everyday practical problems related to operating a neutron activation analysis (NAA) laboratory. It gives answers to questions like ''what to use NAA for'', ''how to find relevant research problems'', ''how to find users for the technique'', ''how to estimate the cost of the analysis and how to finance the work'', ''how to organize the work in a rational way'' and ''how to perform the quality control''. It gives advice in choosing staff, equipment, and consumables and how to design facilities and procedures according to need and available resources. Potential applications of economic or environmental importance, reactor facilities, counting and measuring equipment of the lab, cooperation with other analytical groups and competitiveness of NAA are discussed by experienced analysts. The compiled 8 tables of data useful for neutron activation analysts are a valuable asset for research labs as well as industrial quality control units. Refs, figs and tabs

  6. The contribution of pharmaceutically active compounds from healthcare facilities to a receiving sewage treatment plant in Canada.

    Science.gov (United States)

    Kleywegt, Sonya; Pileggi, Vince; Lam, Yuet Ming; Elises, Alan; Puddicomb, Aaron; Purba, Gurminder; Di Caro, Joanne; Fletcher, Tim

    2016-04-01

    Concentrations and percent loadings of pharmaceutically active compounds (PhACs) and other emerging contaminants released from healthcare facilities (2 hospitals and a long-term care facility) to a sewage treatment plant (STP) in a large urban sewershed were evaluated. An additional hospital outside the sewershed was also monitored. Fourteen of the 24 steroids/hormones and 88 of the 117 PhACs and emerging contaminants were detected at least once. Commonly used substances, including cotinine, caffeine and its metabolite 1,7-dimethylxanthine, ibuprofen and naproxen (analgesics), venlafaxine (antidepressant), and N,N-diethyl-meta-toluamide (insect repellant), were detected in all samples at all sites. Concentrations detected in the large specialty hospital outside the sewershed were similar to those within the sewershed. Cytotoxic drugs (tamoxifen and cyclophosphamide) and x-ray contrast media (iopamidol and diatrizoic acid) were infrequently detected in hospital effluents. Analysis for antibiotics indicated that azithromycin, clarithromycin, ciprofloxacin, erythromycin, ofloxacin, and sulfamethoxazole were consistently detected in hospital wastewaters, as was triclosan (antibacterial agent). Fifteen compounds individually contributed greater than 1% to the total PhAC and emerging contaminant load to the STP from the 2 hospitals in the sewershed, and 9 compounds in the STP effluent exceeded ecotoxicological criteria. The present survey demonstrates that point source discharges from healthcare facilities in this sewershed make a small contribution to the overall PhAC and emerging contaminant loading compared with the total concentrations entering the receiving STP.

  7. Synthesis of sulfonated porous carbon nanospheres solid acid by a facile chemical activation route

    Energy Technology Data Exchange (ETDEWEB)

    Chang, Binbin, E-mail: changbinbin806@163.com; Guo, Yanzhen; Yin, Hang; Zhang, Shouren; Yang, Baocheng, E-mail: baochengyang@yahoo.com

    2015-01-15

    Generally, porous carbon nanospheres materials are usually prepared via a template method, which is a multi-steps and high-cost strategy. Here, we reported a porous carbon nanosphere solid acid with high surface area and superior porosity, as well as uniform nanospheical morphology, which prepared by a facile chemical activation with ZnCl{sub 2} using resorcinol-formaldehyde (RF) resins spheres as precursor. The activation of RF resins spheres by ZnCl{sub 2} at 400 °C brought high surface area and large volume, and simultaneously retained numerous oxygen-containing and hydrogen-containing groups due to the relatively low processing temperature. The presence of these functional groups is favorable for the modification of –SO{sub 3}H groups by a followed sulfonation treating with sulphuric acid and organic sulfonic acid. The results of N{sub 2} adsorption–desorption and electron microscopy clearly showed the preservation of porous structure and nanospherical morphology. Infrared spectra certified the variation of surface functional groups after activation and the successful modification of –SO{sub 3}H groups after sulfonation. The acidities of catalysts were estimated by an indirect titration method and the modified amount of –SO{sub 3}H groups were examined by energy dispersive spectra. The results suggested sulfonated porous carbon nanospheres catalysts possessed high acidities and –SO{sub 3}H densities, which endowed their significantly catalytic activities for biodiesel production. Furthermore, their excellent stability and recycling property were also demonstrated by five consecutive cycles. - Graphical abstract: Sulfonated porous carbon nanospheres with high surface area and superior catalytic performance were prepared by a facile chemical activation route. - Highlights: • Porous carbon spheres solid acid prepared by a facile chemical activation. • It owns high surface area, superior porosity and uniform spherical morphology. • It possesses

  8. Special Analysis for Disposal of High-Concentration I-129 Waste in the Intermediate-Level Vaults at the E-Area Low-Level Waste Facility

    International Nuclear Information System (INIS)

    This revision was prepared to address comments from DOE-SR that arose following publication of revision 0. This Special Analysis (SA) addresses disposal of wastes with high concentrations of I-129 in the Intermediate-Level (IL) Vaults at the operating, low-level radioactive waste disposal facility (the E-Area Low-Level Waste Facility or LLWF) on the Savannah River Site (SRS). This SA provides limits for disposal in the IL Vaults of high-concentration I-129 wastes, including activated carbon beds from the Effluent Treatment Facility (ETF), based on their measured, waste-specific Kds

  9. IFMIF : International Fusion Materials Irradiation Facility Conceptual Design Activity: Final report

    International Nuclear Information System (INIS)

    This report documents the results of the Conceptual Design Activity (CDA) on the International Fusion Materials Irradiation Facility (IFMIF), conducted during 1995 and 1996. The activity is under the auspices of the International Energy Agency (IEA) Implementing Agreement for a Programme of Research and Development on Fusion Materials. An IEA Fusion Materials Executive Subcommittee was charged with overseeing the IFMIF-CDA work. Participants in the CDA are the European Union, Japan, and the United States, with the Russian Federation as an associate member

  10. IFMIF : International Fusion Materials Irradiation Facility Conceptual Design Activity: Final report

    Energy Technology Data Exchange (ETDEWEB)

    Martone, M. [ENEA, Centro Ricerche Frascati, Rome (Italy)

    1997-01-01

    This report documents the results of the Conceptual Design Activity (CDA) on the International Fusion Materials Irradiation Facility (IFMIF), conducted during 1995 and 1996. The activity is under the auspices of the International Energy Agency (IEA) Implementing Agreement for a Programme of Research and Development on Fusion Materials. An IEA Fusion Materials Executive Subcommittee was charged with overseeing the IFMIF-CDA work. Participants in the CDA are the European Union, Japan, and the United States, with the Russian Federation as an associate member.

  11. Instrumentation in neutron activation analysis

    International Nuclear Information System (INIS)

    The rise of neutron activation analysis (NAA) as a tool in geochemical research has parallelled advances in detector, multi-channel analyzer, and computer technology. Micro-computers are now being integrated into NAA systems, and gamma-ray spectrometer instrumentation is evolving towards direct-reading systems. The investigator is faced with a wide range of possibilities and choices when equipping or re-equipping a laboratory. The geoscientist is provided with an overview of the available instrumentation and what soon may be feasible. (L.L.)

  12. Instrumental Neutron Activation Analysis Technique using Subsecond Radionuclides

    DEFF Research Database (Denmark)

    Nielsen, H.K.; Schmidt, J.O.

    1987-01-01

    The fast irradiation facility Mach-1 installed at the Danish DR 3 reactor has been used in boron determinations by means of Instrumental Neutron Activation Analysis using12B with 20-ms half-life. The performance characteristics of the system are presented and boron determinations of NBS standard...... reference materials as well as fertilizer materials are compared by literature value and spectrophotometric measurements, respectively. In both cases good agreement is obtained....

  13. Soil-structure interaction for seismic analysis of a nuclear facility

    Energy Technology Data Exchange (ETDEWEB)

    Chen, J.Z.; Rosidi, D. [CH2M Hill Engineering Ltd., Toronto, ON (Canada); Lee, L. [ARES Corp., Toronto, ON (Canada)

    2010-07-01

    If the foundation material of a nuclear facility is not rock or rock-like soil to support the structure, then the effects of soil-structure interaction (SSI) must be considered in the seismic design of the facility. The direct or impedance method is generally used for SSI seismic analysis. For the direct method, the complete soil-foundation-structure system is modeled and analyzed in a single step based on the input of ground motion at the boundaries while the impedance method uses multiple steps to combine two primary causes of SSI, such as the inability of the foundation to match the free-field deformation and the effect of the dynamic response of the structure-foundation system on the movement of the supporting soil. This paper presented a case study for dynamic analysis of a nuclear facility located in a high seismic hazard zone. The direct method and lumped spring models were utilized in dynamic analysis of SSI. The paper discussed the seismic response of the nuclear facility. Specific topics that were discussed related to the analysis model included the structural model and soil spring model. The discussion regarding the soil spring model included the foundation stiffness, shear stiffness, ultimate foundation capacity, and equivalent damping coefficients. Seismic analysis was also outlined, with particular reference to dynamic analysis procedure; input ground motion; and results of seismic analysis. The results demonstrated a slight variation in peak structural response due to effects of foundation stiffness. 10 refs., 1 tab., 4 figs.

  14. Appendix 1. The initial and final state of the nuclear facility and the planned follow-on and time-binding activities to achieve the ultimate state of the nuclear facility in that phase, including their impact on employees of nuclear facilities and surroundings nuclear facility

    International Nuclear Information System (INIS)

    In this chapter the initial and final state of the NPP A-1 and the planned follow-on and time-binding activities to achieve the ultimate state of the nuclear facility in that phase, including their impact on employees of nuclear facilities and surroundings nuclear facility are reviewed.

  15. Linde FUSRAP Site Remediation: Engineering Challenges and Solutions of Remedial Activities on an Active Industrial Facility - 13506

    International Nuclear Information System (INIS)

    The Linde FUSRAP Site (Linde) is located in Tonawanda, New York at a major research and development facility for Praxair, Inc. (Praxair). Successful remediation activities at Linde combines meeting cleanup objectives of radiological contamination while minimizing impacts to Praxair business operations. The unique use of Praxair's property coupled with an array of active and abandoned utilities poses many engineering and operational challenges; each of which has been overcome during the remedial action at Linde. The U.S. Army Corps of Engineers - Buffalo District (USACE) and CABRERA SERVICES, INC. (CABRERA) have successfully faced engineering challenges such as relocation of an aboveground structure, structural protection of an active water line, and installation of active mechanical, electrical, and communication utilities to perform remediation. As remediation nears completion, continued success of engineering challenges is critical as remaining activities exist in the vicinity of infrastructure essential to business operations; an electrical substation and duct bank providing power throughout the Praxair facility. Emphasis on engineering and operations through final remediation and into site restoration will allow for the safe and successful completion of the project. (authors)

  16. Fast flux test facility final safety analysis report amendment 79

    International Nuclear Information System (INIS)

    This document is provided to replace, remove, or add applicable pages to the chapters on: Heat Transport System; Containment and Structures; Auxiliary Systems; Reactor Refueling System; Conduct of Operations; Safety Analysis; Quality Assurance; FFTF Criticality Specifications; and Appendix H's TRIGA Fuel Storage System

  17. Transuranic-contaminated solid waste Treatment Development Facility. Final safety analysis report

    International Nuclear Information System (INIS)

    The Final Safety Analysis Report (FSAR) for the Transuranic-Contaminated Solid-Waste Treatment Facility has been prepared in compliance with the Department of Energy (DOE) Manual Chapter 0531, Safety of Nonreactor Nuclear Facilities. The Treatment Development Facility (TDF) at the Los Alamos Scientific Laboratory is a research and development facility dedicated to the study of radioactive-waste-management processes. This analysis addresses site assessment, facility design and construction, and the design and operating characteristics of the first study process, controlled air incineration and aqueous scrub off-gas treatment with respect to both normal and accident conditions. The credible accidents having potentially serious consequences relative to the operation of the facility and the first process have been analyzed and the consequences of each postulated credible accident are presented. Descriptions of the control systems, engineered safeguards, and administrative and operational features designed to prevent or mitigate the consequences of such accidents are presented. The essential features of the operating and emergency procedures, environmental protection and monitoring programs, as well as the health and safety, quality assurance, and employee training programs are described

  18. Transuranic-contaminated solid waste Treatment Development Facility. Final safety analysis report

    Energy Technology Data Exchange (ETDEWEB)

    Warner, C.L. (comp.)

    1979-07-01

    The Final Safety Analysis Report (FSAR) for the Transuranic-Contaminated Solid-Waste Treatment Facility has been prepared in compliance with the Department of Energy (DOE) Manual Chapter 0531, Safety of Nonreactor Nuclear Facilities. The Treatment Development Facility (TDF) at the Los Alamos Scientific Laboratory is a research and development facility dedicated to the study of radioactive-waste-management processes. This analysis addresses site assessment, facility design and construction, and the design and operating characteristics of the first study process, controlled air incineration and aqueous scrub off-gas treatment with respect to both normal and accident conditions. The credible accidents having potentially serious consequences relative to the operation of the facility and the first process have been analyzed and the consequences of each postulated credible accident are presented. Descriptions of the control systems, engineered safeguards, and administrative and operational features designed to prevent or mitigate the consequences of such accidents are presented. The essential features of the operating and emergency procedures, environmental protection and monitoring programs, as well as the health and safety, quality assurance, and employee training programs are described.

  19. Comparing Perceived and Objectively Measured Access to Recreational Facilities as Predictors of Physical Activity in Adolescent Girls

    OpenAIRE

    Scott, Molly M.; Evenson, Kelly R.; Cohen, Deborah A.; Cox, Christine E.

    2007-01-01

    A number of studies in recent years have identified both self-report and objectively measured accessibility of recreational facilities as important predictors of physical activity in youth. Yet, few studies have: (1) examined the relationship between the number and proximity of objectively measured neighborhood physical activity facilities and respondents’ perceptions and (2) compared objective and self-report measures as predictors of physical activity. This study uses data on 1,367 6th-grad...

  20. Safety research activities for Japanese regulations of spent fuel interim storage facilities

    International Nuclear Information System (INIS)

    Japan Nuclear Energy Safety Organization (JNES) carries out (a) preparation of technical documents, (b) technical evaluations of standards (prepared by academic societies), etc. and (c) other R and D activities, to support Nuclear and Industrial Safety Agency (NISA: which prepares necessary regulations for Spent Fuel Interim Storage Facilities). In 2011 fiscal year, JNES carried out R and D for UT test of welded canister lids which is required for concrete cask storage facilities. And also, JNES carried out dynamic test of spent fuel to examine the integrity of spent fuel at cask drop accidents and PWR spent fuel storage test to prove long term integrity of spent fuel and cask itself. Some of these tests will be carried out in 2012 fiscal year and after. (author)

  1. The physical protection of nuclear material and nuclear facilities including activities to combat nuclear terrorism

    International Nuclear Information System (INIS)

    The paper describes present of physical protection of nuclear facilities and materials in the Czech Republic; the basic concept and regulation in physical protection and the effort made to strengthen the national regulatory programmes; the role of the police as a response force and the role of the new private security companies; the upgrading of the physical protection systems at the different types of the nuclear installations to fulfill the more strict requirements of the new Atomic Law No. 18/1997 Coll. and Regulation No. 144/1997 Coll., on physical protection of nuclear materials and nuclear facilities; activities carried out in connection with governmental decision No. 479 dated 19 May 2004 on National action plan to combat terrorism. (author)

  2. The calibration of DD neutron indium activation diagnostic for Shenguang-III facility

    CERN Document Server

    Song, Zi-Feng; Liu, Zhong-Jie; Zhan, Xia-Yu; Tang, Qi

    2014-01-01

    The indium activation diagnostic was calibrated on an accelerator neutron source in order to diagnose deuterium-deuterium (DD) neutron yields of implosion experiments on Shenguang-III facility. The scattered neutron background of the accelerator room was measured by placing a polypropylene shield in front of indium sample, in order to correct the calibrated factor of this activation diagnostic. The proper size of this shield was given by Monte Carlo simulation software. The affect from some other activated nuclei on the calibration was verified by judging whether the measured curve obeys exponential decay and contrasting the half life of the activated sample. The calibration results showed that the linear range reached up to 100 cps net count rate in the full energy peak of interest, the scattered neutron background of accelerator room was about 9% of the total neutrons and the possible interferences mixed scarcely in the sample. Subtracting the portion induced by neutron background, the calibrated factor of ...

  3. Data analysis for remote monitoring of safeguarded facilities

    International Nuclear Information System (INIS)

    The International Remote Monitoring Project (IRMP) sponsored by the US DOE allows DOE and its international partners to gain experience with the remote collection, transmission, and interpretation of safeguards-relevant data. This paper focuses on the interpretation of the data from these remote monitoring systems. Users of these systems need to be able to ascertain that the remote monitoring system is functioning as expected and that the events generated by the sensors are consistent with declared activity. The initial set of analytical tools being provided for IRMP installations this year include a suite of automatically generated views of user-selected data. The baseline set of tools, with illustrative examples, will be discussed. Plans for near-term enhancements will also be discussed. Finally, the applicability of more advanced analytical techniques such as expert systems will be discussed

  4. Status Report on the Neutron Activation Analysis Activities in the Philippines

    International Nuclear Information System (INIS)

    The Philippines has a one megawatt open-pool type nuclear research reactor which is presently utilized in the conduct of nuclear research and development activities. The reactor is operated by the Philippine Atomic Research Center, the research arm of the Philippine Atomic Energy Commission. The reactor is presently utilized in the production of some radioisotopes, nuclear physics experiments and neutron activation analysis. For activation analysis the facilities available include the two 2 inch pneumatic tubes and a 2-inch central core dry-pipe. Although the reactor has been operative since 1963 it was only in the latter part of 1966 that a neutron activation analysis group was organized and almost immediately the training of personnel and setting up of a radiochemical laboratory and nucleonic counting assembly were initiated. Today, the counting system include a 100 channel analyzer with a 3 x 3 inch Nal(Tl) crystal

  5. CARE-JRA2* Activities on Photo-Injectors and CLIC Test Facility (CTF3)

    CERN Document Server

    Rinolfi, Louis

    2005-01-01

    In the frame of the CARE project, there is a Joint Research Activity (JRA2) called PHIN (PHoto-INjectors). The main objective of this JRA is to perform Research and Development on charge-production by interaction of a laser pulse with material within RF fields and improve or extend existing infrastructures. Another activity of PHIN is the coordination of the activities of various Institutes concerning photo-injectors. A brief review of the work of the eight European laboratories involved in PHIN is presented. One of these R&D topics is the construction of a photo-injector for the CLIC Test Facility (CTF3). In this context the status of CTF3 and its main goals - the demonstration of the feasibility of the key issues of the CLIC two-beam acceleration scheme - is also presented.

  6. Who Enters Campus Recreation Facilities: A Demographic Analysis

    Directory of Open Access Journals (Sweden)

    Paul Rohe Milton

    2011-06-01

    Full Text Available The purpose of this study was to examine student entry into a campus recreation center based on seven demographics (gender, ethnicity, age, class standing, intercollegiate athlete vs. non-athlete, students with self-reported disability vs. non-disability, and campus residence in order to determine who would be most likely to enter the recreation center. Subjects were from a mid-western, four year state-assisted institution with combined enrollment of 23,932 undergraduate and graduate students. Of the 23,932 enrolled, 14,032 students were examined in this study. Information on student entry to the recreation center was collected through the university’s student information system. Data was analyzed and interpreted using chi-square analysis. Results of the study show statistically significant differences in the demographics except the student disability demographic. More males than females, more African Americans than other ethnicities, more traditionally aged (18-25 students than non-traditional students, more underclassmen than seniors, more athletes and non-athletes, more residents than commuters were likely to enter the campus recreation center. The findings in this study could be used by collegiate recreational sport directors and administrators, in the United States and internationally, for future ideas about programming in similar recreation settings.

  7. Analysis facility infrastructure (Tier-3) for ATLAS experiment

    CERN Document Server

    González de la Hoza, S; Ros, E; Sánchez, J; Amorós, G; Fassi, F; Fernández, A; Kaci, M; Lamas, A; Salt, J

    2008-01-01

    In the ATLAS computing model the tiered hierarchy ranged from the Tier-0 (CERN) down to desktops or workstations (Tier-3). The focus on defining the roles of each tiered component has evolved with the initial emphasis on the Tier-0 and Tier-1 definition and roles. The various LHC (Large Hadron Collider) projects, including ATLAS, then evolved the tiered hierarchy to include Tier-2’s (Regional centers) as part of their projects. Tier-3 centres, on the other hand, have been defined as whatever an institution could construct to support their Physics goals using institutional and otherwise leveraged resources and therefore have not been considered to be part of the official ATLAS computing resources. However, Tier-3 centres are going to exist and will have implications on how the computing model should support ATLAS physicists. Tier-3 users will want to access LHC data and simulations and will want to enable their resources to support their analysis and simulation work. This document will define how IFIC (Insti...

  8. Annual Report To Congress. Department of Energy Activities Relating to the Defense Nuclear Facilities Safety Board, Calendar Year 2003

    Energy Technology Data Exchange (ETDEWEB)

    None, None

    2004-02-28

    The Department of Energy (Department) submits an Annual Report to Congress each year detailing the Department’s activities relating to the Defense Nuclear Facilities Safety Board (Board), which provides advice and recommendations to the Secretary of Energy (Secretary) regarding public health and safety issues at the Department’s defense nuclear facilities. In 2003, the Department continued ongoing activities to resolve issues identified by the Board in formal recommendations and correspondence, staff issue reports pertaining to Department facilities, and public meetings and briefings. Additionally, the Department is implementing several key safety initiatives to address and prevent safety issues: safety culture and review of the Columbia accident investigation; risk reduction through stabilization of excess nuclear materials; the Facility Representative Program; independent oversight and performance assurance; the Federal Technical Capability Program (FTCP); executive safety initiatives; and quality assurance activities. The following summarizes the key activities addressed in this Annual Report.

  9. Availability of exercise facilities and physical activity in 2,037 adults: cross-sectional results from the Swedish neighborhood and physical activity (SNAP) study

    OpenAIRE

    Eriksson Ulf; Arvidsson Daniel; Sundquist Kristina

    2012-01-01

    Abstract Background Exercise facilities may have the potential to promote physical activity among residents, and to support an active lifestyle throughout the year. We investigated the association between objectively assessed availability of exercise facilities and objectively assessed physical activity outcomes, and whether time of year had a modifying effect on these associations. Methods A total of 2,037 adults (55% females) wore an accelerometer for seven days. Time spent in moderate to v...

  10. Safety research activities for Japanese regulations of spent fuel interim storage facilities

    International Nuclear Information System (INIS)

    Japan Nuclear Energy Safety Organization (JNES) carries out (a) preparation of technical documents, (b) technical evaluations of standards (prepared by academic societies), etc. and (c) other R and D activities, to support Nuclear Regulation Authority (NRA: which controls the regulations for Spent Fuel Interim Storage Facilities). In 2012 fiscal year, JNES carried out dynamic test of spent fuel to examine the integrity of spent fuel under cask drop accidents, and preparation for PWR spent fuel storage test to prove long term integrity of spent fuel and cask itself. Some of these tests will be also carried out in 2013 fiscal year and after. (author)

  11. Access to water source, latrine facilities and other risk factors of active trachoma in Ankober, Ethiopia.

    Directory of Open Access Journals (Sweden)

    Ilya Golovaty

    Full Text Available OBJECTIVE: This study aims to determine the prevalence and correlates of active trachoma in Ankober, Ethiopia. METHODS: A cross-sectional community-based study was conducted during July 2007. A total of 507 children (ages 1-9 years, from 232 households were included in the study. All children were examined for trachoma by ophthalmic nurses using the WHO simplified clinical grading system. Interviews and observations were used to assess risk factors. Logistic regression procedures were used to determine associations between potential risk factors and signs of active trachoma. RESULTS: Overall, the prevalence of active trachoma was found to be 53.9% (95%CI 49.6%-58.2%. Presence of fly-eye (fly contact with the eyelid margin during eye examination (Odds Ratio (OR = 4.03 95% CI 1.40-11.59, absence of facial cleanliness (OR = 7.59; 95%CI 4.60-12.52, an illiterate mother (OR = 5.88; 95%CI 2.10-15.95, lack of access to piped water (OR = 2.19; 95%CI 1.14-6.08, and lack of access to latrine facilities (OR = 4.36; 95%CI 1.49-12.74 were statistically significantly associated with increased risk of active trachoma. CONCLUSION: Active trachoma among children 1-9 years of age in Ankober is highly prevalent and significantly associated with a number of risk factors including access to water and latrine facilities. Trachoma prevention programs that include improved access to water and sanitation, active fly control, and hygiene education are recommended to lower the burden of trachoma in Ankober, Ethiopia.

  12. Determination of Importance Evaluation for Exploratory Studies Facility (ESF) Subsurface Testing Activities

    International Nuclear Information System (INIS)

    This Determination of Importance Evaluation (DIE) applies to the Subsurface Exploratory Studies Facility (ESF), encompassing the Topopah Spring (TS) Loop from Station 0+00 meters (m) at the North Portal to breakthrough at the South Portal (approximately 78+77 m), and ancillary test and operation support areas including the Enhanced Characterization of the Repository Block (ECRB) Cross Drift. This evaluation applies specifically to site characterization testing activities ongoing and planned in the Subsurface ESF. ESF site characterization activities are being performed to obtain the information necessary to determine whether the Yucca Mountain Site is suitable as a geologic repository for spent nuclear fuel and high-level radioactive waste. A more detailed description of these testing activities is provided in Section 6 of this DIE. Generally, the construction and operation of excavations associated with these testing activities are evaluated in the DIE for the Subsurface ESF (CRWMS M and O 1999a) and the DIE for the ESF ECRB Cross Drift (CRWMS M and O 2000a). The scope of this DIE also entails the proposed Unsaturated Zone (UZ) Transport Test at Busted Butte. Although, not a part of the TS Loop or ECRB Cross Drift, the associated testing activities are Subsurface testing activities. Busted Butte is located to the south south-east of the TS Loop and is outside the Conceptual Controlled Area Boundary (CCAB). These activities provide access to the Calico Hills (CH) geologic structure. In the case of Busted Butte, construction and operation of excavations are evaluated herein (since this activity was not previously evaluated in CRWMS M and O 1999a). The objectives of this DIE are to determine whether Subsurface ESF testing, and associated activities, could potentially impact site characterization testing and/or the waste isolation capabilities of the site. Controls needed to limit any potential impacts are identified in Section 13. The validity and veracity of the

  13. Determination of Importance Evaluation for Exploratory Studies Facility (ESF) Subsurface Testing Activities

    Energy Technology Data Exchange (ETDEWEB)

    C.J. Byrne

    2001-02-20

    This Determination of Importance Evaluation (DIE) applies to the Subsurface Exploratory Studies Facility (ESF), encompassing the Topopah Spring (TS) Loop from Station 0+00 meters (m) at the North Portal to breakthrough at the South Portal (approximately 78+77 m), and ancillary test and operation support areas including the Enhanced Characterization of the Repository Block (ECRB) Cross Drift. This evaluation applies specifically to site characterization testing activities ongoing and planned in the Subsurface ESF. ESF site characterization activities are being performed to obtain the information necessary to determine whether the Yucca Mountain Site is suitable as a geologic repository for spent nuclear fuel and high-level radioactive waste. A more detailed description of these testing activities is provided in Section 6 of this DIE. Generally, the construction and operation of excavations associated with these testing activities are evaluated in the DIE for the Subsurface ESF (CRWMS M&O 1999a) and the DIE for the ESF ECRB Cross Drift (CRWMS M&O 2000a). The scope of this DIE also entails the proposed Unsaturated Zone (UZ) Transport Test at Busted Butte. Although, not a part of the TS Loop or ECRB Cross Drift, the associated testing activities are Subsurface testing activities. Busted Butte is located to the south south-east of the TS Loop and is outside the Conceptual Controlled Area Boundary (CCAB). These activities provide access to the Calico Hills (CH) geologic structure. In the case of Busted Butte, construction and operation of excavations are evaluated herein (since this activity was not previously evaluated in CRWMS M&O 1999a). The objectives of this DIE are to determine whether Subsurface ESF testing, and associated activities, could potentially impact site characterization testing and/or the waste isolation capabilities of the site. Controls needed to limit any potential impacts are identified in Section 13. The validity and veracity of the individual

  14. Sociospatial distribution of access to facilities for moderate and vigorous intensity physical activity in Scotland by different modes of transport

    Directory of Open Access Journals (Sweden)

    Lamb Karen E

    2012-07-01

    Full Text Available Abstract Background People living in neighbourhoods of lower socioeconomic status have been shown to have higher rates of obesity and a lower likelihood of meeting physical activity recommendations than their more affluent counterparts. This study examines the sociospatial distribution of access to facilities for moderate or vigorous intensity physical activity in Scotland and whether such access differs by the mode of transport available and by Urban Rural Classification. Methods A database of all fixed physical activity facilities was obtained from the national agency for sport in Scotland. Facilities were categorised into light, moderate and vigorous intensity activity groupings before being mapped. Transport networks were created to assess the number of each type of facility accessible from the population weighted centroid of each small area in Scotland on foot, by bicycle, by car and by bus. Multilevel modelling was used to investigate the distribution of the number of accessible facilities by small area deprivation within urban, small town and rural areas separately, adjusting for population size and local authority. Results Prior to adjustment for Urban Rural Classification and local authority, the median number of accessible facilities for moderate or vigorous intensity activity increased with increasing deprivation from the most affluent or second most affluent quintile to the most deprived for all modes of transport. However, after adjustment, the modelling results suggest that those in more affluent areas have significantly higher access to moderate and vigorous intensity facilities by car than those living in more deprived areas. Conclusions The sociospatial distributions of access to facilities for both moderate intensity and vigorous intensity physical activity were similar. However, the results suggest that those living in the most affluent neighbourhoods have poorer access to facilities of either type that can be reached on foot

  15. Safety analysis report for the cold vacuum drying facility, phase 1, supporting civil/structural construction

    International Nuclear Information System (INIS)

    The Cold Vacuum Drying Facility is a subproject of the overall Spent Nuclear Fuel Project. This Phase 2 Safety Analysis Report incorporates the CVD systems design and will update the SAR per DOE Order 5480.23 for manual and other Hanford infrastructure changes

  16. Sampling and Analysis Instruction for Asbestos-Containing Materials from Surveillance Maintenance and Transition Facilities

    International Nuclear Information System (INIS)

    The purpose of this sampling and analysis instruction is to define the waste characterization requirements for disposition of asbestos-containing material in the form of thermal system insulation and transite cement asbestos board found in or near the Hanford Site facilities

  17. Evaluation of syngas production unit cost of bio-gasification facility using regression analysis techniques

    Energy Technology Data Exchange (ETDEWEB)

    Deng, Yangyang; Parajuli, Prem B.

    2011-08-10

    Evaluation of economic feasibility of a bio-gasification facility needs understanding of its unit cost under different production capacities. The objective of this study was to evaluate the unit cost of syngas production at capacities from 60 through 1800Nm 3/h using an economic model with three regression analysis techniques (simple regression, reciprocal regression, and log-log regression). The preliminary result of this study showed that reciprocal regression analysis technique had the best fit curve between per unit cost and production capacity, with sum of error squares (SES) lower than 0.001 and coefficient of determination of (R 2) 0.996. The regression analysis techniques determined the minimum unit cost of syngas production for micro-scale bio-gasification facilities of $0.052/Nm 3, under the capacity of 2,880 Nm 3/h. The results of this study suggest that to reduce cost, facilities should run at a high production capacity. In addition, the contribution of this technique could be the new categorical criterion to evaluate micro-scale bio-gasification facility from the perspective of economic analysis.

  18. Safety analysis of the Los Alamos critical experiments facility: burst operation of Skua

    International Nuclear Information System (INIS)

    A detailed consideration of the Skua burst assembly is presented, thereby supplementing the facility safety analysis report covering the operation of other critical assemblies at Los Alamos. As with these assemblies the small fission-product inventory, ambient pressure, and moderate temperatures in Skua are amenable to straightforward measures to ensure the protection of the public

  19. Safety analysis of the Los Alamos critical experiments facility: burst operation of Skua

    International Nuclear Information System (INIS)

    Detailed consideration of the Skua burst assembly is provided, thereby supplementing the facility Safety Analysis Report covering the operation of other critical assemblies at the Los Alamos Scientific Laboratory. As with these assemblies the small fission-product inventory, ambient pressure, and moderate temperatures in Skua are amenable to straightforward measures to ensure the protection of the public

  20. Determination of Importance Evaluation for Exploratory Studies Facility (ESF) Subsurface Testing Activities

    International Nuclear Information System (INIS)

    This Determination of Importance Evaluation (DIE) applies to the Subsurface Exploratory Studies Facility (ESF), encompassing the Topopah Spring (TS) Loop from Station 0+00 meters (m) at the North Portal to breakthrough at the South Portal (approximately 78+77 m), and ancillary test and operation support areas including the Enhanced Characterization of the Repository Block (ECRB) Cross Drift. This evaluation applies specifically to site characterization testing activities ongoing and planned in the Subsurface ESF. ESF site characterization activities are being performed to obtain the information necessary to determine whether the Yucca Mountain Site is suitable as a geologic repository for spent nuclear fuel and high-level radioactive waste. A more detailed description of these testing activities is provided in Section 6 of this DIE. Generally, the construction and operation of excavations associated with these testing activities are evaluated in the DIE for the Subsurface ESF (CRWMS M andO 1999a) and the DIE for the ESF ECRB Cross Drift (CRWMS M andO 2000a). The scope of this DIE also entails the proposed Unsaturated Zone (UZ) Transport Test at Busted Butte. Although, not a part of the TS Loop or ECRB Cross Drift, the associated testing activities are Subsurface testing activities. Busted Butte is located to the south south-east of the TS Loop and is outside the Conceptual Controlled Area Boundary (CCAB). These activities provide access to the Calico Hills (CH) geologic structure. In the case of Busted Butte, construction and operation of excavations are evaluated herein (since this activity was not previously evaluated in CRWMS M andO 1999a). The objectives of this DIE are to determine whether Subsurface ESF testing, and associated activities, could potentially impact site characterization testing and/or the waste isolation capabilities of the site. Controls needed to limit any potential impacts are identified in Section 13. The validity and veracity of the

  1. Determination of Importance Evaluation for Exploratory Studies Facility (ESF) Subsurface Testing Activities

    Energy Technology Data Exchange (ETDEWEB)

    S. Goodin

    2002-07-22

    This Determination of Importance Evaluation (DIE) applies to the Subsurface Exploratory Studies Facility (ESF), encompassing the Topopah Spring (TS) Loop from Station 0+00 meters (m) at the North Portal to breakthrough at the South Portal (approximately 78+77 m), and ancillary test and operation support areas including the Enhanced Characterization of the Repository Block (ECRB) Cross Drift. This evaluation applies specifically to site characterization testing activities ongoing and planned in the Subsurface ESF. ESF site characterization activities are being performed to obtain the information necessary to determine whether the Yucca Mountain Site is suitable as a geologic repository for spent nuclear fuel and high-level radioactive waste. A more detailed description of these testing activities is provided in Section 6 of this DIE. Generally, the construction and operation of excavations associated with these testing activities are evaluated in the DIE for the Subsurface ESF (CRWMS M&O 1999a) and the DIE for the ESF ECRB Cross Drift (CRWMS M&O 2000a). The scope of this DIE also entails the proposed Unsaturated Zone (UZ) Transport Test at Busted Butte. Although, not a part of the TS Loop or ECRB Cross Drift, the associated testing activities are Subsurface testing activities. Busted Butte is located to the south south-east of the TS Loop and is outside the Conceptual Controlled Area Boundary (CCAB). These activities provide access to the Calico Hills (CH) geologic structure. In the case of Busted Butte, construction and operation of excavations are evaluated herein (since this activity was not previously evaluated in CRWMS M&O 1999a). The objectives of this DIE are to determine whether Subsurface ESF testing, and associated activities, could potentially impact site characterization testing and/or the waste isolation capabilities of the site. Controls needed to limit any potential impacts are identified in Section 13. The validity and veracity of the individual

  2. Development of a systematic methodology to select hazard analysis techniques for nuclear facilities

    Energy Technology Data Exchange (ETDEWEB)

    Vasconcelos, Vanderley de; Reis, Sergio Carneiro dos; Costa, Antonio Carlos Lopes da [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil)]. E-mails: vasconv@cdtn.br; reissc@cdtn.br; aclc@cdtn.br; Jordao, Elizabete [Universidade Estadual de Campinas (UNICAMP), SP (Brazil). Faculdade de Engenharia Quimica]. E-mail: bete@feq.unicamp.br

    2008-07-01

    In order to comply with licensing requirements of regulatory bodies risk assessments of nuclear facilities should be carried out. In Brazil, such assessments are part of the Safety Analysis Reports, required by CNEN (Brazilian Nuclear Energy Commission), and of the Risk Analysis Studies, required by the competent environmental bodies. A risk assessment generally includes the identification of the hazards and accident sequences that can occur, as well as the estimation of the frequencies and effects of these unwanted events on the plant, people, and environment. The hazard identification and analysis are also particularly important when implementing an Integrated Safety, Health, and Environment Management System following ISO 14001, BS 8800 and OHSAS 18001 standards. Among the myriad of tools that help the process of hazard analysis can be highlighted: CCA (Cause- Consequence Analysis); CL (Checklist Analysis); ETA (Event Tree Analysis); FMEA (Failure Mode and Effects Analysis); FMECA (Failure Mode, Effects and Criticality Analysis); FTA (Fault Tree Analysis); HAZOP (Hazard and Operability Study); HRA (Human Reliability Analysis); Pareto Analysis; PHA (Preliminary Hazard Analysis); RR (Relative Ranking); SR (Safety Review); WI (What-If); and WI/CL (What-If/Checklist Analysis). The choice of a particular technique or a combination of techniques depends on many factors like motivation of the analysis, available data, complexity of the process being analyzed, expertise available on hazard analysis, and initial perception of the involved risks. This paper presents a systematic methodology to select the most suitable set of tools to conduct the hazard analysis, taking into account the mentioned involved factors. Considering that non-reactor nuclear facilities are, to a large extent, chemical processing plants, the developed approach can also be applied to analysis of chemical and petrochemical plants. The selected hazard analysis techniques can support cost

  3. The effect of health facility delivery on neonatal mortality: systematic review and meta-analysis

    Directory of Open Access Journals (Sweden)

    Tura Gurmesa

    2013-01-01

    Full Text Available Abstract Background Though promising progress has been made towards achieving the Millennium Development Goal four through substantial reduction in under-five mortality, the decline in neonatal mortality remains stagnant, mainly in the middle and low-income countries. As an option, health facility delivery is assumed to reduce this problem significantly. However, the existing evidences show contradicting conclusions about this fact, particularly in areas where enabling environments are constraint. Thus, this review was conducted with the aim of determining the pooled effect of health facility delivery on neonatal mortality. Methods The reviewed studies were accessed through electronic web-based search strategy from PUBMED, Cochrane Library and Advanced Google Scholar by using combination key terms. The analysis was done by using STATA-11. I2 test statistic was used to assess heterogeneity. Funnel plot, Begg’s test and Egger’s test were used to check for publication bias. Pooled effect size was determined in the form of relative risk in the random-effects model using DerSimonian and Laird's estimator. Results A total of 2,216 studies conducted on the review topic were identified. During screening, 37 studies found to be relevant for data abstraction. From these, only 19 studies fulfilled the preset criteria and included in the analysis. In 10 of the 19 studies included in the analysis, facility delivery had significant association with neonatal mortality; while in 9 studies the association was not significant. Based on the random effects model, the final pooled effect size in the form of relative risk was 0.71 (95% CI: 0.54, 0.87 for health facility delivery as compared to home delivery. Conclusion Health facility delivery is found to reduce the risk of neonatal mortality by 29% in low and middle income countries. Expansion of health facilities, fulfilling the enabling environments and promoting their utilization during childbirth are

  4. Preparation of Phased and Merged Safety Analysis Reports for New DOE Nuclear Facilities

    International Nuclear Information System (INIS)

    The Spent Nuclear Fuels Project (SNFP) is charged with moving to storage 2,100 metric tons of spent nuclear fuel elements left over from plutonium production at DOE'S Hanford site in Washington state. Two new facilities, the Cold Vacuum Drying Facility (CVDF) and the Canister Storage Building (CSB) are in final construction. In order to meet aggressive schedule commitments, the SNFP chose to prepare the safety analysis reports (SAR's) in phases that covered only specific portions of each facility's design as it was built. Each SAR also merged the preliminary and final safety analysis reports into a single SAR, thereby covering all aspects of design, construction, and operation for that portion (phase) of the facility. A policy of ''NRC equivalency'' was also implemented in parallel with this effort, with the goal of achieving a rigor of safety analysis equivalent to that of NRC-licensed fuel processing facilities. DOE Order 5480.23. ''Nuclear Safety Analysis Reports'' allows preparation of both a phased and a merged SAR to accelerate construction schedules. However, project managers must be aware that such acceleration is not guaranteed. Managers considering this approach for their project should be cognizant of numerous obstacles that will be encountered. Merging and phasing SAR's will create new, unique, and unanticipated difficulties which may actually slow construction unless expeditiously and correctly managed. Pitfalls to be avoided and good practices to be implemented in preparing phased and merged SAR's are presented. The value of applying NRC requirements to the DOE safety analysis process is also discussed. As of December, 1999, the SNFP has completed and approved a SAR for the CVDF. Approval of the SAR for the CSB is pending

  5. The European contribution to the development and validation activities for the design of IFMIF lithium facility

    Energy Technology Data Exchange (ETDEWEB)

    Miccichè, Gioacchino, E-mail: gioacchino.micciche@enea.it [EURATOM-ENEA, CR Brasimone I-40035 Camugnano, BO (Italy); Aiello, Antonio; Bernardi, Davide; Favuzza, Paolo; Agostini, Pietro [EURATOM-ENEA, CR Brasimone I-40035 Camugnano, BO (Italy); Frisoni, Manuela [EURATOM-ENEA, CR Bologna I-40129, BO Italy (Italy); Pinna, Tonio; Porfiri, MariaTeresa [EURATOM-ENEA, CR Frascati I-0044 Frascati, Roma (Italy); Tincani, Amelia [EURATOM-ENEA, CR Brasimone I-40035 Camugnano, BO (Italy); Di Maio, PieroAlessandro [University of Palermo, I-90128 Palermo (Italy); Knaepen, Bernard [Université libre de Bruxelles, I-1050 Bruxelles (Belgium)

    2013-10-15

    Highlights: • Engineering design of the target assembly. • Erosion, corrosion phenomena promoted by the lithium are studied. • Purification system implemented in the LiFus6 loop. • Study of the remote handling maintenance for the IFMIF TA. -- Abstract: The International Fusion Materials Irradiation Facility (IFMIF) is an accelerator-driven intense neutron source where candidate materials for fusion reactors will be tested and validated. The high energy neutron flux is produced by means of two deuteron beams (total current of 250 mA, energy of 40 MeV) that strikes a liquid lithium target circulating in a lithium loop of IFMIF plant. The European (EU) contribution to the development of the lithium facility comprises five procurement packages, as follow: (1) participation to the experimental activities of the EVEDA lithium test loop in Oarai (Japan); (2) study aimed at evaluating the corrosion and erosion phenomena, promoted by lithium, for structural fusion reference materials like AISI 316L and Eurofer; (3) design and validation of the lithium purification method with the aim to provide input data for the design of the purification system of IFIMF lithium loop; (4) design and validation of the remote handling (RH) procedures for the refurbishment/replacement of the EU concept of IFMIF target assembly including the design of the remote handling tools; (5) the engineering design of the European target assembly for IFMIF and the safety and RAMI analyses for the entire IFMIF lithium facility. The paper gives an overview of the status of the activities and of the main outcomes achieved so far.

  6. Guidance for preparation of safety analysis reports for nonreactor facilities and operations

    International Nuclear Information System (INIS)

    Department of Energy (DOE) Orders 5480.23, ''Nuclear Safety Analysis Reports,'' and 5481.1B, ''Safety Analysis and Review System'' require the preparation of appropriate safety analyses for each DOE operation and subsequent significant modifications including decommissioning, and independent review of each safety analysis. The purpose of this guide is to assist in the preparation and review of safety documentation for Oak Ridge Field Office (OR) nonreactor facilities and operation. Appendix A lists DOE Orders, NRC Regulatory Guides and other documents applicable to the preparation of safety analysis reports

  7. Modelling activities of experimental facilities related to advanced reactors. Considerations on 1D/3D issues

    International Nuclear Information System (INIS)

    The state of art of modelling activities related to integral experimental facilities of advanced passive reactors show to date important open items. The main advantage of using 1D plant codes is the capability of simulating the full interaction between components traditionally correctly modelled (condensers, heat exchangers, pipes and vessels) and other components for which codes are not 100% suitable (pools and containments). Polytechnical University of Catalonia (UPC) and Polytechnical University of Valencia (UPV) cooperated with other European research organizations in the 'Technology Enhancement for Passive Safety Systems' (TEPSS) project, within the European Fourth Framework Programme. It was a task of both Universities to supply analytical support of PANDA tests. The paper deals with the 1D/3D discussion in the framework of modelling activities related to integral passive facilities like PANDA. It starts choosing reference tests among those corresponding to our participation in TEPSS project. The discrepancies observed in a 1D simulation of the selected tests will be shown and analyzed. An evaluation of how the 3D version can lead to a better agreement with data will be included. Disadvantages of 3D codes will be shown too. Combining the use of different codes, and considering analyst criteria, will make possible to establish suitable recommendations from both engineering and scientific point of view. (author)

  8. DOE standard: Integration of environment, safety, and health into facility disposition activities. Volume 1: Technical standard

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-05-01

    This Department of Energy (DOE) technical standard (referred to as the Standard) provides guidance for integrating and enhancing worker, public, and environmental protection during facility disposition activities. It provides environment, safety, and health (ES and H) guidance to supplement the project management requirements and associated guidelines contained within DOE O 430.1A, Life-Cycle Asset Management (LCAM), and amplified within the corresponding implementation guides. In addition, the Standard is designed to support an Integrated Safety Management System (ISMS), consistent with the guiding principles and core functions contained in DOE P 450.4, Safety Management System Policy, and discussed in DOE G 450.4-1, Integrated Safety Management System Guide. The ISMS guiding principles represent the fundamental policies that guide the safe accomplishment of work and include: (1) line management responsibility for safety; (2) clear roles and responsibilities; (3) competence commensurate with responsibilities; (4) balanced priorities; (5) identification of safety standards and requirements; (6) hazard controls tailored to work being performed; and (7) operations authorization. This Standard specifically addresses the implementation of the above ISMS principles four through seven, as applied to facility disposition activities.

  9. Analysis of Debris Trajectories at the Scaled Wind Farm Technology (SWiFT) Facility

    Energy Technology Data Exchange (ETDEWEB)

    White, Jonathan R. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Burnett, Damon J. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2016-01-01

    Sandia National Laboratories operates the Scaled Wind Farm Technology Facility (SWiFT) on behalf of the Department of Energy Wind and Water Power Technologies Office. An analysis was performed to evaluate the hazards associated with debris thrown from one of SWiFT’s operating wind turbines, assuming a catastrophic failure. A Monte Carlo analysis was conducted to assess the complex variable space associated with debris throw hazards that included wind speed, wind direction, azimuth and pitch angles of the blade, and percentage of the blade that was separated. In addition, a set of high fidelity explicit dynamic finite element simulations were performed to determine the threshold impact energy envelope for the turbine control building located on-site. Assuming that all of the layered, independent, passive and active engineered safety systems and administrative procedures failed (a 100% failure rate of the safety systems), the likelihood of the control building being struck was calculated to be less than 5/10,000 and ballistic simulations showed that the control building would not provide passive protection for the majority of impact scenarios. Although options exist to improve the ballistic resistance of the control building, the recommendation is not to pursue them because there is a low probability of strike and there is an equal likelihood personnel could be located at similar distances in other areas of the SWiFT facility which are not passively protected, while the turbines are operating. A fenced exclusion area has been created around the turbines which restricts access to the boundary of the 1/100 strike probability. The overall recommendation is to neither relocate nor improve passive protection of the control building as the turbine safety systems have been improved to have no less than two independent, redundant, high quality engineered safety systems. Considering this, in combination with a control building strike probability of less than 5/10,000, the

  10. Preliminary Hazard Analysis for the Remote-Handled Low-Level Waste Disposal Facility

    Energy Technology Data Exchange (ETDEWEB)

    Lisa Harvego; Mike Lehto

    2010-05-01

    The need for remote handled low level waste (LLW) disposal capability has been identified. A new onsite, remote-handled LLW disposal facility has been identified as the highest ranked alternative for providing continued, uninterrupted remote-handled LLW disposal capability for remote-handled LLW that is generated as part of the nuclear mission of the Idaho National Laboratory and from spent nuclear fuel processing activities at the Naval Reactors Facility. Historically, this type of waste has been disposed of at the Radioactive Waste Management Complex. Disposal of remote-handled LLW in concrete disposal vaults at the Radioactive Waste Management Complex will continue until the facility is full or until it must be closed in preparation for final remediation of the Subsurface Disposal Area (approximately at the end of Fiscal Year 2017). This document supports the conceptual design for the proposed remote-handled LLW disposal facility by providing an initial nuclear facility hazard categorization and by identifying potential hazards for processes associated with onsite handling and disposal of remote-handled LLW.

  11. Preliminary Hazard Analysis for the Remote-Handled Low-Level Waste Disposal Facility

    Energy Technology Data Exchange (ETDEWEB)

    Lisa Harvego; Mike Lehto

    2010-02-01

    The need for remote handled low level waste (LLW) disposal capability has been identified. A new onsite, remote-handled LLW disposal facility has been identified as the highest ranked alternative for providing continued, uninterrupted remote-handled LLW disposal capability for remote-handled LLW that is generated as part of the nuclear mission of the Idaho National Laboratory and from spent nuclear fuel processing activities at the Naval Reactors Facility. Historically, this type of waste has been disposed of at the Radioactive Waste Management Complex. Disposal of remote-handled LLW in concrete disposal vaults at the Radioactive Waste Management Complex will continue until the facility is full or until it must be closed in preparation for final remediation of the Subsurface Disposal Area (approximately at the end of Fiscal Year 2017). This document supports the conceptual design for the proposed remote-handled LLW disposal facility by providing an initial nuclear facility hazard categorization and by identifying potential hazards for processes associated with onsite handling and disposal of remote-handled LLW.

  12. Analysis Methods for Extracting Knowledge from Large-Scale WiFi Monitoring to Inform Building Facility Planning

    DEFF Research Database (Denmark)

    Ruiz-Ruiz, Antonio; Blunck, Henrik; Prentow, Thor Siiger;

    2014-01-01

    realistic data to inform facility planning. In this paper, we propose analysis methods to extract knowledge from large sets of network collected WiFi traces to better inform facility management and planning in large building complexes. The analysis methods, which build on a rich set of temporal and spatial...

  13. Radiohygienic aspects of the safety analysis of the Puespoekszilagy radioactive waste disposal and treatment facility, Hungary

    International Nuclear Information System (INIS)

    A temporary disposal was established for low level radioactive waste (LLW) at Solymar close to Budapest in 1960. Approx. 900 m3 LLW was disposed in concrete ring bells on the site until 1975. A new disposal (Radwaste Treatment and Disposal Facility, RWTDF) for low and intermediate radioactive waste (L/ILW) was put into operation at Puespoekszilagy, about 40 km to Budapest in 1976. The site was operated by the Metropolitan Institute of National Public Health and Medical Officer Service until 1997, when according to the new Hungarian Act on Atomic Energy the Public Agency for Radioactive Waste Management was established to perform the tasks connected to radwaste management and decommissioning of nuclear installations. The Solymar facility was dismantled and the radioactive waste transported to Puespoekszilagy. The RWTDF is situated on the ridge of a hill in a clay formation with conductivity from 10-8 to 10-6 cm.s-1; the groundwater depth is 17-20 m from the bottom of the disposal units. The waste is deposited in near surface disposal units (trenches, cells, and wells) with engineered barriers. Up to now about 4900 m3 of solid and solidified waste has been emplaced and 2 trenches of about 3000 m3 has been temporary sealed. More than 80% of the disposed waste is of low level. Approx. 700 TBq is the total activity of the radwaste including long-lived and alpha emitting radionuclides with the activity of the order of magnitude of 10 TBq. As the safety analysis was performed in a simple way in 1970's during the commissioning of the facility a comprehensive safety analysis was prescribed to get the license for the operation of the storage units extended at the end of 1980's. ETV-EROETERV Ltd. has won the tender for the safety analysis and the NRIRR was involved in the biosphere characterisation of the region and in the dose estimations for different accidental scenarios as well. The biosphere characterisation included the following categories: meteorology, geography, land

  14. Conference on instrumental activation analysis IAA 92

    International Nuclear Information System (INIS)

    The publication contains 26 abstracts primarily concerned with neutron activation analysis, although other analytical techniques based on X-ray fluorescence analysis, PIXE, PIGE, RBS are also included. Some contributions deal with aspects of quality practice and assurance in radioanalytical laboratories, with marketing of instrumental neutron activation analysis services, with hard- and software aspects of radiation detection, etc. (Z.S.)

  15. The INFN-CNAF Tier-1 GEMSS Mass Storage System and database facility activity

    Science.gov (United States)

    Ricci, Pier Paolo; Cavalli, Alessandro; Dell'Agnello, Luca; Favaro, Matteo; Gregori, Daniele; Prosperini, Andrea; Pezzi, Michele; Sapunenko, Vladimir; Zizzi, Giovanni; Vagnoni, Vincenzo

    2015-05-01

    The consolidation of Mass Storage services at the INFN-CNAF Tier1 Storage department that has occurred during the last 5 years, resulted in a reliable, high performance and moderately easy-to-manage facility that provides data access, archive, backup and database services to several different use cases. At present, the GEMSS Mass Storage System, developed and installed at CNAF and based upon an integration between the IBM GPFS parallel filesystem and the Tivoli Storage Manager (TSM) tape management software, is one of the largest hierarchical storage sites in Europe. It provides storage resources for about 12% of LHC data, as well as for data of other non-LHC experiments. Files are accessed using standard SRM Grid services provided by the Storage Resource Manager (StoRM), also developed at CNAF. Data access is also provided by XRootD and HTTP/WebDaV endpoints. Besides these services, an Oracle database facility is in production characterized by an effective level of parallelism, redundancy and availability. This facility is running databases for storing and accessing relational data objects and for providing database services to the currently active use cases. It takes advantage of several Oracle technologies, like Real Application Cluster (RAC), Automatic Storage Manager (ASM) and Enterprise Manager centralized management tools, together with other technologies for performance optimization, ease of management and downtime reduction. The aim of the present paper is to illustrate the state-of-the-art of the INFN-CNAF Tier1 Storage department infrastructures and software services, and to give a brief outlook to forthcoming projects. A description of the administrative, monitoring and problem-tracking tools that play a primary role in managing the whole storage framework is also given.

  16. Development of HANARO Activation Analysis System and Utilization Technology

    Energy Technology Data Exchange (ETDEWEB)

    Chung, Y. S.; Moon, J. H.; Cho, H. J. (and others)

    2007-06-15

    1. Establishment of evaluation system using a data for a neutron activation analysis : Improvement of NAA measurement system and its identification, Development of combined data evaluation code of NAA/PGAA, International technical cooperation project 2. Development of technique for a industrial application of high precision gamma nuclide spectroscopic analysis : Analytical quality control, Development of industrial application techniques and its identification 3. Industrial application research for a prompt gamma-ray activation analysis : Improvement of Compton suppression counting system (PGAA), Development of applied technology using a PGAA system 4. Establishment of NAA user supporting system and KOLAS management : Development and validation of KOLAS/ISO accreditation testing and identification method, Cooperation researches for a industrial application, Establishment of integrated user analytical supporting system, Accomplishment of sample irradiation facility.

  17. Development of HANARO Activation Analysis System and Utilization Technology

    International Nuclear Information System (INIS)

    1. Establishment of evaluation system using a data for a neutron activation analysis : Improvement of NAA measurement system and its identification, Development of combined data evaluation code of NAA/PGAA, International technical cooperation project 2. Development of technique for a industrial application of high precision gamma nuclide spectroscopic analysis : Analytical quality control, Development of industrial application techniques and its identification 3. Industrial application research for a prompt gamma-ray activation analysis : Improvement of Compton suppression counting system (PGAA), Development of applied technology using a PGAA system 4. Establishment of NAA user supporting system and KOLAS management : Development and validation of KOLAS/ISO accreditation testing and identification method, Cooperation researches for a industrial application, Establishment of integrated user analytical supporting system, Accomplishment of sample irradiation facility

  18. Current status of neutron activation analysis in HANARO Research Reactor

    International Nuclear Information System (INIS)

    The facilities for neutron activation analysis in the HANARO (Hi-flux Advanced Neutron Application Research Reactor) are described and the main applications of NAA (Neutron Activation Analysis) are reviewed. The sample irradiation tube, automatic and manual pneumatic transfer system were installed at three irradiation holes of HANARO at the end of 1995. The performance of the NAA facility was examined to identify the characteristics of the tube transfer system, irradiation sites and custom-made polyethylene irradiation capsule. The available thermal neutron fluxes at irradiation sites are in the range of 3 x 1013 - 1 x 1014 n/cm2·s and cadmium ratios are in 15 - 250. For an automatic sample changer for gamma-ray counting, a domestic product was designed and manufactured. An integrated computer program (Labview) to analyse the content was developed. In 2001, PGNAA (Prompt Gamma Neutron Activation Analysis) facility has been installed using a diffracted neutron beam of ST1. NAA has been applied in the trace component analysis of nuclear, geological, biological, environmental and high purity materials, and various polymers for research and development. The improvement of analytical procedures and establishment of an analytical quality control and assurance system were studied. Applied research and development for the environment, industry and human health by NAA and its standardization were carried out. For the application of the KOLAS (Korea Laboratory Accreditation Scheme), evaluation of measurement uncertainty and proficiency testing of reference materials were performed. Also to verify the reliability and to validate analytical results, intercomparison studies between laboratories were carried out. (author)

  19. Current status of neutron activation analysis in HANARO Research Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Chung, Yong Sam; Moon, Jong Hwa; Sohn, Jae Min [Korea Atomic Energy Research Institute, Daejeon (Korea)

    2003-03-01

    The facilities for neutron activation analysis in the HANARO (Hi-flux Advanced Neutron Application Research Reactor) are described and the main applications of NAA (Neutron Activation Analysis) are reviewed. The sample irradiation tube, automatic and manual pneumatic transfer system were installed at three irradiation holes of HANARO at the end of 1995. The performance of the NAA facility was examined to identify the characteristics of the tube transfer system, irradiation sites and custom-made polyethylene irradiation capsule. The available thermal neutron fluxes at irradiation sites are in the range of 3 x 10{sup 13} - 1 x 10{sup 14} n/cm{sup 2}{center_dot}s and cadmium ratios are in 15 - 250. For an automatic sample changer for gamma-ray counting, a domestic product was designed and manufactured. An integrated computer program (Labview) to analyse the content was developed. In 2001, PGNAA (Prompt Gamma Neutron Activation Analysis) facility has been installed using a diffracted neutron beam of ST1. NAA has been applied in the trace component analysis of nuclear, geological, biological, environmental and high purity materials, and various polymers for research and development. The improvement of analytical procedures and establishment of an analytical quality control and assurance system were studied. Applied research and development for the environment, industry and human health by NAA and its standardization were carried out. For the application of the KOLAS (Korea Laboratory Accreditation Scheme), evaluation of measurement uncertainty and proficiency testing of reference materials were performed. Also to verify the reliability and to validate analytical results, intercomparison studies between laboratories were carried out. (author)

  20. IFMIF, International Fusion Materials Irradiation Facility conceptual design activity cost report

    International Nuclear Information System (INIS)

    This report documents the cost estimate for the International Fusion Materials Irradiation Facility (IFMIF) at the completion of the Conceptual Design Activity (CDA). The estimate corresponds to the design documented in the Final IFMIF CDA Report. In order to effectively involve all the collaborating parties in the development of the estimate, a preparatory meeting was held at Oak Ridge National Laboratory in March 1996 to jointly establish guidelines to insure that the estimate was uniformly prepared while still permitting each country to use customary costing techniques. These guidelines are described in Section 4. A preliminary cost estimate was issued in July 1996 based on the results of the Second Design Integration Meeting, May 20--27, 1996 at JAERI, Tokai, Japan. This document served as the basis for the final costing and review efforts culminating in a final review during the Third IFMIF Design Integration Meeting, October 14--25, 1996, ENEA, Frascati, Italy. The present estimate is a baseline cost estimate which does not apply to a specific site. A revised cost estimate will be prepared following the assignment of both the site and all the facility responsibilities

  1. IFMIF, International Fusion Materials Irradiation Facility conceptual design activity cost report

    Energy Technology Data Exchange (ETDEWEB)

    Rennich, M.J. [comp.

    1996-12-01

    This report documents the cost estimate for the International Fusion Materials Irradiation Facility (IFMIF) at the completion of the Conceptual Design Activity (CDA). The estimate corresponds to the design documented in the Final IFMIF CDA Report. In order to effectively involve all the collaborating parties in the development of the estimate, a preparatory meeting was held at Oak Ridge National Laboratory in March 1996 to jointly establish guidelines to insure that the estimate was uniformly prepared while still permitting each country to use customary costing techniques. These guidelines are described in Section 4. A preliminary cost estimate was issued in July 1996 based on the results of the Second Design Integration Meeting, May 20--27, 1996 at JAERI, Tokai, Japan. This document served as the basis for the final costing and review efforts culminating in a final review during the Third IFMIF Design Integration Meeting, October 14--25, 1996, ENEA, Frascati, Italy. The present estimate is a baseline cost estimate which does not apply to a specific site. A revised cost estimate will be prepared following the assignment of both the site and all the facility responsibilities.

  2. Auditable Safety Analysis and Final Hazard Classification for the 105-N Reactor Zone and 109-N Steam Generator Zone Facility

    International Nuclear Information System (INIS)

    This document is a graded auditable safety analysis (ASA) and final hazard classification (FHC) for the Reactor/Steam Generator Zone Segment. The Reactor/Steam Generator Zone Segment, part of the N Reactor Complex, that is also known as the Reactor Building and Steam Generator Cells. The installation of the modifications described within to support surveillance and maintenance activities are to be completed by July 1, 1999. The surveillance and maintenance activities addressed within are assumed to continue for the next 15- 20 years, until the initiation of facility D ampersand D (i.e., Interim Safe Storage). The graded ASA in this document is in accordance with EDPI-4.30-01, Rev. 1, Safety Analysis Documentation, (BHI-DE-1) and is consistent with guidance provided by the U.S. Department of Energy. This ASA describes the hazards within the facility and evaluates the adequacy of the measures taken to reduce, control, or mitigate the identified hazards. This document also serves as the FHC for the Reactor/Steam Generator Zone Segment. This FHC is developed through the use of bounding accident analyses that envelope the potential exposures to personnel

  3. The association between high recreational physical activity and physical activity as a part of daily living in adolescents and availability of local indoor sports facilities and sports clubs

    DEFF Research Database (Denmark)

    Niclasen, B.; Petzold, M.; Schnohr, Christina Warrer

    2012-01-01

    Aim: The aim of this study was to examine how vigorous physical activity (recreational physical activity) (VPA) and moderate to vigorous physical activity as a part of daily life (MVPA) is associated with structural characteristics (availability of sports facilities and sports clubs with child me...

  4. Synthesis of sulfonated porous carbon nanospheres solid acid by a facile chemical activation route

    Science.gov (United States)

    Chang, Binbin; Guo, Yanzhen; Yin, Hang; Zhang, Shouren; Yang, Baocheng

    2015-01-01

    Generally, porous carbon nanospheres materials are usually prepared via a template method, which is a multi-steps and high-cost strategy. Here, we reported a porous carbon nanosphere solid acid with high surface area and superior porosity, as well as uniform nanospheical morphology, which prepared by a facile chemical activation with ZnCl2 using resorcinol-formaldehyde (RF) resins spheres as precursor. The activation of RF resins spheres by ZnCl2 at 400 °C brought high surface area and large volume, and simultaneously retained numerous oxygen-containing and hydrogen-containing groups due to the relatively low processing temperature. The presence of these functional groups is favorable for the modification of -SO3H groups by a followed sulfonation treating with sulphuric acid and organic sulfonic acid. The results of N2 adsorption-desorption and electron microscopy clearly showed the preservation of porous structure and nanospherical morphology. Infrared spectra certified the variation of surface functional groups after activation and the successful modification of -SO3H groups after sulfonation. The acidities of catalysts were estimated by an indirect titration method and the modified amount of -SO3H groups were examined by energy dispersive spectra. The results suggested sulfonated porous carbon nanospheres catalysts possessed high acidities and -SO3H densities, which endowed their significantly catalytic activities for biodiesel production. Furthermore, their excellent stability and recycling property were also demonstrated by five consecutive cycles.

  5. Instrumental neutron activation analysis - a routine method

    International Nuclear Information System (INIS)

    This thesis describes the way in which at IRI instrumental neutron activation analysis (INAA) has been developed into an automated system for routine analysis. The basis of this work are 20 publications describing the development of INAA since 1968. (Auth.)

  6. Analysis Facility infrastructure (TIER3) for ATLAS High Energy physics experiment

    Energy Technology Data Exchange (ETDEWEB)

    Gonzalez de la Hoz, S.; March, L.; Ros, E.; Sanchez, J.; Amoros, G.; Fassi, F.; Fernandez, A.; Kaci, M.; Lamas, A.; Salt, J.

    2007-07-01

    ATLAS project has been asked to define the scope and role of Tier-3 resources (facilities or centres) within the existing ATLAS computing model, activities and facilities. This document attempts to address these questions by describing Tier-3 resources generally, and their relationship to the ATLAS Software and Computing Project. Originally the tiered computing model came out of MONARC (see http://monarc.web.cern.ch/MONARC/) work and was predicated upon the network being a scarce resource. In this model the tiered hierarchy ranged from the Tier-0 (CERN) down to the desktop or workstation (Tier 3). The focus on defining the roles of each tiered component has evolved with the initial emphasis on the Tier-0 (CERN) and Tier-1 (National centres) definition and roles. The various LHC projects, including ATLAS, then evolved the tiered hierarchy to include Tier-2s (Regional centers) as part of their projects. Tier-3s, on the other hand, have (implicitly and sometime explicitly) been defined as whatever an institution could construct to support their Physics goals using institutional and otherwise leveraged resources and therefore have not been considered to be part of the official ATLAS Research Program computing resources nor under their control, meaning there is no formal MOU process to designate sites as Tier-3s and no formal control of the program over the Tier-3 resources. Tier-3s are the responsibility of individual institutions to define, fund, deploy and support. However, having noted this, we must also recognize that Tier-3s must exist and will have implications for how our computing model should support ATLAS physicists. Tier-3 users will want to access data and simulations and will want to enable their Tier-3 resources to support their analysis and simulation work. Tiers 3s are an important resource for physicists to analyze LHC (Large Hadron Collider) data. This document will define how Tier-3s should best interact with the ATLAS computing model, detail the

  7. 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

  8. Safety analysis report for the Heavy-Element Facility (Building 251), Lawrence Livermore National Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    Kvam, D.J.

    1982-10-11

    A comprehensive safety analysis was performed on the Lawrence Livermore National Laboratory's Heavy Element Facility, Building 251. The purpose of the analysis was to evaluate the building and its operations in order to inform LLNL and the Department of Energy of the risks they assume at Building 251. This was done by examining all of the energy sources and matching them with the physical and administrative barriers that control, prevent, or mitigate their hazards. Risk was evaluated for each source under both normal and catastrophic circumstances such as fire, flood, high wind, lighting, earthquake, and criticality. No significant safety deficiencies were found; it is concluded that the operation of the facility presents no unacceptable risk.

  9. Search for reaction-in-flight neutrons using thulium activation at the National Ignition Facility

    Science.gov (United States)

    Grim, Gary; Rundberg, Robert; Tonchev, Anton; Fowler, Malcolm; Wilhelmy, Jerry; Archuleta, Tom; Bionta, Richard; Boswell, Mitzi; Gostic, Julie; Griego, Jeff; Knittel, Kenn; Klein, Andi; Moody, Ken; Shaughnessy, Dawn; Wilde, Carl; Yeamans, Charles

    2013-10-01

    We report on measurements of reaction-in-flight (RIF) neutrons at the National Ignition Facility. RIF neutrons are produced in cryogenically layered implision by up-scattered deuterium, or tritium ions that undergo subsequent fusion reactions. The rate of RIF neutron production is proportional to the fuel areal density (| | R) and ion-stopping length in the dense fuel assembly. Thus, RIF neutrons provide information on charge particle stopping in a strongly coupled plasma, where perturbative modeling breaks down. To measure RIF neutrons, a set of thulium activation foils was placed 50 cm from layered cryogenic implosions at the NIF. The reaction 169Tm(n,3n)167Tm has a neutron kinetic energy threshold of 14.96 MeV. We will present results from initial experiments performed during the spring of 2013. Prepared by LANL under Contract DE-AC-52-06-NA25396, TSPA, LA-UR-13-22085.

  10. The dry storage cask in interim storage facility and safeguards activity

    International Nuclear Information System (INIS)

    The Japan Atomic Power Company (JAPC) is preparing for interim storage of spent fuel at Recyclable-Fuel Storage Center (RFSC) in Aomori Prefecture. Metallic dry casks are employed to contain the spent fuel and to serve for about 50 years in RFSC. Metallic dry casks have already been used for spent fuel dry storage at Tokai No.2 power station. But, RFSC is not exactly the same as the dry storage facility in Tokai No.2 power station, for example, casks are transported out side of the reactor site and RFSC has no fuel handling system. Therefore, additional implementation of safeguards is necessary. This report introduces the design and handling of metallic dry casks for RFSC and the currently developing status of the safeguards activity such as containment and surveillance for the fuel loading at the power station, the cask receipt and storage at RFSC, etc. (author)

  11. Facile synthesis of PtCu nanowires with enhanced electrocatalytic activity

    Institute of Scientific and Technical Information of China (English)

    Wei Hong[1,2; Jin Wang[1,3; Erkang Wang[1,2

    2015-01-01

    Using Te nanowires as a sacrificial template, We developed a facile wet-chemical method for the synthesis of bimetallic PtCu nanowires. The as-prepared PtCu nanowires possess a porous structure and high aspect ratio. Transmission electron microscopy, X-ray diffraction, energy dispersive spectroscopy, energy dispersive X-ray spectrum elemental mapping, inductively coupled plasma- mass spectroscopy, and X-ray photoelectron spectroscopy (XPS) measurement techniques are used to analyze the structure and composition of the as-prepared nanowires. The XPS results verify that the incorporation of Cu led to the modified electronic state of Pt. Electrocatalytic results prove that the as-prepared nanowires present superior activity for methanol and ethanol electrooxidation in an alkaline solution.

  12. Chemical Hygiene Plan for Onsite Measurement and Sample Shipping Facility Activities

    International Nuclear Information System (INIS)

    This chemical hygiene plan presents the requirements established to ensure the protection of employee health while performing work in mobile laboratories, the sample shipping facility, and at the onsite radiological counting facility. This document presents the measures to be taken to promote safe work practices and to minimize worker exposure to hazardous chemicals. Specific hazardous chemicals present in the mobile laboratories, the sample shipping facility, and in the radiological counting facility are presented in Appendices A through G

  13. Proposed outline of safety analysis report for facilities for geologic isolation of radioactive wastes

    International Nuclear Information System (INIS)

    This report is concerned with formulating the appropriate and necessary contents for a Safety Analysis Report (SAR) for safe, long-term radioactive waste isolation in federal repositories. The material is presented as a guide rather than as an outline of a SAR. Site characteristics, design criteria, facility design, operational systems and components, radiation protection and operational safety, long-term waste isolation, conduct of operations, technical specifications, and quality assurance are covered. Recommendations are given for further research studies

  14. 200 Area Treated Effluent Disposal Facility (TEDF) Effluent Sampling and Analysis Plan

    Energy Technology Data Exchange (ETDEWEB)

    BROWN, M.J.

    2000-05-18

    This Sampling and Analysis Plan (SAP) has been developed to comply with effluent monitoring requirements at the 200 Area Treated Effluent Disposal Facility (TEDF), as stated in Washington State Waste Discharge Permit No. ST 4502 (Ecology 2000). This permit, issued by the Washington State Department of Ecology (Ecology) under the authority of Chapter 90.48 Revised Code of Washington (RCW) and Washington Administrative Code (WAC) Chapter 173-216, is an April 2000 renewal of the original permit issued on April 1995.

  15. Fracture mechanics analysis of a high-pressure hydrogen facility compressor

    Science.gov (United States)

    Vroman, G. A.

    1974-01-01

    The investigation and analysis of a high-pressure hydrogen facility compressor is chronicled, and a life prediction based on fracture mechanics is presented. Crack growth rates in SA 105 Gr II steel are developed for the condition of sustained loading, using a hypothesis of hydrogen embrittlement associated with plastic zone reverse yielding. The resultant formula is compared with test data obtained from laboratory specimens.

  16. Facile synthesis of phosphorus doped graphitic carbon nitride polymers with enhanced visible-light photocatalytic activity

    Energy Technology Data Exchange (ETDEWEB)

    Zhang, Ligang [Key Laboratory of Biobased Materials, Qingdao Institute of Bioenergy and Bioprocess Technology, Chinese Academy of Sciences, Qingdao 266101 (China); University of Chinese Academy of Sciences, Beijing 100049 (China); Chen, Xiufang; Guan, Jing; Jiang, Yijun; Hou, Tonggang [Key Laboratory of Biobased Materials, Qingdao Institute of Bioenergy and Bioprocess Technology, Chinese Academy of Sciences, Qingdao 266101 (China); Mu, Xindong, E-mail: muxd@qibebt.ac.cn [Key Laboratory of Biobased Materials, Qingdao Institute of Bioenergy and Bioprocess Technology, Chinese Academy of Sciences, Qingdao 266101 (China)

    2013-09-01

    Graphical abstract: - Highlights: • P-doped g-C{sub 3}N{sub 4} has been prepared by a one-pot green synthetic approach. • The incorporation of P resulted in favorable textural and electronic properties. • Doping with P enhanced the visible-light photocatalytic activity of g-C{sub 3}N{sub 4}. • A postannealing treatment further enhanced the activity of P-doped g-C{sub 3}N{sub 4}. • Photogenerated holes were the main species responsible for the activity. - Abstract: Phosphorus-doped carbon nitride materials were prepared by a one-pot green synthetic approach using dicyandiamide monomer and a phosphorus containing ionic liquid as precursors. The as-prepared materials were subjected to several characterizations and investigated as metal-free photocatalysts for the degradation of organic pollutants (dyes like Rhodamine B, Methyl orange) in aqueous solution under visible light. Results revealed that phosphorus-doped carbon nitride have a higher photocatalytic activity for decomposing Rhodamine B and Methyl orange in aqueous solution than undoped g-C{sub 3}N{sub 4}, which was attributed to the favorable textural, optical and electronic properties caused by doping with phosphorus heteroatoms into carbon nitride host. A facile postannealing treatment further improved the activity of the photocatalytic system, due to the higher surface area and smaller structural size in the postcalcined catalysts. The phosphorus-doped carbon nitride showed high visible-light photocatalytic activity, making them promising materials for a wide range of potential applications in photochemistry.

  17. The Influence of Urban Land-Use and Public Transport Facilities on Active Commuting in Wellington, New Zealand: Active Transport Forecasting Using the WILUTE Model

    OpenAIRE

    Joreintje Dingena Mackenbach; Edward Randal; Pengjun Zhao; Philippa Howden-Chapman

    2016-01-01

    Physical activity has numerous physical and mental health benefits, and active commuting (walking or cycling to work) can help meet physical activity recommendations. This study investigated socioeconomic differences in active commuting, and assessed the impact of urban land-use and public transport policies on active commuting in the Wellington region in New Zealand. We combined data from the New Zealand Household Travel Survey and GIS data on land-use and public transport facilities with th...

  18. A neutron activation spectrometer and neutronic experimental platform for the National Ignition Facility (invited)

    Science.gov (United States)

    Yeamans, C. B.; Gharibyan, N.

    2016-11-01

    At the National Ignition Facility, the diagnostic instrument manipulator-based neutron activation spectrometer is used as a diagnostic of implosion performance for inertial confinement fusion experiments. Additionally, it serves as a platform for independent neutronic experiments and may be connected to fast recording systems for neutron effect tests on active electronics. As an implosion diagnostic, the neutron activation spectrometers are used to quantify fluence of primary DT neutrons, downscattered neutrons, and neutrons above the primary DT neutron energy created by reactions of upscattered D and T in flight. At a primary neutron yield of 1015 and a downscattered fraction of neutrons in the 10-12 MeV energy range of 0.04, the downscattered neutron fraction can be measured to a relative uncertainty of 8%. Significant asymmetries in downscattered neutrons have been observed. Spectrometers have been designed and fielded to measure the tritium-tritium and deuterium-tritium neutron outputs simultaneously in experiments using DT/TT fusion ratio as a direct measure of mix of ablator into the gas.

  19. Control of pneumatic transfer system for neutron activation analysis

    International Nuclear Information System (INIS)

    Pneumatic transfer system(PTS) is one of the facilities to be used in irradiation of target materials for neutron activation analysis(NAA) in the research reactor. There are two systems the manual and the automatic system in PTS of HANARO research reactor. The pneumatic transfer system consists of many devices, sends and loads the capsules from NAA laboratory into three holes in the reflector tank of reactor and retrieves irradiated capsules after irradiation. This report describes the part's design, control system and the operation procedures. All the algorithm described in the text will be used for maintenance and upgrading

  20. Control of pneumatic transfer system for neutron activation analysis

    Energy Technology Data Exchange (ETDEWEB)

    Jung, H. S.; Chung, Y. S.; Wu, J. S.; Kim, H. K.; Choi, Y. S.; Kim, S. H.; Moon, J. H.; Baek, S. Y

    2000-06-01

    Pneumatic transfer system(PTS) is one of the facilities to be used in irradiation of target materials for neutron activation analysis(NAA) in the research reactor. There are two systems the manual and the automatic system in PTS of HANARO research reactor. The pneumatic transfer system consists of many devices, sends and loads the capsules from NAA laboratory into three holes in the reflector tank of reactor and retrieves irradiated capsules after irradiation. This report describes the part's design, control system and the operation procedures. All the algorithm described in the text will be used for maintenance and upgrading.

  1. Overview of NORM and activities by a NORM licensed permanent decontamination and waste processing facility

    Energy Technology Data Exchange (ETDEWEB)

    Mirro, G.A. [Growth Resources, Inc., Lafayette, LA (United States)

    1997-02-01

    This paper presents an overview of issues related to handling NORM materials, and provides a description of a facility designed for the processing of NORM contaminated equipment. With regard to handling NORM materials the author discusses sources of NORM, problems, regulations and disposal options, potential hazards, safety equipment, and issues related to personnel protection. For the facility, the author discusses: description of the permanent facility; the operations of the facility; the license it has for handling specific radioactive material; operating and safety procedures; decontamination facilities on site; NORM waste processing capabilities; and offsite NORM services which are available.

  2. Xenon diffusion studies with prompt gamma activation analysis

    International Nuclear Information System (INIS)

    Developing a better understanding of xenon transport through porous systems is critical to predicting how this gas will enter the atmosphere after a below ground nuclear weapons test. Radioxenon monitoring is a vital part of the Comprehensive Nuclear-Test-Ban Treaty (CTBT) International Monitoring System. This work details the development of prompt gamma activation analysis for measuring the diffusion rates of xenon and argon gases through a porous medium. The University of Texas at Austin maintains a prompt gamma activation analysis facility with a peak neutron flux of ∼ 1.5 x 107 cm-2 s-1 and a beam diameter of 1 cm. Due to the relatively large prompt gamma cross sections of many stable xenon isotopes at thermal and sub-thermal neutron energies, prompt gamma activation analysis is a suitable technique for in situ non-destructive analysis of natural xenon. A test chamber has been designed and constructed to utilize prompt gamma activation analysis to measure xenon and argon diffusion through geological materials (e.g., sand, soil, etc.). Initial experiments have been conducted to determine the detection limits for stable gas measurements. The results from these experiments will be utilized to benchmark parts of a xenon transport model that is being used to determine diffusion coefficients for xenon and argon. (author)

  3. Velo and REXAN - Integrated Data Management and High Speed Analysis for Experimental Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Kleese van Dam, Kerstin; Carson, James P.; Corrigan, Abigail L.; Einstein, Daniel R.; Guillen, Zoe C.; Heath, Brandi S.; Kuprat, Andrew P.; Lanekoff, Ingela T.; Lansing, Carina S.; Laskin, Julia; Li, Dongsheng; Liu, Yan; Marshall, Matthew J.; Miller, Erin A.; Orr, Galya; Pinheiro da Silva, Paulo; Ryu, Seun; Szymanski, Craig J.; Thomas, Mathew

    2013-01-10

    The Chemical Imaging Initiative at the Pacific Northwest National Laboratory (PNNL) is creating a ‘Rapid Experimental Analysis’ (REXAN) Framework, based on the concept of reusable component libraries. REXAN allows developers to quickly compose and customize high throughput analysis pipelines for a range of experiments, as well as supporting the creation of multi-modal analysis pipelines. In addition, PNNL has coupled REXAN with its collaborative data management and analysis environment Velo to create an easy to use data management and analysis environments for experimental facilities. This paper will discuss the benefits of Velo and REXAN in the context of three examples: PNNL High Resolution Mass Spectrometry - reducing analysis times from hours to seconds, and enabling the analysis of much larger data samples (100KB to 40GB) at the same time · ALS X-Ray tomography - reducing analysis times of combined STXM and EM data collected at the ALS from weeks to minutes, decreasing manual work and increasing data volumes that can be analysed in a single step ·Multi-modal nano-scale analysis of STXM and TEM data - providing a semi automated process for particle detection The creation of REXAN has significantly shortened the development time for these analysis pipelines. The integration of Velo and REXAN has significantly increased the scientific productivity of the instruments and their users by creating easy to use data management and analysis environments with greatly reduced analysis times and improved analysis capabilities.

  4. Lightweight scheduling of elastic analysis containers in a competitive cloud environment: a Docked Analysis Facility for ALICE

    Science.gov (United States)

    Berzano, D.; Blomer, J.; Buncic, P.; Charalampidis, I.; Ganis, G.; Meusel, R.

    2015-12-01

    During the last years, several Grid computing centres chose virtualization as a better way to manage diverse use cases with self-consistent environments on the same bare infrastructure. The maturity of control interfaces (such as OpenNebula and OpenStack) opened the possibility to easily change the amount of resources assigned to each use case by simply turning on and off virtual machines. Some of those private clouds use, in production, copies of the Virtual Analysis Facility, a fully virtualized and self-contained batch analysis cluster capable of expanding and shrinking automatically upon need: however, resources starvation occurs frequently as expansion has to compete with other virtual machines running long-living batch jobs. Such batch nodes cannot relinquish their resources in a timely fashion: the more jobs they run, the longer it takes to drain them and shut off, and making one-job virtual machines introduces a non-negligible virtualization overhead. By improving several components of the Virtual Analysis Facility we have realized an experimental “Docked” Analysis Facility for ALICE, which leverages containers instead of virtual machines for providing performance and security isolation. We will present the techniques we have used to address practical problems, such as software provisioning through CVMFS, as well as our considerations on the maturity of containers for High Performance Computing. As the abstraction layer is thinner, our Docked Analysis Facilities may feature a more fine-grained sizing, down to single-job node containers: we will show how this approach will positively impact automatic cluster resizing by deploying lightweight pilot containers instead of replacing central queue polls.

  5. Defense In-Depth Accident Analysis Evaluation of Tritium Facility Bldgs. 232-H, 233-H, and 234-H

    International Nuclear Information System (INIS)

    'The primary purpose of this report is to document a Defense-in-Depth (DID) accident analysis evaluation for Department of Energy (DOE) Savannah River Site (SRS) Tritium Facility Buildings 232-H, 233-H, and 234-H. The purpose of a DID evaluation is to provide a more realistic view of facility radiological risks to the offsite public than the bounding deterministic analysis documented in the Safety Analysis Report, which credits only Safety Class items in the offsite dose evaluation.'

  6. Monitoring the performances of a real scale municipal solid waste composting and a biodrying facility using respiration activity indices.

    Science.gov (United States)

    Evangelou, Alexandros; Gerassimidou, Spyridoula; Mavrakis, Nikitas; Komilis, Dimitrios

    2016-05-01

    Objective of the work was to monitor two full-scale commingled municipal solid waste (MSW) mechanical and biological pretreatment (MBT) facilities in Greece, namely a biodrying and a composting facility. Monitoring data from a 1.5-year sampling period is presented, whilst microbial respiration indices were used to monitor the decomposition process and the stability status of the wastes in both facilities during the process. Results showed that in the composting facility, the organic matter reduced by 35 % after 8 weeks of combined composting/curing. Material exiting the biocells had a moisture content of less than 30 % (wb) indicating a moisture limitation during the active composting process. The static respiration indexes indicated that some stabilization occurred during the process, but the final material could not be characterized as stable compost. In the biodrying facility, the initial and final moisture contents were 50 % and less than 20 % wb, respectively, and the biodrying index was equal to 4.1 indicating effective biodrying. Lower heating values at the inlet and outlet were approximately 5.5 and 10 MJ/wet kg, respectively. The organic matter was reduced by 20 % during the process and specifically from a range of 63-77 % dw (inlet) to a range of 61-70 % dw. A significant respiration activity reduction was observed for some of the biodrying samples. A statistically significant correlation among all three respiration activity indices was recorded, with the two oxygen related activity indices (CRI7 and SRI24) observing the highest correlation.

  7. Monitoring the performances of a real scale municipal solid waste composting and a biodrying facility using respiration activity indices.

    Science.gov (United States)

    Evangelou, Alexandros; Gerassimidou, Spyridoula; Mavrakis, Nikitas; Komilis, Dimitrios

    2016-05-01

    Objective of the work was to monitor two full-scale commingled municipal solid waste (MSW) mechanical and biological pretreatment (MBT) facilities in Greece, namely a biodrying and a composting facility. Monitoring data from a 1.5-year sampling period is presented, whilst microbial respiration indices were used to monitor the decomposition process and the stability status of the wastes in both facilities during the process. Results showed that in the composting facility, the organic matter reduced by 35 % after 8 weeks of combined composting/curing. Material exiting the biocells had a moisture content of less than 30 % (wb) indicating a moisture limitation during the active composting process. The static respiration indexes indicated that some stabilization occurred during the process, but the final material could not be characterized as stable compost. In the biodrying facility, the initial and final moisture contents were 50 % and less than 20 % wb, respectively, and the biodrying index was equal to 4.1 indicating effective biodrying. Lower heating values at the inlet and outlet were approximately 5.5 and 10 MJ/wet kg, respectively. The organic matter was reduced by 20 % during the process and specifically from a range of 63-77 % dw (inlet) to a range of 61-70 % dw. A significant respiration activity reduction was observed for some of the biodrying samples. A statistically significant correlation among all three respiration activity indices was recorded, with the two oxygen related activity indices (CRI7 and SRI24) observing the highest correlation. PMID:27098520

  8. Thermohydraulic analysis of the IAEA standard problem test on the PMK-NHV facility

    International Nuclear Information System (INIS)

    International Atomic Energy Agency (IAEA) has supported a standard test problem simulating small break loss of coolant accident on the test facility PMH-NHV in Budapest. The present pretest analysis of that transient was done using the computer code RELAP4/MOD6. The results were compared to the measurements data and to data of 19 other laboratories around the world that have performed the same analysis. The correspondence of the results to the measured data is reasonable. There are bigger discrepancies, which in turn influence other variables. (author)

  9. Safety Analysis (SA) of the decontamination facility, Building 419, at the Lawrence Livermore National Laboratory

    International Nuclear Information System (INIS)

    This safety analysis was performed for the Manager, Plant Services at LLNL and fulfills the requirements of DOE Order 5481.1. The analysis was based on field inspections, document review, computer calculations, and extensive input from Waste Management personnel. It was concluded that the maximum quantities of radioactive materials that safety procedures allow to be handled in this building do not pose undue risks on- or off-site even in postulated severe accidents. Risk from the various hazards at this facility vary from low to moderate as specified in DOE Order 5481.1. Recommendations are made for improvements that will reduce risks even further

  10. Software systems for processing and analysis at the NOVA high-energy laser facility

    International Nuclear Information System (INIS)

    A typical laser interaction experiment at the NOVA high-energy laser facility produces in excess of 20 Mbytes of digitized data. Extensive processing and analysis of this raw data from a wide variety of instruments is necessary to produce results that can be readily used to interpret the experiment. Using VAX-based computer hardware, software systems have been set up to convert the digitized instrument output to physics quantities describing the experiment. A relational data-base management system is used to coordinate all levels of processing and analysis. Software development emphasizes structured design, flexibility, automation, and ease of use

  11. Analysis of HR activities in selected company

    OpenAIRE

    Jandová, Šárka

    2012-01-01

    The aim of this thesis is based on theoretical knowledge and analysis of the basic HR activities in the selected company to identify the strengths and weaknesses of the policies implemented personnel work. Then propose an effective ways of improving HR activities and employee satisfaction. Basic personal activities analyzed in this thesis are the adaptation, acquisition and selection of employees, performance management and staff appraisal, remuneration and training of staff. Analysis of pers...

  12. Uncertainty Analysis of non-point source pollution control facilities design techniques in Korea

    Science.gov (United States)

    Lee, J.; Okjeong, L.; Gyeong, C. B.; Park, M. W.; Kim, S.

    2015-12-01

    The design of non-point sources control facilities in Korea is divided largely by the stormwater capture ratio, the stormwater load capture ratio, and the pollutant reduction efficiency of the facility. The stormwater capture ratio is given by a design formula as a function of the water quality treatment capacity, the greater the capacity, the more the amount of stormwater intercepted by the facility. The stormwater load capture ratio is defined as the ratio of the load entering the facility of the total pollutant load generated in the target catchment, and is given as a design formula represented by a function of the stormwater capture ratio. In order to estimate the stormwater capture ratio and load capture ratio, a lot of quantitative analysis of hydrologic processes acted in pollutant emission is required, but these formulas have been applied without any verification. Since systematic monitoring programs were insufficient, verification of these formulas was fundamentally impossible. However, recently the Korean ministry of Environment has conducted an long-term systematic monitoring project, and thus the verification of the formulas became possible. In this presentation, the stormwater capture ratio and load capture ratio are re-estimated using actual TP data obtained from long-term monitoring program at Noksan industrial complex located in Busan, Korea. Through the re-estimated process, the uncertainty included in the design process that has been applied until now will be shown in a quantitative extent. In addition, each uncertainty included in the stormwater capture ratio estimation and in the stormwater load capture ratio estimation will be expressed to quantify the relative impact on the overall non-point pollutant control facilities design process. Finally, the SWMM-Matlab interlocking module for model parameters estimation will be introduced. Acknowledgement This subject is supported by Korea Ministry of Environment as "The Eco Innovation Project : Non

  13. Conference on Instrumental Activation Analysis: IAA 89

    Science.gov (United States)

    Vobecky, M.; Obrusnik, I.

    1989-05-01

    The proceedings contain 40 abstracts of papers all of which have been incorporated in INIS. The papers were centred on the applications of radioanalytical methods, especially on neutron activation analysis, x ray fluorescence analysis, PIXE analysis and tracer techniques in biology, medicine and metallurgy, measuring instruments including microcomputers, and data processing methods.

  14. 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.

  15. Measuring neutron yield and ρR anisotropies with activation foils at the National Ignition Facility

    Directory of Open Access Journals (Sweden)

    Bleuel D.L.

    2013-11-01

    Full Text Available Neutron yields at the National Ignition Facility (NIF are measured with a suite of diagnostics, including activation of ∼20–200 g samples of materials undergoing a variety of energy-dependent neutron reactions. Indium samples were mounted on the end of a Diagnostic Instrument Manipulator (DIM, 25–50 cm from the implosion, to measure 2.45 MeV D-D fusion neutron yield. The 336.2 keV gamma rays from the 4.5 hour isomer of 115mIn produced by (n,n′ reactions are counted in high-purity germanium detectors. For capsules producing D-T fusion reactions, zirconium and copper are activated via (n,2n reactions at various locations around the target chamber and bay, measuring the 14 MeV neutron yield to accuracies on order of 7%. By mounting zirconium samples on ports at nine locations around the NIF chamber, anisotropies in the primary neutron emission due to fuel areal density asymmetries can be measured to a relative precision of 3%.

  16. Facile synthesis of PdAgTe nanowires with superior electrocatalytic activity

    Science.gov (United States)

    Hong, Wei; Wang, Jin; Wang, Erkang

    2014-12-01

    In this work, ultrathin Te nanowires (NWs) with high-aspect-ratio are prepared by a simple hydrothermal method. By using Te NWs as the sacrificial template, we demonstrate a facile and efficient method for the synthesis of PdAgTe NWs with high-quality through the partly galvanic replacement between Te NWs and the corresponding noble metal salts precursors in an aqueous solution. The compositions of PdAgTe NWs can be tuned by simply altering the concentration of the precursors. After cyclic voltammetry treatment, multi-component PdAgTe NW with a highly active and stable surface can be obtained. The structure and composition of the as-prepared nanomaterials are analyzed by transmission electron microscope, X-ray diffraction, energy dispersive X-ray spectroscopy, inductively coupled plasma-mass spectroscopy and X-ray photoelectron spectroscopy. Electrochemical catalytic measurement results prove that the as synthesized PdAgTe NWs present superior catalytic activity toward ethanol electrooxidation in alkaline solution than the commercial Pd/C catalyst, which making them can be used as effective catalysts for the direct ethanol fuel cells.

  17. Seismic risk analysis for the Atomics International Nuclear Materials Development Facility, Santa Susana California

    International Nuclear Information System (INIS)

    This report presents the results of a detailed seismic risk analysis of the Nuclear Materials Development Facility (NMDF) operated by Atomics International at Santa Susana, California. The historical seismic record was established after a review of available literature, consultation with operators of local seismic arrays and examination of appropriate seismic data bases including the USGS, California Institute of Technology and NEIS data bases. The resulting seismic record, covering the period 1969 to 1977, was used to identify all possible sources of seismicity that could affect the site. The best estimate curve indicates that the facility will experience 30% g with a return period of 55 years and 60% g with a return period of 750 years

  18. 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.

  19. Beam Based HOM Analysis of Acceleating Structures at the TESLA Test Facility LINAC

    CERN Document Server

    Wendt, M; Gössel, A

    2003-01-01

    The beam emittance in future linear accelerators for high energy physics and SASE-FEL applications depends highly on the field performance in the accelerating structures, i.e. the damping of higher order modes (HOM). Besides theoretical and laboratory analysis (network analyzer), a beam based analysis technique was established [S. Fartoukh, et.al., Proceedings of the PAC99 Conference] at the TESLA Test Facility (TTF) linac. It uses a charge modulated beam of variable modulation frequency to excite dipole modes. This causes a modulation of the transverse beam displacement, which is observed at a downstream BPM and associated with a direct analysis of the modes at the HOM couplers. Emphasis of this presentation is put on beam instrumentation and signal analysis aspects. A brief introduction of eigenmodes in resonant structures, as well as some interesting measurement results are further presented.

  20. A software architectural framework specification for neutron activation analysis

    International Nuclear Information System (INIS)

    Neutron Activation Analysis (NAA) is a sensitive multi-element nuclear analytical technique that has been routinely applied by research reactor (RR) facilities to environmental, nutritional, health related, geological and geochemical studies. As RR facilities face calls to increase their research output and impact, with existing or reducing budgets, automation of NAA offers a possible solution. However, automation has many challenges, not the least of which is a lack of system architecture standards to establish acceptable mechanisms for the various hardware/software and software/software interactions among data acquisition systems, specialised hardware such as sample changers, sample loaders, and data processing modules. This lack of standardization often results in automation hardware and software being incompatible with existing system components, in a facility looking to automate its NAA operations. This limits the availability of automation to a few RR facilities with adequate budgets or in-house engineering resources. What is needed is a modern open system architecture for NAA, that provides the required set of functionalities. This paper describes such an 'architectural framework' (OpenNAA), and portions of a reference implementation. As an example of the benefits, calculations indicate that applying this architecture to the compilation and QA steps associated with the analysis of 35 elements in 140 samples, with 14 SRM's, can reduce the time required by over 80 %. The adoption of open standards in the nuclear industry has been very successful over the years in promoting interchangeability and maximising the lifetime and output of nuclear measurement systems. OpenNAA will provide similar benefits within the NAA application space, safeguarding user investments in their current system, while providing a solid path for development into the future. (author)

  1. ALL-PATHWAYS DOSE ANALYSIS FOR THE PORTSMOUTH ON-SITE WASTE DISPOSAL FACILITY

    Energy Technology Data Exchange (ETDEWEB)

    Smith, F.; Phifer, M.

    2014-04-10

    A Portsmouth On-Site Waste Disposal Facility (OSWDF) All-Pathways analysis has been conducted that considers the radiological impacts to a resident farmer. It is assumed that the resident farmer utilizes a farm pond contaminated by the OSWDF to irrigate a garden and pasture and water livestock from which food for the resident farmer is obtained, and that the farmer utilizes groundwater from the Berea sandstone aquifer for domestic purposes (i.e. drinking water and showering). As described by FBP 2014b the Hydrologic Evaluation of Landfill Performance (HELP) model (Schroeder et al. 1994) and the Surface Transport Over Multiple Phases (STOMP) model (White and Oostrom 2000, 2006) were used to model the flow and transport from the OSWDF to the Points of Assessment (POAs) associated with the 680-ft elevation sandstone layer (680 SSL) and the Berea sandstone aquifer. From this modeling the activity concentrations radionuclides were projected over time at the POAs. The activity concentrations were utilized as input to a GoldSimTM (GTG 2010) dose model, described herein, in order to project the dose to a resident farmer over time. A base case and five sensitivity cases were analyzed. The sensitivity cases included an evaluation of the impacts of using a conservative inventory, an uncased well to the Berea sandstone aquifer, a low waste zone uranium distribution coefficient (Kd), different transfer factors, and reference person exposure parameters (i.e. at 95 percentile). The maximum base case dose within the 1,000 year assessment period was projected to be 1.5E-14 mrem/yr, and the maximum base case dose at any time less than 10,000 years was projected to be 0.002 mrem/yr. The maximum projected dose of any sensitivity case was approximately 2.6 mrem/yr associated with the use of an uncased well to the Berea sandstone aquifer. This sensitivity case is considered very unlikely because it assumes leakage from the location of greatest concentration in the 680 SSL in to the

  2. Neutron activation analysis of reference materials

    International Nuclear Information System (INIS)

    The importance is pointed out of neutron activation analysis in the preparation of reference materials, and studies are reported conducted recently by UJV. Instrumental neutron activation analysis has been used in testing homogeneity and in determining 28 elements in newly prepared reference standards of coal fly ash designated ENO, EOP and ECH. For accuracy testing, the same method was used in the analysis of NBS SRM-1633a Trace Elements in Coal Fly Ash and IAEA CRM Soil-5 and RM Soil-7. Radiochemical neutron activation analysis was used in determining Cd, Cu, Mn, Mo, and Zn in biological materials NBS SRM-1577 Bovine Liver, Bowen's Kale and in IAEA RM Milk Powder A-11 and Animal Muscle H-4. In all instances very good precision and accuracy of neutron activation analysis results were shown. (author)

  3. A survey of experiments and experimental facilities for active control of flexible structures

    Science.gov (United States)

    Sparks, Dean W., Jr.; Horner, Garnett C.; Juang, Jer-Nan; Klose, Gerhard

    1989-01-01

    A brief survey of large space structure control related experiments and facilities was presented. This survey covered experiments performed before and up to 1982, and those of the present period (1982-...). Finally, the future planned experiments and facilities in support of the control-structure interaction (CSI) program were reported. It was stated that new, improved ground test facilities are needed to verify the new CSI design techniques that will allow future space structures to perform planned NASA missions.

  4. Benchmarking study and its application for shielding analysis of large accelerator facilities

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Hee-Seock; Kim, Dong-hyun; Oranj, Leila Mokhtari; Oh, Joo-Hee; Lee, Arim; Jung, Nam-Suk [POSTECH, Pohang (Korea, Republic of)

    2015-10-15

    Shielding Analysis is one of subjects which are indispensable to construct large accelerator facility. Several methods, such as the Monte Carlo, discrete ordinate, and simplified calculation, have been used for this purpose. The calculation precision is overcome by increasing the trial (history) numbers. However its accuracy is still a big issue in the shielding analysis. To secure the accuracy in the Monte Carlo calculation, the benchmarking study using experimental data and the code comparison are adopted fundamentally. In this paper, the benchmarking result for electrons, protons, and heavy ions are presented as well as the proper application of the results is discussed. The benchmarking calculations, which are indispensable in the shielding analysis were performed for different particles: proton, heavy ion and electron. Four different multi-particle Monte Carlo codes, MCNPX, FLUKA, PHITS, and MARS, were examined for higher energy range equivalent to large accelerator facility. The degree of agreement between the experimental data including the SINBAD database and the calculated results were estimated in the terms of secondary neutron production and attenuation through the concrete and iron shields. The degree of discrepancy and the features of Monte Carlo codes were investigated and the application way of the benchmarking results are discussed in the view of safety margin and selecting the code for the shielding analysis. In most cases, the tested Monte Carlo codes give proper credible results except of a few limitation of each codes.

  5. OVERVIEW OF UAV ACTIVITIES IN WAGENINGEN UNMANNED AERIAL REMOTE SENSING FACILITY

    Directory of Open Access Journals (Sweden)

    J. Suomalainen

    2015-08-01

    Full Text Available The WUR Unmanned Aerial Remote Sensing Facility (UARSF (www.wageningenur.nl/uarsf is a co-operation organization of different groups within Wageningen University and Research Centre to use UAVs in remote sensing applications. The facility was founded in 2012. Since then the facility has taken part in numerous of mapping campaigns exploiting UAVs with researchers with in WUR as well as external cooperating partners. In this paper/poster we present the facility, the UAV platforms, the camera systems, and demonstrate some highlights of our results.

  6. Fermilab D-0 Experimental Facility: Energy conservation report and mechanical systems design optimization and cost analysis study

    International Nuclear Information System (INIS)

    This report is developed as part of the Fermilab D-0 Experimental Facility Project Title II Design Documentation Update. As such, it concentrates primarily on HVAC mechanical systems design optimization and cost analysis

  7. Development of cancer therapy facility of HANARO and medical research in BNCT; development of the technique for boron concentration analysis

    Energy Technology Data Exchange (ETDEWEB)

    Choi, Hee Dong; Byun, Soo Hyun; Sun, Gwang Min; Kim, Suk Kwon; Kim, In Jung; Park, Chang Su [Seoul National University, Seoul (Korea)

    2002-03-01

    Objective and Necessity of the Project- Development of a boron concentration analysis facility used for BNCT. - Development of the technique for boron concentration analysis. Contents and Scopes of the Project - Construction of the boron concentration analysis facility based on PGAA. Estimation of the neutron beam characteristics. -Establishment of the technique for the boron concentration analysis. - Estimation of the reliability for the boron analysis. Results of the Project -Installation of the boron concentration analysis facility at Hanaro. - Neutron beam characteristics are the sample position (neutron flux : 7.9 x 10{sup 7} n/cm{sup 2}s, Cd-ratio : 266) Technique for the boron concentration analysis. - Boron detection sensitivity and limit (detection sensitivity : 2, 131 cps/mg-B, detection limit : 67 ng for 10,000 sec). 63 refs., 37 figs., 13 tabs. (Author)

  8. COGEMA's UMF [Uranium Management Facility

    International Nuclear Information System (INIS)

    The French government-owned corporation, COGEMA, is responsible for the nuclear fuel cycle. This paper describes the activities at COGEMA's Pierrelatte facility, especially its Uranium Management Facility. UF6 handling and storage is described for natural, enriched, depleted, and reprocessed uranium. UF6 quality control specifications, sampling, and analysis (halocarbon and volatile fluorides, isotopic analysis, uranium assay, and impurities) are described. In addition, the paper discusses the filling and cleaning of containers and security at UMF

  9. CFD Analysis for Natural Convection Induced by Steam Condensation in the THAI Facility

    International Nuclear Information System (INIS)

    A series of tests were performed to investigate this design feature of the PWR in Germany. One of the tests was to investigate the dissolution of a steam-air stratification by natural convection in the THAI (Thermal hydraulics, Hydrogen, Aerosol, and Iodine) facility of 9.2 m height and 3.2 m diameter. In addition, the test results are used as validation data for development of numerical models in the lumped parameter codes and the computational fluid dynamics (CFD) codes for simulating the multiphase flow field in the containment. In this study, STAR-CCM+ 9.04 was used to evaluate its models for simulating the dissolution of a steam-air stratification induced by the natural convection in the THAI facility. Through the comparison of the simulated results with the test results performed in the THAI facility, we found that STAR-CCM+ 9.04 with the fluid film model simulating the steam condensation predicted the steam concentration, the gas temperature, and the vessel wall temperature with an error range of about ±20%. In order to decrease the discrepancy between the CFD and test results, a detailed analysis on the fluid film model and the conjugate heat transfer through the vessel wall should be performed. Furthermore, the total calculation time should be extended to about 2000 s for better comparison between the CFD results and test data

  10. Neutron activation analysis of geochemical samples

    International Nuclear Information System (INIS)

    The present paper will describe the work done at the Technical Research Centre of Finland in developing methods for the large-scale activation analysis of samples for the geochemical prospecting of metals. The geochemical prospecting for uranium started in Finland in 1974 and consequently a manually operated device for the delayed neutron activation analysis of uranium was taken into use. During 1974 9000 samples were analyzed. The small capacity of the analyzer made it necessary to develop a completely automated analyzer which was taken into use in August 1975. Since then 20000-30000 samples have been analyzed annually the annual capacity being about 60000 samples when running seven hours per day. Multielemental instrumental neutron activation analysis is used for the analysis of more than 40 elements. Using instrumental epithermal neutron activation analysis 25-27 elements can be analyzed using one irradiation and 20 min measurement. During 1982 12000 samples were analyzed for mining companies and Geological Survey of Finland. The capacity is 600 samples per week. Besides these two analytical methods the analysis of lanthanoids is an important part of the work. 11 lanthanoids have been analyzed using instrumental neutron activation analysis. Radiochemical separation methods have been developed for several elements to improve the sensitivity of the analysis

  11. Relationships between Physical Activity and the Proximity of Exercise Facilities and Home Exercise Equipment Used by Undergraduate University Students.

    Science.gov (United States)

    Reed, Julian A.; Phillips, D. Allen

    2005-01-01

    The authors used stratified random sampling procedures to investigate the relationships among physical activity (PA), the proximity of exercise facilities, and the quantity of home exercise equipment in a sample of 411 undergraduates. To examine the data they collected from the modified Godin Leisure-Time Exercise Questionnaire and the Home…

  12. Flow measurement by pulsed-neutron activation techniques at the PKL facility at Erlangen (Germany). [PWR

    Energy Technology Data Exchange (ETDEWEB)

    Kehler, P.

    1982-03-01

    Flow velocities in the downcomer at the PKL facility (in Erlangen, Germany) were measured by the Pulsed-Neutron Activation (PNA) techniques. This was the first time that a fully automated PNA system, incorporating a dedicated computer for on-line data reduction, was used for flow measurements. A prototype of a portable, pulsed, high-output neutron source, developed by the Sandia National Laboratories for the US Nuclear Regulatory Commission, was also successfully demonstrated during this test. The PNA system was the primary flow-measuring device used at the PKL, covering the whole range of velocities of interest. In this test series, the PKL simulated small-break accidents similar to the one that occurred at TMI. The flow velocities in the downcomer were, therefore, very low, ranging between 0.03 and 0.35 m/sec. Two additional flow-measuring methods were used over a smaller range of velocities. Wherever comparison was possible, the PNA-derived velocity values agreed well with the measurements performed by the two more conventional methods.

  13. The NASA Heliophysics Active Final Archive at the Space Physics Data Facility

    Science.gov (United States)

    McGuire, Robert E.

    2012-01-01

    The 2009 NASA Heliophysics Science Data Management Policy re-defined and extended the responsibilities of the Space Physics Data Facility (SPDF) project. Building on SPDF's established capabilities, the new policy assigned the role of active "Final Archive" for non-solar NASA Heliophysics data to SPDF. The policy also recognized and formalized the responsibilities of SPDF as a source for critical infrastructure services such as VSPO to the overall Heliophysics Data Environment (HpDE) and as a Center of Excellence for existing SPDF science-enabling services and software including CDAWeb, SSCWeb/4D Orbit Viewer, OMNIweb and CDF. We will focus this talk to the principles, strategies and planned SPDF architecture to effectively and efficiently perform these roles, with special emphasis on how SPDF will ensure the long-term preservation and ongoing online community access to all the data entrusted to SPDF. We will layout our archival philosophy and what we are advocating in our work with NASA missions both current and future, with potential providers of NASA and NASA-relevant archival data, and to make the data and metadata held by SPDF accessible to other systems and services within the overall HpOE. We will also briefly review our current services, their metrics and our current plans and priorities for their evolution.

  14. Scientific Ballooning Activities and Recent Developments in Technology and Instrumentation of the TIFR Balloon Facility, Hyderabad

    Science.gov (United States)

    Buduru, Suneel Kumar

    2016-07-01

    The Balloon Facility of Tata Institute of Fundamental Research (TIFR-BF) is a unique center of expertise working throughout the year to design, fabricate and launch scientific balloons mainly for space astronomy, atmospheric science and engineering experiments. Recently TIFR-BF extended its support to new user scientists for conducting balloon launches for biological and middle atmospheric sciences. For the first time two balloon launches conducted for sending live lab rats to upper stratosphere and provided launch support for different balloon campaigns such as Tropical Tropopause Dynamics (TTD) to study water vapour content in upper tropospheric and lower stratospheric regions over Hyderabad and the other balloon campaign to study the Asian Tropopause Aerosol Layer (BATAL) during the Indian summer monsoon season. BATAL is the first campaign to conduct balloon launches during active (South-West) monsoon season using zero pressure balloons of different volumes. TIFR-BF also provided zero pressure and sounding balloon support to various research institutes and organizations in India and for several international space projects. In this paper, we present details on our increased capability of balloon fabrication for carrying heavier payloads, development of high strength balloon load tapes and recent developments of flight control and safety systems. A summary of the various flights conducted in two years will be presented along with the future ballooning plans.

  15. Enhanced Photocatalytic Activity of BiOBr/ZnO Heterojunction Semiconductors Prepared by Facile Hydrothermal Method

    Directory of Open Access Journals (Sweden)

    Xiangchao Meng

    2015-01-01

    Full Text Available Hexagonal wurtzite pure ZnO and BiOBr-ZnO composites were synthesized by facile hydrothermal method. The amount of BiOBr as dopant was adjusted from 5 wt.% to 75 wt.%, and correspondingly the morphologies and crystal structures of the as-prepared composites were measured and discussed. Specifically, according to XRD patterns and SEM images, the main crystalline structure of ZnO was not destroyed after doping, but growth of ZnO crystals was inhibited by doping BiOBr. Meanwhile, the optical properties of the composites were measured by the diffuse reflectance spectra (DRS. The band gap of composites was also calculated using the classical Tauc equation and it was found to be around 3.0 eV. In the test of photocatalytic activation, the ZnO-BiOBr photocatalysts exhibited high photocatalytic efficiencies in the degradation of Rhodamine B (RhB under visible-light irradiation. It was ascribed to not only the small size of crystalline, but also the reduction in the recombination rate of the photogenerated carriers for the enhancement effect of p-n heterojunction. This work sheds light on improving the photocatalytic performance by establishing the heterojunction and contributes to the development of a commercially competitive photocatalyst.

  16. FACILE GREEN SYNTHESIS OF GOLD NANOPARTICLES WITH GREAT CATALYTIC ACTIVITY USING ULVA FASCIATA

    Directory of Open Access Journals (Sweden)

    V. Sugantha Kumari

    2014-03-01

    Full Text Available We report a facile, green, and high yielding approache for the synthesis and stabilization of monodisperse gold nanoparticles (AuNPs using green seaweed Ulva fasciata extract. Characterization of the obtained AuNPs was performed using UV-visible, Fourier transform infrared (FTIR, X-ray diffraction (XRD and transmission electron microscopy (TEM. UV-visible absorption spectroscopy was used to determine the yield of the gold nanoparticles. The UV-visible absorption spectrum showed a characteristic optical peak of AuNPs at 541 nm. The X-ray diffraction pattern suggested the formation and crystallinity of AuNPs. Spherical AuNPs synthesized with an average particle size of 10 ± 3 nm were confirmed by TEM. FTIR analysis supported the role of phytochemicals of Ulva fasciata extract for bioreduction and stabilization of AuNPs. Moreover, the synthesized AuNPs exhibit remarkable catalytic efficiency by using the reduction of 4-nitroaniline by potassium borohydride in aqueous solution using UV-visible absorption spectroscopy. Catalytic reduction followed pseudo-first-order kinetics with respect to 4-Nitrophenol.

  17. The analysis and selection of methods and facilities for cutting of naturally-deficit materials

    Science.gov (United States)

    Akhmetov, I. D.; Zakirova, A. R.; Sadykov, Z. B.

    2016-06-01

    The comparison of perspective methods is done in the article, such as laser, plasma and combined electro-diamond methods of hard processed materials cutting. There are the review and analysis of naturally-deficit materials cutting facilities. A new electrode-tool for the combined cutting of naturally-deficit materials is suggested. This electrode-tool eliminates electrical contact between the cutting electrode-tool and side surfaces of the channel of cutting workpiece cut, which allows to obtain coplanar channels of cut.

  18. Scaling analysis for the European heavy liquid metal scaled pool facility escape

    Energy Technology Data Exchange (ETDEWEB)

    Van Tichelen, K.; Vanderhaegen, M. [SCK CEN, Mol (Belgium); Jajarayu, S. [NRG, Petten (Netherlands); Keijers, S. [SCK CEN, Mol (Belgium); Roelofs, F. [NRG, Petten (Netherlands)

    2011-07-01

    The understanding of the thermal-hydraulic phenomena occurring in the reactor pool is a critical issue in the design of the MYRRHA system, the European Technology Pilot Plant for the Lead Fast Reactor. The E-SCAPE facility is a thermal-hydraulic scale model of the MYRRHA reactor using lead-bismuth as coolant. Non-dimensional analysis and CFD simulations are used to determine the scaling factors and transposition of the experimental results to the real scale situation. The joint efforts of SCK·CEN and NRG within the European project THINS in applying CFD to fix the design parameters of E-SCAPE is reported. (author)

  19. Production planning and control for semiconductor wafer fabrication facilities modeling, analysis, and systems

    CERN Document Server

    Mönch, Lars; Mason, Scott J

    2012-01-01

    Over the last fifty-plus years, the increased complexity and speed of integrated circuits have radically changed our world. Today, semiconductor manufacturing is perhaps the most important segment of the global manufacturing sector. As the semiconductor industry has become more competitive, improving planning and control has become a key factor for business success. This book is devoted to production planning and control problems in semiconductor wafer fabrication facilities. It is the first book that takes a comprehensive look at the role of modeling, analysis, and related information systems

  20. 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.

  1. 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

  2. GIS analysis of the siting criteria for the Mixed and Low-Level Waste Treatment Facility and the Idaho Waste Processing Facility

    Energy Technology Data Exchange (ETDEWEB)

    Hoskinson, R.L.

    1994-01-01

    This report summarizes a study conducted using the Arc/Info{reg_sign} geographic information system (GIS) to analyze the criteria used for site selection for the Mixed and Low-Level Waste Treatment Facility (MLLWTF) and the Idaho Waste Processing Facility (IWPF). The purpose of the analyses was to determine, based on predefined criteria, the areas on the INEL that best satisfied the criteria. The coverages used in this study were produced by importing the AutoCAD files that produced the maps for a pre site selection draft report into the GIS. The files were then converted to Arc/Info{reg_sign} GIS format. The initial analysis was made by considering all of the criteria as having equal importance in determining the areas of the INEL that would best satisfy the requirements. Another analysis emphasized four of the criteria as ``must`` criteria which had to be satisfied. Additional analyses considered other criteria that were considered for, but not included in the predefined criteria. This GIS analysis of the siting criteria for the IWPF and MLLWTF provides a logical, repeatable, and defensible approach to the determination of candidate locations for the facilities. The results of the analyses support the location of the Candidate Locations.

  3. Applications of neutron activation analysis in industry

    International Nuclear Information System (INIS)

    Neutron activation analysis technique is discussed in brief. This technique is used for quality control of raw materials, process materials and finished products, as well as activities in research and development for the improvement of the products and new products. The uses of this technique in several experienced industries are mentioned (author)

  4. New studies in forensic neutron activation analysis

    International Nuclear Information System (INIS)

    Three recently completed studies in forensic neutron activation analysis are reported: a study of 0.22-caliber rimfire cartridge primers, a large-scale study of shotgun pellets, and a new 5-element procedure for the analysis of bullet-lead and shotgun-pellet samples. (author) 12 refs

  5. New studies in forensic neutron activation analysis

    International Nuclear Information System (INIS)

    Earlier studies in forensic neutron activation analysis are being extended in This Laboratory. Three of these new studies are reported here: 1) a study of 0.22-caliber rimfire cartridge primers, 2) a large-scale study of shotgun pellets, and 3) a new 5-element procedure for the analysis of bullet-lead and shotgun-pellet samples. (author)

  6. Computational Models for Analysis of Illicit Activities

    DEFF Research Database (Denmark)

    Nizamani, Sarwat

    Numerous illicit activities happen in our society, which, from time to time affect the population by harming individuals directly or indirectly. Researchers from different disciplines have contributed to developing strategies to analyze such activities, in order to help law enforcement agents dev...... population globally sensitive to specific world issues. The models discuss the dynamics of population in response to such issues. All the models presented in the thesis can be combined for a systematic analysis of illicit activities.......Numerous illicit activities happen in our society, which, from time to time affect the population by harming individuals directly or indirectly. Researchers from different disciplines have contributed to developing strategies to analyze such activities, in order to help law enforcement agents...... devise policies to minimize them. These activities include cybercrimes, terrorist attacks or violent actions in response to certain world issues. Beside such activities, there are several other related activities worth analyzing, for which computational models have been presented in this thesis...

  7. The role of human error in risk analysis: Application to pre- and post-maintenance procedures of process facilities

    International Nuclear Information System (INIS)

    Human factors play an important role in the safe operation of a facility. Human factors include the systematic application of information about human characteristics and behavior to increase the safety of a process system. A significant proportion of human errors occur during the maintenance phase. However, the quantification of human error probabilities in the maintenance phase has not been given the amount of attention it deserves. This paper focuses on a human factors analysis in pre-and post- pump maintenance operations. The procedures for removing process equipment from service (pre-maintenance) and returning the equipment to service (post-maintenance) are considered for possible failure scenarios. For each scenario, human error probability is calculated for each activity using the Success Likelihood Index Method (SLIM). Consequences are also assessed in this methodology. The risk assessment is conducted for each component and the overall risk is estimated by adding individual risks. The present study is aimed at highlighting the importance of considering human error in quantitative risk analyses. The developed methodology has been applied to a case study of an offshore process facility

  8. Automated absolute activation analysis with californium-252 sources

    Energy Technology Data Exchange (ETDEWEB)

    MacMurdo, K.W.; Bowman, W.W.

    1978-09-01

    A 100-mg /sup 252/Cf neutron activation analysis facility is used routinely at the Savannah River Laboratory for multielement analysis of many solid and liquid samples. An absolute analysis technique converts counting data directly to elemental concentration without the use of classical comparative standards and flux monitors. With the totally automated pneumatic sample transfer system, cyclic irradiation-decay-count regimes can be pre-selected for up to 40 samples, and samples can be analyzed with the facility unattended. An automatic data control system starts and stops a high-resolution gamma-ray spectrometer and/or a delayed-neutron detector; the system also stores data and controls output modes. Gamma ray data are reduced by three main programs in the IBM 360/195 computer: the 4096-channel spectrum and pertinent experimental timing, counting, and sample data are stored on magnetic tape; the spectrum is then reduced to a list of significant photopeak energies, integrated areas, and their associated statistical errors; and the third program assigns gamma ray photopeaks to the appropriate neutron activation product(s) by comparing photopeak energies to tabulated gamma ray energies. Photopeak areas are then converted to elemental concentration by using experimental timing and sample data, calculated elemental neutron capture rates, absolute detector efficiencies, and absolute spectroscopic decay data. Calculational procedures have been developed so that fissile material can be analyzed by cyclic neutron activation and delayed-neutron counting procedures. These calculations are based on a 6 half-life group model of delayed neutron emission; calculations include corrections for delayed neutron interference from /sup 17/O. Detection sensitivities of < or = 400 ppB for natural uranium and 8 ppB (< or = 0.5 (nCi/g)) for /sup 239/Pu were demonstrated with 15-g samples at a throughput of up to 140 per day. Over 40 elements can be detected at the sub-ppM level.

  9. Evaluation of business activity using financial analysis

    OpenAIRE

    Kučerová, Martina

    2012-01-01

    Czech University of Life Sciences Prague Faculty of Economics and Management Department of Trade and Accounting Abstract of Diploma Thesis Evaluation of business activity using financial analysis Martina Kučerová © 2012 CULS in Prague Summary: The aim of this thesis is to apply methods of financial analysis on chosen business for its first three accounting periods 2009, 2010 and 2011. The thesis is further analysis of my bachelor thesis on to...

  10. Analysis of prompt decay experiments for ADS reactivity monitoring at VENUS-F facility

    International Nuclear Information System (INIS)

    The strategy chosen to monitor a subcritical core reactivity combines two approaches: 1) the on-line monitoring of the relative fluctuations of the reactivity ρ(t), due to the measurement of the ratio of the beam intensity to the reactor power; 2) some calibration measurements, performed regularly, providing an absolute level of ρ. These absolute or calibration measurements are performed during beam interruptions and are based on the analysis of the time decay of the reactor neutron population, N(t). Different analysis techniques can be applied, but most of them require analysing both prompt and delayed neutron contributions (as the area method). Consequently, to give precise results, these techniques require the use of long beam interruptions of several ms durations. This paper focuses on the prompt decay part of N(t) and presents a method to determine the prompt multiplication factor kp, from which the keff can be inferred. This method requires shorter beam interruptions of a few tens of microseconds. The method is applied to Pulsed Neutron Source (PNS) measurements at the VENUS-F facility. The VENUS-F Facility is a zero power ADS mock-up and consists in the vertical coupling of the VENUS reactor (at SCK-CEN, Mol, Belgium) with a deuteron accelerator GENEPI-3C

  11. Sustainability analysis in petroleum production facilities; Analise de sustentabilidade em instalacoes de producao de petroleo

    Energy Technology Data Exchange (ETDEWEB)

    Pacheco, Jose Marcos Leite [Petroleo Brasileiro S.A. (PETROBRAS), Rio de Janeiro, RJ (Brazil); Santos, Adriano [Universidade Federal do Rio Grande do Norte (UFRN), RN (Brazil); Fernandes Junior, Wilaci Eutropio [Petroleo Brasileiro S.A. (PETROBRAS), Rio de Janeiro, RJ (Brazil); Universidade Federal do Rio Grande do Norte (UFRN), RN (Brazil)

    2012-07-01

    The global sustainability aspects are discussed and a method for sustainability analysis in oil and gas production surface facilities is presented. The proposed method requires a multidisciplinary viewpoint and considers social, economic and environmental sustainability aspects during the early design programming and planning phases. Traditionally, Feasibility (Technical and Economical), Environmental Impact Assessment (EIA) and risk (Hazop) analysis are performed separately. On the other hand, the proposed methodology merges economical, environmental and social sustainability analysis; which allows deciding the most globally sustainable scenario. A checklist containing global sustainability aspects (Economical, Social, Environmental, Health, Safety, etc.) and a qualitative analysis of these aspects is suggested. The first step for applying the proposed method consists in checking the aspects and the corresponding suggestions for improving the global sustainability. Secondly, the impact of each aspect on sustainability is verified. Finally, the most important aspects are selected and different scenarios are simulated allowing choosing the most sustainable scenario. The results and conclusions are then presented in a Global Sustainability Report. The proposed analysis was applied to study the sustainability of a small offshore platform design. In this case study, several aspects that could potentially improve sustainability were identified. The simulated scenarios showed that some critical aspects contributed decisively to the global sustainability. These critical aspects are not easily identified if only the traditional economical, environmental and risk analysis are applied. (author)

  12. Facile template-free synthesis of pine needle-like Pd micro/nano-leaves and their associated electro-catalytic activities toward oxidation of formic acid

    Directory of Open Access Journals (Sweden)

    Wang Chuanyi

    2011-01-01

    Full Text Available Abstract Pine needle-like Pd micro/nano-leaves have been synthesized by a facile, template-free electrochemical method. As-synthesized Pd micro/nano-leaves were directly electrodeposited on an indium tin oxide substrate in the presence of 1.0 mM H2PdCl4 + 0.33 M H3PO4. The formation processes of Pd micro/nano-leaves were revealed by scanning electron microscope, and further characterized by X-ray diffraction and electrochemical analysis. Compared to conventional Pd nanoparticles, as-prepared Pd micro/nano-leaves exhibit superior electrocatalytic activities for the formic acid oxidation.

  13. Preclosure radiological safety analysis for accident conditions of the potential Yucca Mountain Repository: Underground facilities

    International Nuclear Information System (INIS)

    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 10-11/yr to 10-5/yr. The study identifies 33 scenarios that could result in offsite doses over 50 mrem and that have annual probabilities greater than 10-9/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

  14. Bayesian Analysis of Inertial Confinement Fusion Experiments at the National Ignition Facility

    CERN Document Server

    Gaffney, J A; Sonnad, V; Libby, S B

    2012-01-01

    We develop a Bayesian inference method that allows the efficient determination of several interesting parameters from complicated high-energy-density experiments performed on the National Ignition Facility (NIF). The model is based on an exploration of phase space using the hydrodynamic code HYDRA. A linear model is used to describe the effect of nuisance parameters on the analysis, allowing an analytic likelihood to be derived that can be determined from a small number of HYDRA runs and then used in existing advanced statistical analysis methods. This approach is applied to a recent experiment in order to determine the carbon opacity and X-ray drive; it is found that the inclusion of prior expert knowledge and fluctuations in capsule dimensions and chemical composition significantly improve the agreement between experiment and theoretical opacity calculations. A parameterisation of HYDRA results is used to test the application of both Markov chain Monte Carlo (MCMC) and genetic algorithm (GA) techniques to e...

  15. Software systems for processing and analysis of experimental data at the Nova laser facility

    International Nuclear Information System (INIS)

    A typical laser-plasma interaction experiment at the Nova laser facility produces in excess of 20 megabytes of digitized data. Extensive processing and analysis of this raw data from a wide variety of instruments is necessary to produce data that can be readily used to interpret the experiment. The authors describe how using VAX based computer hardware, a software system has been set up to convert the digitized instrument output to physics quantities describing the experiment. A relational data base management system is used to coordinate all levels of processing and analysis. Extensive data bases of instrument response and set-up parameters are used at all levels of processing and archiving. An extensive set of programs is used to handle the large amounts of X, Y, Z data recorded on film by the bulk of Nova diagnostics. Software development emphasizes structured design, flexibility, automation and ease of use

  16. Facile residue analysis of recent and prehistoric cook-stones using handheld Raman spectrometry

    CERN Document Server

    Short, Laura; Cao, Bin; Sinyukov, Alexander M; Joshi, Amitabh; Scully, Rob; Sanders, Virgil; Voronine, Dmitri V

    2013-01-01

    We performed food residue analysis of cook-stones from experimental and prehistoric earth ovens using a handheld Raman spectrometry. Progress in modern optical technology provides a facile means of rapid non-destructive identification of residue artifacts from archaeological sites. For this study spectral signatures were obtained on sotol (Dasylirion spp.) experimentally baked in an earth oven as well as sotol residue on an experimentally used processing tool. Inulin was the major residue component. The portable handheld Raman spectrometer also detected traces of inulin on boiling stones used to boil commercially obtained inulin. The Raman spectra of inulin and sotol may be useful as signatures of wild plant residues in archaeology. Spectroscopic analysis of millennia-old cook-stones from prehistoric archaeological sites in Fort Hood, TX revealed the presence of residues whose further identification requires improvement of current optical methods.

  17. An overview of research activities on materials for nuclear applications at the INL Safety, Tritium and Applied Research facility

    Energy Technology Data Exchange (ETDEWEB)

    P. Calderoni; P. Sharpe; M. Shimada

    2009-09-01

    The Safety, Tritium and Applied Research facility at the Idaho National Laboratory is a US Department of Energy National User Facility engaged in various aspects of materials research for nuclear applications related to fusion and advanced fission systems. Research activities are mainly focused on the interaction of tritium with materials, in particular plasma facing components, liquid breeders, high temperature coolants, fuel cladding, cooling and blanket structures and heat exchangers. Other activities include validation and verification experiments in support of the Fusion Safety Program, such as beryllium dust reactivity and dust transport in vacuum vessels, and support of Advanced Test Reactor irradiation experiments. This paper presents an overview of the programs engaged in the activities, which include the US-Japan TITAN collaboration, the US ITER program, the Next Generation Power Plant program and the tritium production program, and a presentation of ongoing experiments as well as a summary of recent results with emphasis on fusion relevant materials.

  18. Safety analysis--200 Area Savannah River Site: Separations Area operations Building 211-H Outside Facilities. Supplement 11, Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    1993-01-01

    The H-Area Outside Facilities are located in the 200-H Separations Area and are comprised of a number of processes, utilities, and services that support the separations function. Included are enriched uranium loadout, bulk chemical storage, water handling, acid recovery, general purpose evaporation, and segregated solvent facilities. In addition, services for water, electricity, and steam are provided. This Safety Analysis Report (SAR) documents an analysis of the H-Area Outside Facilities and is one of a series of documents for the Separations Area as specified in the SR Implementation Plan for DOE order 5481.1A. The primary purpose of the analysis was to demonstrate that the facility can be operated without undue risk to onsite or offsite populations, to the environment, and to operating personnel. In this report, risks are defined as the expected frequencies of accidents, multiplied by the resulting radiological consequences in person-rem. Following the summary description of facility and operations is the site evaluation including the unique features of the H-Area Outside Facilities. The facility and process design are described in Chapter 3.0 and a description of operations and their impact is given in Chapter 4.0. The accident analysis in Chapter 5.0 is followed by a list of safety related structures and systems (Chapter 6.0) and a description of the Quality Assurance program (Chapter 7.0). The accident analysis in this report focuses on estimating the risk from accidents as a result of operation of the facilities. The operations were evaluated on the basis of three considerations: potential radiological hazards, potential chemical toxicity hazards, and potential conditions uniquely different from normal industrial practice.

  19. Safety analysis--200 Area Savannah River Site: Separations Area operations Building 211-H Outside Facilities. Supplement 11, Revision 1

    International Nuclear Information System (INIS)

    The H-Area Outside Facilities are located in the 200-H Separations Area and are comprised of a number of processes, utilities, and services that support the separations function. Included are enriched uranium loadout, bulk chemical storage, water handling, acid recovery, general purpose evaporation, and segregated solvent facilities. In addition, services for water, electricity, and steam are provided. This Safety Analysis Report (SAR) documents an analysis of the H-Area Outside Facilities and is one of a series of documents for the Separations Area as specified in the SR Implementation Plan for DOE order 5481.1A. The primary purpose of the analysis was to demonstrate that the facility can be operated without undue risk to onsite or offsite populations, to the environment, and to operating personnel. In this report, risks are defined as the expected frequencies of accidents, multiplied by the resulting radiological consequences in person-rem. Following the summary description of facility and operations is the site evaluation including the unique features of the H-Area Outside Facilities. The facility and process design are described in Chapter 3.0 and a description of operations and their impact is given in Chapter 4.0. The accident analysis in Chapter 5.0 is followed by a list of safety related structures and systems (Chapter 6.0) and a description of the Quality Assurance program (Chapter 7.0). The accident analysis in this report focuses on estimating the risk from accidents as a result of operation of the facilities. The operations were evaluated on the basis of three considerations: potential radiological hazards, potential chemical toxicity hazards, and potential conditions uniquely different from normal industrial practice

  20. Isolation facilities for highly infectious diseases in Europe--a cross-sectional analysis in 16 countries.

    Directory of Open Access Journals (Sweden)

    Stefan Schilling

    Full Text Available BACKGROUND: Highly Infectious Diseases (HIDs are (i easily transmissible form person to person; (ii cause a life-threatening illness with no or few treatment options; and (iii pose a threat for both personnel and the public. Hence, even suspected HID cases should be managed in specialised facilities minimizing infection risks but allowing state-of-the-art critical care. Consensus statements on the operational management of isolation facilities have been published recently. The study presented was set up to compare the operational management, resources, and technical equipment among European isolation facilities. Due to differences in geography, population density, and national response plans it was hypothesized that adherence to recommendations will vary. METHODS AND FINDINGS: Until mid of 2010 the European Network for Highly Infectious Diseases conducted a cross-sectional analysis of isolation facilities in Europe, recruiting 48 isolation facilities in 16 countries. Three checklists were disseminated, assessing 44 items and 148 specific questions. The median feedback rate for specific questions was 97.9% (n = 47/48 (range: n = 7/48 (14.6% to n = 48/48 (100%. Although all facilities enrolled were nominated specialised facilities' serving countries or regions, their design, equipment and personnel management varied. Eighteen facilities fulfilled the definition of a High Level Isolation Unit'. In contrast, 24 facilities could not operate independently from their co-located hospital, and five could not ensure access to equipment essential for infection control. Data presented are not representative for the EU in general, as only 16/27 (59.3% of all Member States agreed to participate. Another limitation of this study is the time elapsed between data collection and publication; e.g. in Germany one additional facility opened in the meantime. CONCLUSION: There are disparities both within and between European countries regarding the design

  1. Interactive Parallel Data Analysis within Data-Centric Cluster Facilities using the IPython Notebook

    Science.gov (United States)

    Pascoe, S.; Lansdowne, J.; Iwi, A.; Stephens, A.; Kershaw, P.

    2012-12-01

    The data deluge is making traditional analysis workflows for many researchers obsolete. Support for parallelism within popular tools such as matlab, IDL and NCO is not well developed and rarely used. However parallelism is necessary for processing modern data volumes on a timescale conducive to curiosity-driven analysis. Furthermore, for peta-scale datasets such as the CMIP5 archive, it is no longer practical to bring an entire dataset to a researcher's workstation for analysis, or even to their institutional cluster. Therefore, there is an increasing need to develop new analysis platforms which both enable processing at the point of data storage and which provides parallelism. Such an environment should, where possible, maintain the convenience and familiarity of our current analysis environments to encourage curiosity-driven research. We describe how we are combining the interactive python shell (IPython) with our JASMIN data-cluster infrastructure. IPython has been specifically designed to bridge the gap between the HPC-style parallel workflows and the opportunistic curiosity-driven analysis usually carried out using domain specific languages and scriptable tools. IPython offers a web-based interactive environment, the IPython notebook, and a cluster engine for parallelism all underpinned by the well-respected Python/Scipy scientific programming stack. JASMIN is designed to support the data analysis requirements of the UK and European climate and earth system modeling community. JASMIN, with its sister facility CEMS focusing the earth observation community, has 4.5 PB of fast parallel disk storage alongside over 370 computing cores provide local computation. Through the IPython interface to JASMIN, users can make efficient use of JASMIN's multi-core virtual machines to perform interactive analysis on all cores simultaneously or can configure IPython clusters across multiple VMs. Larger-scale clusters can be provisioned through JASMIN's batch scheduling system

  2. Thermal-hydraulic analysis of an intermediate LOCA test at the ROSA facility including uncertainty evaluation

    International Nuclear Information System (INIS)

    Highlights: ► Pre and post test calculations of an IBLOCA test at the ROSA facility are presented. ► Both analyses included an evaluation of the uncertainties. ► The differences between the two uncertainty evaluations are analysed. ► The article highlights the impact of the base case on the final uncertainty band. - Abstract: The goal of uncertainty analyses is to provide best-estimate simulations with uncertainty bands, which take into account uncertainties in the code modeling capabilities as well as uncertainties in the initial and boundary conditions of a given transient scenario. In the present paper, the experience acquired at the Paul Scherrer Institut (PSI) through participations to previous international programs (among these the OECD/NEA BEMUSE program) is used to evaluate a blind calculation of the ROSA-2 Test 1. The OECD/NEA ROSA-2 project aims at addressing thermal-hydraulic safety issues relevant for light water reactors by building up an experimental database at the ROSA Large Scale Test Facility (LSTF). The ROSA facility simulates a PWR Westinghouse design with a four-loop configuration and a power of 3423 MWth. Test 1 of the ROSA-2 program consists of an intermediate break located in one of the hot legs, in particular it represents the rupture of the pressurizer surge line. Using a TRACE model, previously validated against experiments of the ROSA-1 programme, namely small break LOCA Tests 6-1 and 6-2, a blind case calculation was performed for Test 1/ROSA-2. An uncertainty analysis was carried out together with the simulation of Test 1, in order to provide uncertainty bands for each time trend and finally determine whether the TRACE simulation is able to capture the experimental results within the uncertainty bands. Since the uncertainty bands did not envelop the experimental data, a post-test analysis was carried out. The post-test analysis was helpful in determining which relevant physical phenomena had not been included in the pre

  3. Analysis of umayyad islamic silver coins (Dirhams) by using instrumental neutron activation analysis

    Institute of Scientific and Technical Information of China (English)

    1999-01-01

    Islamic silver coins (Dirhams) running the period between 107 to 126 Hijri (726-743AD), which belong to the Umayyad Empire period, 41-132 hijri (661-750AD), were selected for analysis by using instrumentalneutron activation analysis techniques.During this period (105-126H),(724-743AD), the Caliph Hisham Eben Abdlemalek ruled the Umayyad Empire.Dirhams were irradiated in a reactor neutron activation facility.Levels of various elements viz.Cu, Ag and Au were estimated.It was found that the average silver concentration, the baseconstituent of the Dirham, was about 88wt%.Correlation between thecomposition of Dirhams and the historical implications was discussed.

  4. Risk assessment and optimization (ALARA) analysis for the environmental remediation of Brookhaven National Laboratory's hazardous waste management facility

    International Nuclear Information System (INIS)

    The Department of Energy's (DOE) Office of Environment, Safety, and Health (EH) sought examples of risk-based approaches to environmental restoration to include in their guidance for DOE nuclear facilities. Extensive measurements of radiological contamination in soil and ground water have been made at Brookhaven National Laboratory's Hazardous Waste Management Facility (HWMF) as part of a Comprehensive Environmental Response, Compensation and Liability Act (CERCLA) remediation process. This provided an ideal opportunity for a case study. This report provides a risk assessment and an open-quotes As Low as Reasonably Achievableclose quotes (ALARA) analysis for use at other DOE nuclear facilities as an example of a risk-based decision technique

  5. Annual report to Congress: Department of Energy activities relating to the Defense Nuclear Facilities Safety Board, calendar year 1998

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-02-01

    This is the ninth Annual Report to the Congress describing Department of Energy (Department) activities in response to formal recommendations and other interactions with the Defense Nuclear Facilities Safety Board (Board). The Board, an independent executive-branch agency established in 1988, provides advice and recommendations to the Secretary of energy regarding public health and safety issues at the Department`s defense nuclear facilities. The Board also reviews and evaluates the content and implementation of health and safety standards, as well as other requirements, relating to the design, construction, operation, and decommissioning of the Department`s defense nuclear facilities. The locations of the major Department facilities are provided. During 1998, Departmental activities resulted in the proposed closure of one Board recommendation. In addition, the Department has completed all implementation plan milestones associated with four other Board recommendations. Two new Board recommendations were received and accepted by the Department in 1998, and two new implementation plans are being developed to address these recommendations. The Department has also made significant progress with a number of broad-based initiatives to improve safety. These include expanded implementation of integrated safety management at field sites, a renewed effort to increase the technical capabilities of the federal workforce, and a revised plan for stabilizing excess nuclear materials to achieve significant risk reduction.

  6. Human hair neutron activation analysis: analysis on population level, mapping

    International Nuclear Information System (INIS)

    Neutron activation analysis is an outstanding analytical method having very wide applications in various fields. Analysis of human hair within last decades mostly based on neutron activation analysis is a very attractive illustration of the application of nuclear analytical techniques. Very interesting question is how the elemental composition differs in different areas or cities. In this connection the present paper gives average data and maps of various localities in the vicinity of drying-out Aral Sea and of various industrial cities in Central Asia. (author)

  7. Sampling and analysis of radioactive liquid wastes and sludges in the Melton Valley and evaporator facility storage tanks at ORNL

    Energy Technology Data Exchange (ETDEWEB)

    Sears, M.B.; Botts, J.L.; Ceo, R.N.; Ferrada, J.J.; Griest, W.H.; Keller, J.M.; Schenley, R.L.

    1990-09-01

    The sampling and analysis of the radioactive liquid wastes and sludges in the Melton Valley Storage Tanks (MVSTs), as well as two of the evaporator service facility storage tanks at ORNL, are described. Aqueous samples of the supernatant liquid and composite samples of the sludges were analyzed for major constituents, radionuclides, total organic carbon, and metals listed as hazardous under the Resource Conservation and Recovery Act (RCRA). Liquid samples from five tanks and sludge samples from three tanks were analyzed for organic compounds on the Environmental Protection Agency (EPA) Target Compound List. Estimates were made of the inventory of liquid and sludge phases in the tanks. Descriptions of the sampling and analytical activities and tabulations of the results are included. The report provides data in support of the design of the proposed Waste Handling and Packaging Plant, the Liquid Low-Level Waste Solidification Project, and research and development activities (R D) activities in developing waste management alternatives. 7 refs., 8 figs., 16 tabs.

  8. Use of a Graded Approach in the Application of the Management System Requirements for Facilities and Activities

    International Nuclear Information System (INIS)

    IAEA Safety Standards Series No. GS-R-3, The Management System for Facilities and Activities, defines the requirements for establishing, implementing, assessing and continually improving a management system that integrates safety, health, environmental, security, quality and economical elements. It details the need to grade the application of the management system requirements to ensure that resources are deployed and appropriate controls are applied on the basis of the consideration of: the significance and complexity of each product or activity; the hazards and the magnitude of the potential impact (risks) associated with the safety, health, environmental, security, quality and economical elements of each product or activity; and the possible consequences if a product fails or an activity is carried out incorrectly. The grading of the application of the requirements detailed in IAEA Safety Standards Series No. GS-R-3 is especially essential when they are implemented in smaller facilities and activities. The grading is done to ensure that the management system for smaller facilities and activities are suitably tailored to the hazards and the magnitude of the potential impact of the facilities and activities. Detailed guidance on how the grading requirements of IAEA Safety Standards Series No. GS-R-3 can be met and how to ensure that grading is performed in a consistent manner can be found in IAEA Safety Standards Series No. GS-G-3.1, Application of the Management System for Facilities and Activities. In addition, it contains guidance on systematic grading methods which will reduce the likelihood and consequences of improper grading. This publication provides an overview of grading fundamentals, the grading process, the role of classification in the process and the typical controls that can be graded. It also provides practical guidance and examples of grading as required by IAEA Safety Standards Series No. GS-R-3 to develop and apply a method of grading

  9. Neutron activation spectrometry and neutron activation analysis in analytical geochemistry

    International Nuclear Information System (INIS)

    The present report is to show the geochemists who are interested in neutron activation spectrometry (NAS) and neutron activation analysis (NAA) which analytical possibilities these methods offer him. As a review of these analytical possibilities, a lieterature compolation is given which is subdivided into two groups: 1) rock (basic, intermediary, acid, sediments, soils and nuds, diverse minerals, tectites, meteorites and lunar material). 2) ore (Al, Au, Be, Cr, Cu, Mn, Mo, Fe, Pb, Pt, Sn, Ti, W, Zn, Zr, U and phosphate ore, polymetallic ores, fluorite, monazite and diverse ores). The applied methods as well as the determinable elements in the given materials can be got from the tables. On the whole, the literature evaluation carried out makes it clear that neutron activation spectrometry is a very useful multi-element method for the analysis of rocks. The analysis of ores, however, is subjected to great limitations. As rock analysis is very frequently of importance in prospecting for ore deposits, the NAS proves to be extremely useful for this very field of application. (orig./LH)

  10. Loss of coolant accident analysis and evolution of emergency core cooling system for an inpile irradiation facility

    International Nuclear Information System (INIS)

    This paper deals with the Loss of Coolant Accident (LOCA) analysis of an inpile facility using RELAP4/MOD6 computer code. The present study is the culmination of a three part LOCA analysis done earlier by the authors. Blowdown analysis had been extended to include reflood part of the transient. Based on the analysis an Emergency Core Cooling System (ECCS) has been evolved. (author). 5 figs., 2 tabs

  11. Application of FEPs analysis to identify research priorities relevant to the safety case for an Australian radioactive waste facility

    International Nuclear Information System (INIS)

    The Australian Nuclear Science and Technology Organisation (ANSTO) has established a project to undertake research relevant to the safety case for the proposed Australian radioactive waste facility. This facility will comprise a store for intermediate level radioactive waste, and either a store or a near-surface repository for low-level waste. In order to identify the research priorities for this project, a structured analysis of the features, events and processes (FEPs) relevant to the performance of the facility was undertaken. This analysis was based on the list of 137 FEPs developed by the IAEA project on 'Safety Assessment Methodologies for Near Surface Disposal Facilities' (ISAM). A number of key research issues were identified, and some factors which differ in significance for the store, compared to the repository concept, were highlighted. For example, FEPs related to long-term groundwater transport of radionuclides are considered to be of less significance for a store than a repository. On the other hand, structural damage from severe weather, accident or human interference is more likely for a store. The FEPs analysis has enabled the scientific research skills required for the inter-disciplinary project team to be specified. The outcomes of the research will eventually be utilised in developing the design, and assessing the performance, of the future facility. It is anticipated that a more detailed application of the FEPs methodology will be undertaken to develop the safety case for the proposed radioactive waste management facility. (authors)

  12. Neutron activation analysis (NAA), radioisotope production via neutron activation (PNA) and fission product gas-jet (GJA)

    Energy Technology Data Exchange (ETDEWEB)

    Gaeggeler, H.W. [Paul Scherrer Inst. (PSI), Villigen (Switzerland)

    1996-11-01

    Three different non-diffractive applications of neutrons are outlined, neutron activation analysis, production of radionuclides, mostly for medical applications, and production of short-lived fission nuclides with a so-called gas-jet. It is shown that all three devices may be incorporated into one single insert at SINQ due to their different requests with respect to thermal neutron flux. Some applications of these three facilities are summarized. (author) 3 figs., 1 tab., 8 refs.

  13. Analysis of 2015 Meteorological Data from the Knolls Atomic Power Laboratory and Kesselring Site Operations Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Aluzzi, F. J. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

    2016-02-19

    Both the Knolls Atomic Power Laboratory (KAPL) in Schenectady, N.Y. and the Kesselring Site Operations (KSO) facility near Ballston Spa, N.Y. are required to estimate the effects of hypothetical emissions of radiological material from their respective facilities by the U.S. Environmental Protection Agency (EPA), which regulates both sites. An atmospheric dispersion model known as CAP88, which was developed and approved by the EPA for such purposes, is used by KAPL and KSO to meet this requirement. CAP88 calculations over a given time period are based on statistical data on the meteorological conditions for that period. Both KAPL and KSO have on-site meteorological towers which take atmospheric measurements at a frequency ideal for EPA regulatory model input. However, an independent analysis and processing of the meteorological data from each tower is required to derive a data set appropriate for use in the CAP88 model. The National Atmospheric Release Advisory Center (NARAC) was contracted to process the meteorological tower data for the 2015 calendar year from both on-site meteorological towers.

  14. Analysis of 2014 Meteorological Data from the Knolls Atomic Power Laboratory and Kesselring Site Operations Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Aluzzi, Fernando J. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

    2015-02-25

    Both the Knolls Atomic Power Laboratory (KAPL) in Schenectady, N.Y. and the Kesselring Site Operations (KSO) facility near Ballston Spa, N.Y. are required to estimate the effects of hypothetical emissions of radiological material from their respective facilities by the U.S. Environmental Protection Agency (EPA), which regulates both sites. An atmospheric dispersion model known as CAP88, which was developed and approved by the EPA for such purposes, is used by KAPL and KSO to meet this requirement. CAP88 calculations over a given time period are based on statistical data on the meteorological conditions for that period. Both KAPL and KSO have on-site meteorological towers which take atmospheric measurements at a frequency ideal for EPA regulatory model input. However, an independent analysis and processing of the meteorological data from each tower is required to derive a data set appropriate for use in the CAP88 model. The National Atmospheric Release Advisory Center (NARAC) was contracted by KAPL to process the on-site data for the calendar year 2014.

  15. Facile heterocyclic synthesis and antimicrobial activity of polysubstituted and condensed pyrazolopyranopyrimidine and pyrazolopyranotriazine derivatives

    Directory of Open Access Journals (Sweden)

    Hafez Hend N.

    2015-12-01

    Full Text Available Reaction of 6-amino-3-methyl-4-(substituted phenyl-1,4- dihydropyrano[2,3-c]pyrazole-5-carbonitrile (1 with triethylorthoformate followed by treatment with hydrazine hydrate, formic acid, acetic acid, phenylisocyanate, ammonium thiocyanate and formamide afforded the corresponding pyranopyrimidine derivatives 2-6. Cyclocondensation of 1 with cyclohexanone afforded pyrazolopyranoquinoline 7. One-pot process of diazotation and de-diazochlorination of 1 afforded pyrazolopyranotriazine derivative 8, which upon treatment with secondary amines afforded 9 and 10a- c. Condensation of 2 with aromatic aldehyde gave the corresponding Schiff bases 11a,b, the oxidative cyclization of the hydrazone with appropriate oxidant afforded 11-(4- fluorophenyl- 2-(4-substituted phenyl-10-methyl-8,11-dihydropyrazolo-[ 4’,3’:5,6]pyrano[3,2-e][1,2,4]triazolo[1,5-c]pyrimidines (12a,b. Structures of the synthesized compounds were confirmed by spectral data and elemental analysis. All synthesized compounds were evaluated for antibacterial and antifungal activities compared to norfloxacin and fluconazole as standard drugs. Compounds 9, 10c, 12a and 15 were found to be the most potent antibacterial agents, with activity equal to that of norfloxacin. On the other hand, compound 5 exhibited higher antifungal activity compared to fluconazole.

  16. Operational safety analysis of the Olkiluoto encapsulation plant and disposal facility; Olkiluodon kapselointi- ja loppusijoituslaitoksen kaeyttoeturvallisuusanalyysi

    Energy Technology Data Exchange (ETDEWEB)

    Rossi, J.; Suolanen, V. [VTT Technical Research Centre of Finland, Espoo (Finland)

    2012-11-15

    Radiation doses for workers of the facility, for inhabitants in the environment and for terrestrial ecosystem possibly caused by the encapsulation and disposal facilities to be built at Olkiluoto during its operation were considered in the study. The study covers both the normal operation of the plant and some hypothetical incidents and accidents. Release through the ventilation stack is assumed to be filtered both in normal operation and in hypothetical abnormal fault and accident cases. In addition the results for unfiltered releases are also presented. This research is limited to the deterministic analysis. During about 30 operation years of our four nuclear power plant units there have been found 58 broken fuel pins. Roughly estimating there has been one fuel leakage per year in a facility (includes two units). Based on this and adopting a conservative approach, it is estimated that one fuel pin per year could leak in normal operation during encapsulation process. The release magnitude in incidents and accidents is based on the event chains, which lead to loss of fuel pin tightness followed by a discharge of radionuclides into the handling space and to some degree to the atmosphere through the ventilation stack equipped with redundant filters. The most exposed group of inhabitants is conservatively assumed to live at the distance of 200 meters from the encapsulation and disposal plant and it will receive the largest doses in most dispersion conditions. The dose value to a member of the most exposed group was calculated on the basis of the weather data in such a way that greater dose than obtained here is caused only in 0.5 percent of dispersion conditions. The results obtained indicate that during normal operation the doses to workers remain small and the dose to the member of the most exposed group is less than 0.001 mSv per year. In the case of hypothetical fault and accident releases the offsite doses do not exceed either the limit values set by the safety

  17. Activation analysis of air particulate matter

    International Nuclear Information System (INIS)

    This review on activation analysis of air particulate matter is an extended and updated version of a review given by the same authors in 1985. The main part is aimed at the analytical scheme and refers to rules and techniques for sampling, sample and standard preparation, irradiation and counting procedures, as well as data processing, - evaluation, and - presentation. Additional chapters deal with relative and monostandard methods, the use of activation analysis for atmosphere samples in various localities, and level of toxic and other elements in the atmosphere. The review contains 190 references. (RB)

  18. Design of Neutron Activation Analysis Laboratorium Room

    International Nuclear Information System (INIS)

    Base on the planning to increase of the research and service quality in the ''Neutron activation analysis'' (APN),the design of mentioned ''Neutron activation analysis laboratories room'' has been done in the multi purpose reactor G.A. Siwabessy. By the using the designed installation, the irradiation preparation and counting sample can be done. The design doing by determination of installation lay out and maximum particle contain in the air. The design installation required a unit of 1 HP blower, a unit of 1 HP split air condition and 2 units 1200 x 800 mm HEPA filter. This paper concluded that this design is feasible to fabricated

  19. Data Analysis Software Tools for Enhanced Collaboration at the DIII-D National Fusion Facility

    International Nuclear Information System (INIS)

    Data analysis at the DIII-D National Fusion Facility is simplified by the use of two software packages in analysis codes. The first is GAP1otObj, an IDL-based object-oriented library used in visualization tools for dynamic plotting. GAPlotObj gives users the ability to manipulate graphs directly through mouse and keyboard-driven commands. The second software package is MDSplus, which is used at DIED as a central repository for analyzed data. GAPlotObj and MDSplus reduce the effort required for a collaborator to become familiar with the DIII-D analysis environment by providing uniform interfaces for data display and retrieval. Two visualization tools at DIII-D that benefit from them are ReviewPlus and EFITviewer. ReviewPlus is capable of displaying interactive 2D and 3D graphs of raw, analyzed, and simulation code data. EFITviewer is used to display results from the EFIT analysis code together with kinetic profiles and machine geometry. Both bring new possibilities for data exploration to the user, and are able to plot data from any fusion research site with an MDSplus data server

  20. Enhanced Computational Infrastructure for Data Analysis at the DIII-D National Fusion Facility

    International Nuclear Information System (INIS)

    Recently a number of enhancements to the computer hardware infrastructure have been implemented at the DIII-D National Fusion Facility. Utilizing these improvements to the hardware infrastructure, software enhancements are focusing on streamlined analysis, automation, and graphical user interface (GUI) systems to enlarge the user base. The adoption of the load balancing software package LSF Suite by Platform Computing has dramatically increased the availability of CPU cycles and the efficiency of their use. Streamlined analysis has been aided by the adoption of the MDSplus system to provide a unified interface to analyzed DIII-D data. The majority of MDSplus data is made available in between pulses giving the researcher critical information before setting up the next pulse. Work on data viewing and analysis tools focuses on efficient GUI design with object-oriented programming (OOP) for maximum code flexibility. Work to enhance the computational infrastructure at DIII-D has included a significant effort to aid the remote collaborator since the DIII-D National Team consists of scientists from 9 national laboratories, 19 foreign laboratories, 16 universities, and 5 industrial partnerships. As a result of this work, DIII-D data is available on a 24 x 7 basis from a set of viewing and analysis tools that can be run either on the collaborators' or DIII-Ds computer systems. Additionally, a Web based data and code documentation system has been created to aid the novice and expert user alike

  1. Inelastic analysis of two pipelines in the Fast Flux Test Facility

    International Nuclear Information System (INIS)

    Several complex pipelines of the Fast Flux Test Facility (FFTF) were evaluated using detailed inelastic analysis because they did not satisfactorily comply with the ASME elastic analysis rules. The purpose of the inelastic analysis is to demonstrate that the piping systems, which operate at elevated temperatures, comly with ASME Code requirements under the loading conditions specified in the Design Specification of each pipeline, using inelastic analysis rules. Two pipelines are discussed, the 8-inch Secondary Hot Leg in the Heat Transport System and the 3-inch/4-inch Primary Hot Leg (Ex-module) in the Closed Loop System. The former is made from type 304SS, operating at 9650F (518.30C) and designed for a 20 year life; the latter is made from type 316SS, operating at 12000F (648.90C) and designed for a 10 year life. The MARC general finite element computer program was utilized in the analyses. The pipelines were idealized using the combinations of thin-walled circular closed section beam elements and constant bending 3-node elbow elements. Discussions on the load histograms used, the inelastic strain accumulated, and the effects of creep and fatigue on the lines are given

  2. Enhanced Computational Infrastructure for Data Analysis at the DIII-D National Fusion Facility

    Energy Technology Data Exchange (ETDEWEB)

    Schissel, D.P.; Peng, Q.; Schachter, J.; Terpstra, T.B.; Casper, T.A.; Freeman, J.; Jong, R.; Keith, K.M.; Meyer, W.H.; Parker, C.T.

    1999-08-01

    Recently a number of enhancements to the computer hardware infrastructure have been implemented at the DIII-D National Fusion Facility. Utilizing these improvements to the hardware infrastructure, software enhancements are focusing on streamlined analysis, automation, and graphical user interface (GUI) systems to enlarge the user base. The adoption of the load balancing software package LSF Suite by Platform Computing has dramatically increased the availability of CPU cycles and the efficiency of their use. Streamlined analysis has been aided by the adoption of the MDSplus system to provide a unified interface to analyzed DIII-D data. The majority of MDSplus data is made available in between pulses giving the researcher critical information before setting up the next pulse. Work on data viewing and analysis tools focuses on efficient GUI design with object-oriented programming (OOP) for maximum code flexibility. Work to enhance the computational infrastructure at DIII-D has included a significant effort to aid the remote collaborator since the DIII-D National Team consists of scientists from 9 national laboratories, 19 foreign laboratories, 16 universities, and 5 industrial partnerships. As a result of this work, DIII-D data is available on a 24 x 7 basis from a set of viewing and analysis tools that can be run either on the collaborators' or DIII-Ds computer systems. Additionally, a Web based data and code documentation system has been created to aid the novice and expert user alike.

  3. Facile synthesis of Bi2WO6/Bi2O3-loaded polyurethane sponge with enhanced visible light photocatalytic activity

    Science.gov (United States)

    Zhang, Fengjun; Wang, Zhi; Wang, Tianye; Jia, Liwei; Wang, Chao; Zhang, Shengyu

    2016-03-01

    In this study, Bi2WO6/Bi2O3-loaded polyurethane sponge composite photocatalyst was successfully synthesized via a facile two-step approach. The composite was characterized by X-ray diffraction, ultraviolet-visible diffuse reflectance, and scanning electron microscopy. The Bi2WO6/Bi2O3 photocatalyst was successfully loaded on polyurethane sponge and the composite displayed enhanced absorption in the ultraviolet-to-visible light region. Furthermore, the composite exhibited enhanced photocatalytic activity and reusability towards the degradation of rhodamine B (RhB) under visible light. This work demonstrates a facile method for synthesizing Bi2WO6/Bi2O3-loaded polyurethane sponge with enhanced photocatalytic activity and easy immobilization of the photocatalyst for application in environmental purification.

  4. Final report on passive and active low-frequency electromagnetic spectroscopy for airborne detection of underground facilities

    Energy Technology Data Exchange (ETDEWEB)

    SanFilipo, Bill

    2000-04-01

    The objective of this program is to perform research to advance the science in the application of both passive and active electromagnetic measurement techniques for the detection and spatial delineation of underground facilities. Passive techniques exploit the electromagnetic fields generated by electrical apparatus within the structure, including generators, motors, power distribution circuitry, as well as communications hardware and similar electronics equipment. Frequencies monitored are generally in the audio range (60-20,000 Hz), anticipating strong sources associated with normal AC power (i.e., 50 or 60 Hz and associated harmonics), and low frequency power from broad-band sources such as switching circuits. Measurements are made using receiver induction coils wired to electronics that digitize and record the voltage induced by the time varying magnetic fields. Active techniques employ electromagnetic field transmitters in the form of AC current carrying loops also in the audio frequency range, and receiving coils that measure the resultant time varying magnetic fields. These fields are perturbed from those expected in free space by any conductive material in the vicinity of the coils, including the ground, so that the total measured field is comprised of the primary free-space component and the secondary scattered component. The latter can be further delineated into an average background field (uniform conductive half-space earth) and anomalous field associated with heterogeneous zones in the earth, including both highly conductive objects such as metallic structures as well as highly resistive structures such as empty voids corresponding to rooms or tunnels. Work performed during Phase I included the development of the prototype GEM-2H instrumentation, collection of data at several test sites in the passive mode and a single site in the active mode, development of processing and interpretation software. The technical objectives of Phase II were to: (1

  5. Static Analysis of No.2 Vessel in Uranium Liquor Critical Facility

    Institute of Scientific and Technical Information of China (English)

    2008-01-01

    <正>In order to make it clear whether the No.2 vessel of the uranium liquor critical facility have enough intensity to endure the static loads or not and supply data for the general stress evaluation of the facility,

  6. 78 FR 3900 - Generic Drug User Fee-Active Pharmaceutical Ingredient and Finished Dosage Form Facility Fee...

    Science.gov (United States)

    2013-01-17

    ...The Food and Drug Administration (FDA) is announcing the rate for the generic drug active pharmaceutical ingredient (API) and finished dosage form (FDF) facilities user fees for fiscal year (FY) 2013. The Federal Food, Drug, and Cosmetic Act (the FD&C Act), as amended by the Generic Drug User Fee Amendments of 2012 (GDUFA), enacted the Food and Drug Administration Safety and Innovation Act, as......

  7. Transmutation of alloys in MFE facilities as calculated by REAC (a computer code system for activation and transmutation)

    International Nuclear Information System (INIS)

    A computer code system for fast calculation of activation and transmutation has been developed. The system consists of a driver code, cross-section libraries, flux libraries, a material library, and a decay library. The code is used to predict transmutations in a Ti-modified 316 stainless steel, a commercial ferritic alloy (HT9), and a V-15%Cr-5%Ti alloy in various magnetic fusion energy (MFE) test facilities and conceptual reactors

  8. Operation And Maintenance In Facilities Management Practices: A Gap Analysis In Malaysia

    OpenAIRE

    Zawawi Zuraihana Ahmad; Khalid Mohd Khazli Aswad; Ahmad Nur Azfahani; Zahari Nurul Fadzila; Agus Salim Nuzaihan Aras

    2016-01-01

    Facilities management in Malaysia has started as early as 1990s during the development of mega projects such as Putrajaya in 1999 [8, 9]. During this period, Malaysia was introduced to an integrated property management and maintenance services known as facilities management. However, its implementation according to the standard practice is still being disputed. The purpose of facilities management standard practices is to provide the facility management profession with a leading reference on ...

  9. Analysis of operational possibilities and conditions of remote handling systems in nuclear facilities

    International Nuclear Information System (INIS)

    Accepting the development of the occupational radiation exposure in nuclear facilities, it will be showing possibilities of cost effective reduction of the dose rate through the application of robots and manipulators for the maintenance of nuclear power plants, fuel reprocessing plants, decommissioning and dismantling of the mentioned plants. Based on the experiences about industrial robot applications by manufacturing and manipulator applications by the handling of radioactive materials as well as analysis of the handling procedures and estimation of the dose intensity, it will be defining task-orientated requirements for the conceptual design of the remote handling systems. Furthermore the manifold applications of stationary and mobil arranged handling systems in temporary or permanent operation are described. (orig.)

  10. Preliminary control system design and analysis for the Space Station Furnace Facility thermal control system

    Science.gov (United States)

    Jackson, M. E.

    1995-01-01

    This report presents the Space Station Furnace Facility (SSFF) thermal control system (TCS) preliminary control system design and analysis. The SSFF provides the necessary core systems to operate various materials processing furnaces. The TCS is defined as one of the core systems, and its function is to collect excess heat from furnaces and to provide precise cold temperature control of components and of certain furnace zones. Physical interconnection of parallel thermal control subsystems through a common pump implies the description of the TCS by coupled nonlinear differential equations in pressure and flow. This report formulates the system equations and develops the controllers that cause the interconnected subsystems to satisfy flow rate tracking requirements. Extensive digital simulation results are presented to show the flow rate tracking performance.

  11. Accident safety analysis for 300 Area N Reactor Fuel Fabrication and Storage Facility

    Energy Technology Data Exchange (ETDEWEB)

    Johnson, D.J.; Brehm, J.R.

    1994-01-01

    The purpose of the accident safety analysis is to identify and analyze a range of credible events, their cause and consequences, and to provide technical justification for the conclusion that uranium billets, fuel assemblies, uranium scrap, and chips and fines drums can be safely stored in the 300 Area N Reactor Fuel Fabrication and Storage Facility, the contaminated equipment, High-Efficiency Air Particulate filters, ductwork, stacks, sewers and sumps can be cleaned (decontaminated) and/or removed, the new concretion process in the 304 Building will be able to operate, without undue risk to the public, employees, or the environment, and limited fuel handling and packaging associated with removal of stored uranium is acceptable.

  12. Accident safety analysis for 300 Area N Reactor Fuel Fabrication and Storage Facility

    International Nuclear Information System (INIS)

    The purpose of the accident safety analysis is to identify and analyze a range of credible events, their cause and consequences, and to provide technical justification for the conclusion that uranium billets, fuel assemblies, uranium scrap, and chips and fines drums can be safely stored in the 300 Area N Reactor Fuel Fabrication and Storage Facility, the contaminated equipment, High-Efficiency Air Particulate filters, ductwork, stacks, sewers and sumps can be cleaned (decontaminated) and/or removed, the new concretion process in the 304 Building will be able to operate, without undue risk to the public, employees, or the environment, and limited fuel handling and packaging associated with removal of stored uranium is acceptable

  13. ANALYSIS OF ENERGY CONSUMPTION IN THE FACILITIES OF THE CIECHANÓW DAIRY COOPERATIVE

    Directory of Open Access Journals (Sweden)

    Marek Gugała

    2015-06-01

    Full Text Available The work presents the analysis of electric energy consumption in individual buildings of the Ciechanów Dairy Cooperative in 2011. The plant includes a cool storage facility, a boiler house, a compression room and CIP (Cleaning In Place stations. The plant manufactures liquid milk, cream, cheese, cottage cheese, cream cheese, butter and yoghurts. In 2011, the total electric energy consumption in the Cechanów Dairy Cooperative was 873114.0 kWh. The highest energy consumption (556430.0 kWh0 was recorded for the cooler (63.7% of total consumption and the lowest for CIP stations (33084.0 kWh. The average electric energy consumption in the Cooperative plant was 72759.5 kWh, the highest (104800.6 kWh in November and the lowest (40000.6 kWh in March.

  14. Cryogen system analysis for the Mirror Fusion Test Facility. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Parmley, R.T.; Hausman, R.F.; Naes, L.G.

    1979-06-01

    The Mirror Fusion Test Facility being designed and constructed at the Lawrence Livermore Laboratory requires a liquid helium liquefaction, storage, distribution, and recovery system and a liquid nitrogen storage and distribution system. To provide a powerful analytical tool to aid in the design evolution of this system through hardware, a thermodynamic fluid flow model was developed. This final report defines the cryogen system that was analyzed (consisting of the LHe subsystem, the GHe recovery subsystem and the LN/sub 2/ subsystem). It details the program assumptions, the theoretical basis for the analysis and limitations of the output. Several parametric runs were performed to illustrate the use of the program. Special detailed analyses were also performed on components such as the recuperator in the helium gas recovery system.

  15. Multiattribute utility analysis as a framework for public participation siting a hazardous waste facility

    Energy Technology Data Exchange (ETDEWEB)

    Merkhofer, M.W. [Applied Decision Analysis, Inc., Menlo Park, CA (United States); Conway, R. [Sandia National Labs., Albuquerque, NM (United States); Anderson, R.G. [Los Alamos National Lab., NM (United States)

    1996-05-01

    How can the public play a role in decisions involving complicated scientific arguments? This paper describes a public participation exercise in which stakeholders used multiattribute utility analysis to select a site for a hazardous waste facility. Key to success was the ability to separate and address the two types of judgements inherent in environmental decisions: technical judgements on the likely consequences of alternative choices and value judgements on the importance or seriousness of those consequences. This enabled technical specialists to communicate the essential technical considerations and allowed stakeholders to establish the value judgements for the decision. Although rarely used in public participation, the multiattribute utility approach appears to provide a useful framework for the collaborative resolution of many complex environmental decision problems.

  16. Quality assurance in biomedical neutron activation analysis

    International Nuclear Information System (INIS)

    The summary report represents an attempt to identify some of the possible sources of error in in vitro neutron activation analysis of trace elements applied to specimens of biomedical origin and to advise on practical means to avoid them. The report is intended as guidance for all involved in analysis, including sample collection and preparation for analysis. All these recommendations constitute part of quality assurance which is here taken to encompass the two concepts - quality control and quality assessment. Quality control is the mechanism established to control errors, while quality assessment is the mechanism used to verify that the analytical procedure is operating within acceptable limits

  17. Facile Synthesis of Heterocycles via 2-Picolinium Bromide and Antimicrobial Activities of the Products

    Directory of Open Access Journals (Sweden)

    Elham S. Darwish

    2008-05-01

    Full Text Available The 2-picolinium N-ylide 4, generated in situ from the N-acylmethyl-2-picolinium bromide 3, underwent cycloaddition to N-phenylmaleimide or carbon disulfideto give the corresponding cycloadducts 6 and 8, respectively similar reactions ofcompound 3 with some electron-deficient alkenes in the presence of MnO2 yielded theproducts 11 and 12. In addition, reaction of 4 with arylidene cyanothioacetamide andmalononitrile derivatives afforded the thiophene and aniline derivatives 15 and 17,respectively. Heating of picolinium bromide 3 with triethylamine in benzene furnished 2-(2-thienylindolizine (18. The structures of the isolated products were confirmed byelemental analysis as well as by 1H- and 13C-NMR, IR, and MS data. Both thestereochemistry and the regioselectivity of the studied reactions are discussed. Thebiological activity of the newly synthesized compounds was examined and showedpromising results.

  18. IFMIF (International Fusion Materials Irradiation Facility) conceptual design activity reduced cost report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-02-01

    This report describes the results of a preliminary reevaluation of the design and cost of the International Fusion Materials Irradiation Facility (IFMIF) Project in response to the request from the 28th FPCC meeting in January 1999. Two major ideas have been considered: 1) reduction of the total construction cost through elimination of the previously planned facility upgrade and 2) a facility deployment in 3 stages with capabilities for limited experiments in the first stage. As a result, the size and complexity of the facility could be significantly reduced, leading to substantial cost savings. In addition to these two ideas, this study also included a critical review of the original CDA specification with the objective of elimination of nonessential items. For example, the number of lithium targets was reduced from two to one. As a result of these changes in addition to the elimination of the upgrade, the total cost estimate was very substantially reduced from 797.2 MICF to 487.8 MICF, where 1 MICF = 1 Million of the IFMIF Conversion Units (approximately $1M US January, 1996). (author)

  19. Hazard screening of chemical releases and environmental equity analysis of populations proximate to toxic release inventory facilities in Oregon.

    Science.gov (United States)

    Neumann, C M; Forman, D L; Rothlein, J E

    1998-04-01

    A comprehensive approach using hazard screening, demographic analysis, and a geographic information system (GIS) for mapping is employed to address environmental equity issues in Oregon. A media-specific chronic toxicity index [or chronic index (CI)] was used to compare environmental chemical releases reported in the EPA's Toxic Chemical Release Inventory (TRI) database. In 1992, 254 facilities reportedly released more than 40 million pounds of toxic chemicals directly into the environment on-site or transferred them to sewage treatment plants or other off-site facilities for disposal and recycling. For each reported on-site TRI chemical release, a CI based on oral toxicity factors and total mass was calculated. CIs were aggregated on a media-, facility-, and chemical-specific basis. Glycol ethers, nickel, trichloroethylene, chloroform, and manganese were ranked as the top five chemicals released statewide based on total CI. In contrast, based on total mass, methanol, nickel, ammonia, acetone, and toluene were identified as the top five TRI chemicals released in Oregon. TRI facility rankings were related to the demographics and household income of surrounding neighborhoods using bivariate GIS mapping and statistical analysis. TRI facilities were disproportionately located in racial and ethnic minority neighborhoods. They were also located in areas with lower incomes compared to those in the surrounding county. No relationship was observed between the hazard ranking of the TRI facilities overall and socioeconomic characteristics of the community in which they were located.

  20. Prompt gamma-ray activation analysis (PGAA)

    Energy Technology Data Exchange (ETDEWEB)

    Kern, J. [Fribourg Univ. (Switzerland). Inst. de Physique

    1996-11-01

    The paper deals with a brief description of the principles of prompt gamma-ray activation analysis (PGAA), with the detection of gamma-rays, the PGAA project at SINQ and with the expected performances. 8 figs., 3 tabs., 10 refs.

  1. The Atomic Fingerprint: Neutron Activation Analysis

    Energy Technology Data Exchange (ETDEWEB)

    Keisch, Bernard [Carnegie-Mellon University

    1972-01-01

    The nuclei of atoms are stable only when they contain certain numbers of neutrons and protons. Since nuclei can absorb additional neutrons, which in many cases results in the conversion of a stable nucleus to a radioactive one, neutron activation analysis is possible.

  2. Isotopic neutron sources for neutron activation analysis

    International Nuclear Information System (INIS)

    This User's Manual is an attempt to provide for teaching and training purposes, a series of well thought out demonstrative experiments in neutron activation analysis based on the utilization of an isotopic neutron source. In some cases, these ideas can be applied to solve practical analytical problems. 19 refs, figs and tabs

  3. Transforming Teacher Education, An Activity Theory Analysis

    Science.gov (United States)

    McNicholl, Jane; Blake, Allan

    2013-01-01

    This paper explores the work of teacher education in England and Scotland. It seeks to locate this work within conflicting sociocultural views of professional practice and academic work. Drawing on an activity theory framework that integrates the analysis of these seemingly contradictory discourses with a study of teacher educators' practical…

  4. SPECIAL ANALYSIS AIR PATHWAY MODELING OF E-AREA LOW-LEVEL WASTE FACILITY

    Energy Technology Data Exchange (ETDEWEB)

    Hiergesell, R.; Taylor, G.

    2011-08-30

    This Special Analysis (SA) was initiated to address a concern expressed by the Department of Energy's Low Level Waste Disposal Facility Federal Review Group (LFRG) Review Team during their review of the 2008 E-Area Performance Assessment (PA) (WSRC, 2008). Their concern was the potential for overlapping of atmospheric plumes, emanating from the soil surface above SRS LLW disposal facilities within the E-Area, to contribute to the dose received by a member of the public during the Institutional Control (IC) period. The implication of this concern was that the dose to the maximally-exposed individual (MEI) located at the SRS boundary might be underestimated during this time interval. To address this concern a re-analysis of the atmospheric pathway releases from E-Area was required. In the process of developing a new atmospheric release model (ARM) capable of addressing the LFRG plume overlap concern, it became obvious that new and better atmospheric pathway disposal limits should be developed for each of the E-Area disposal facilities using the new ARM. The scope of the SA was therefore expanded to include the generation of these new limits. The initial work conducted in this SA was to develop a new ARM using the GoldSim{reg_sign} program (GTG, 2009). The model simulates the subsurface vapor diffusion of volatile radionuclides as they release from E-Area disposal facility waste zones and migrate to the land surface. In the process of this work, many new features, including several new physical and chemical transport mechanisms, were incorporated into the model. One of the most important improvements was to incorporate a mechanism to partition volatile contaminants across the water-air interface within the partially saturated pore space of the engineered and natural materials through which vapor phase transport occurs. A second mechanism that was equally important was to incorporate a maximum concentration of 1.9E-07 Ci/m{sup 3} of {sup 14}CO{sub 2} in the air

  5. The National Analysis Facility at DESY - status and use cases by the participating experiments

    International Nuclear Information System (INIS)

    The German National Analysis Facility (NAF) was set up at DESY, starting end of 2007 in the context of the Helmholtz Alliance 'Physics at the Terascale'. The NAF complements the DESY and the German Grid resources, and hence offers users from the German HEP institutes the best possible environment for data analysis. In the first part, the key aspects and components of the NAF are briefly presented with an emphasis on recent improvements. In the second part, the use cases of the three participating LHC experiments, ATLAS, CMS and LHCb, will be presented. Differences and commonalities in the usage of the NAF will be shown. Special emphasis will be placed on the usage of PROOF, whose usage on the NAF has been pioneered by CMS. It is now adapted by ATLAS. The third part will concentrate on how the NAF was used for detector optimisation studies in the preparation of one of the ILC Lol's (ILD 2009), as well as how CALICE uses the NAF for the analysis of their data taken in several test beam experiments performed for detector R and D. Finally, future developments of the NAF are presented.

  6. The National Analysis Facility at DESY - status and use cases by the participating experiments

    Science.gov (United States)

    Aplin, S.; Ehrenfeld, W.; Haupt, A.; Kemp, Y.; Langenbruch, C.; Leffhalm, K.; Lucaci-Timoce, A.; Stadie, H.

    2011-12-01

    The German National Analysis Facility (NAF) was set up at DESY, starting end of 2007 in the context of the Helmholtz Alliance "Physics at the Terascale". The NAF complements the DESY and the German Grid resources, and hence offers users from the German HEP institutes the best possible environment for data analysis. In the first part, the key aspects and components of the NAF are briefly presented with an emphasis on recent improvements. In the second part, the use cases of the three participating LHC experiments, ATLAS, CMS and LHCb, will be presented. Differences and commonalities in the usage of the NAF will be shown. Special emphasis will be placed on the usage of PROOF, whose usage on the NAF has been pioneered by CMS. It is now adapted by ATLAS. The third part will concentrate on how the NAF was used for detector optimisation studies in the preparation of one of the ILC Lol's (ILD 2009), as well as how CALICE uses the NAF for the analysis of their data taken in several test beam experiments performed for detector R & D. Finally, future developments of the NAF are presented.

  7. Microwave-assisted facile green synthesis of silver nanoparticles and spectroscopic investigation of the catalytic activity

    Indian Academy of Sciences (India)

    Siby Joseph; Beena Mathew

    2015-06-01

    Silver nanoparticles have been successfully synthesized in aqueous medium by a green, rapid and costefficient synthetic approach based on microwave irradiation. In this study, iota-carrageenan (I-carrageenan) is used both as reducing and stabilizing agent. The formation of nanoparticles is determined using UV–vis, Fourier transform infrared (FTIR), X-ray diffraction (XRD), energy-dispersive X-ray (EDX) and high-resolution-transmission electron microscopic (HR-TEM) analysis. Transmission electron microscopic (TEM) images show that the nanoparticles are of spherical shape with an average diameter of 18.2 nm. I-carrageenan-stabilized silver nanoparticles show outstanding catalytic activity for the reduction of 4-nitrophenol in the presence of NaBH4 in aqueous medium. The reaction follows pseudo-first-order kinetics and the reaction rate increases with the increase in amount of the catalyst. The study of the temperature dependence of reaction rate gives activation energy of 42.81 kJ mol−1. The synthesized silver nanoparticles are anticipated to be a promising material for pollution abatement.

  8. A survey of strippable and tie-down coatings for use in the decommissioning of alpha-active facilities

    International Nuclear Information System (INIS)

    The paper concerns temporary coatings for use in decommissioning operations of alpha-active facilities. The various temporary coating options are described with respect to: decontamination by removal of a previously applied protective coating, and the in-situ application of a coating for tie-down or decontamination duties. The specifications for coating systems to be used in active areas are defined in general terms. A survey of currently available temporary coating material is given, as well as the suitability of commercially available coating systems. (U.K.)

  9. Annual report to Congress: Department of Energy activities relating to the Defense Nuclear Facilities Safety Board, Calendar Year 1999

    International Nuclear Information System (INIS)

    This is the tenth Annual Report to the Congress describing Department of Energy activities in response to formal recommendations and other interactions with the Defense Nuclear Facilities Safety Board (Board). The Board, an independent executive-branch agency established in 1988, provides advice and recommendations to the Secretary of Energy regarding public health and safety issues at the Department's defense nuclear facilities. The Board also reviews and evaluates the content and implementation of health and safety standards, as well as other requirements, relating to the design, construction, operation, and decommissioning of the Department's defense nuclear facilities. During 1999, Departmental activities resulted in the closure of nine Board recommendations. In addition, the Department has completed all implementation plan milestones associated with three Board recommendations. One new Board recommendation was received and accepted by the Department in 1999, and a new implementation plan is being developed to address this recommendation. The Department has also made significant progress with a number of broad-based initiatives to improve safety. These include expanded implementation of integrated safety management at field sites, opening of a repository for long-term storage of transuranic wastes, and continued progress on stabilizing excess nuclear materials to achieve significant risk reduction

  10. Facile Synthesis of High {001} Facets Dominated BiOCl Nanosheets and Their Selective Dye-Sensitized Photocatalytic Activity Induced by Visible Light

    Directory of Open Access Journals (Sweden)

    Da Zhang

    2016-01-01

    Full Text Available Single-crystal BiOCl nanosheets, with high {001} facets exposed, were synthesized through a facile hydrolysis reaction under general atmospheric pressure, without adding any organic surfactant or agent. The thickness of the BiOCl nanosheets is about 20 nm, and the diameter is arranged from 200 to 400 nm. The structure of the BiOCl nanosheets was characterized by X-ray diffraction, energy disperse X-ray spectrum, transmission electron microscopy, and selective area electron diffraction. Moreover, three different dyes were used as model molecules to test the photocatalytic activity of BiOCl nanosheets under visible light. It was found that the BiOCl nanosheets possess selective photocatalytic behavior as their activity over RhB is much higher than that over MO or MB. Based on the analysis of the experimental results, the potential mechanism was discussed.

  11. Neutron activation analysis of Etruscan pottery

    International Nuclear Information System (INIS)

    Neutron activation analysis (NAA) has been widely used in archaeology for compositional analysis of pottery samples taken from sites of archaeological importance. Elemental profiles can determine the place of manufacture. At Cornell, samples from an Etruscan site near Siena, Italy, are being studied. The goal of this study is to compile a trace element concentration profile for a large number of samples. These profiles will be matched with an existing data bank in an attempt to understand the place of origin for these samples. The 500 kW TRIGA reactor at the Ward Laboratory is used to collect NAA data for these samples. Experiments were done to set a procedure for the neutron activation analysis with respect to sample preparation, selection of irradiation container, definition of activation and counting parameters and data reduction. Currently, we are able to analyze some 27 elements in samples of mass 500 mg with a single irradiation of 4 hours and two sequences of counting. Our sensitivity for many of the trace elements is better than 1 ppm by weight under the conditions chosen. In this talk, details of our procedure, including quality assurance as measured by NIST standard reference materials, will be discussed. In addition, preliminary results from data treatment using cluster analysis will be presented. (author)

  12. Boil-off experiments with the EIR-NEPTUN Facility: Analysis and code assessment overview report

    International Nuclear Information System (INIS)

    The NEPTUN data discussed in this report are from core uncovery (boil-off) experiments designed to investigate the mixture level decrease and the heat up of the fuel rod simulators above the mixture level for conditions simulating core boil-off for a nuclear reactor under small break loss-of-coolant accident conditions. The first series of experiments performed in the NEPTUN test facility consisted of ten boil-off (uncovery) and one adiabatic heat-up tests. In these tests three parameters were varied: rod power, system pressure and initial coolant subcooling. The NEPTUN experiments showed that the external surface thermocouples do not cause a significant cooling influence in the rods to which they are attached under boil-off conditions. The reflooding tests performed later on indicated that the external surface thermocouples have some effect during reflooding for NEPTUN electrically heated rod bundle. Peak cladding temperatures are reduced by about 30--40C and quench times occur 20--70 seconds earlier than rods with embedded thermocouples. Additionally, the external surface-thermocouples give readings up to 20 K lower than those obtained with internal surface thermocouples (in the absence of external thermocouples) in the peak cladding temperature zone. Some of the boil-off data obtained from the NEPTUN test facility are used for the assessment of the thermal-hydraulic transient computer codes. These calculations were performed extensively using the frozen version of TRAC-BD1/MOD1 (version 22). A limited number of assessment calculations were done with RELAP5/MOD2 (version 36.02). In this report the main results and conclusions of these calculations are presented with the identification of problem areas in relation to models relevant to boil-off phenomena. On the basis of further analysis and calculations done, changing some of the models such as the bubbly/slug flow interfacial friction correlation which eliminate some of the problems are recommended

  13. Boil-off experiments with the EIR-NEPTUN Facility: Analysis and code assessment overview report

    Energy Technology Data Exchange (ETDEWEB)

    Aksan, S.N.; Stierli, F.; Analytis, G.T. [Paul Scherrer Inst. (PSI), Villigen (Switzerland). Lab. for Thermal-Hydraulics

    1992-03-01

    The NEPTUN data discussed in this report are from core uncovery (boil-off) experiments designed to investigate the mixture level decrease and the heat up of the fuel rod simulators above the mixture level for conditions simulating core boil-off for a nuclear reactor under small break loss-of-coolant accident conditions. The first series of experiments performed in the NEPTUN test facility consisted of ten boil-off (uncovery) and one adiabatic heat-up tests. In these tests three parameters were varied: rod power, system pressure and initial coolant subcooling. The NEPTUN experiments showed that the external surface thermocouples do not cause a significant cooling influence in the rods to which they are attached under boil-off conditions. The reflooding tests performed later on indicated that the external surface thermocouples have some effect during reflooding for NEPTUN electrically heated rod bundle. Peak cladding temperatures are reduced by about 30--40C and quench times occur 20--70 seconds earlier than rods with embedded thermocouples. Additionally, the external surface-thermocouples give readings up to 20 K lower than those obtained with internal surface thermocouples (in the absence of external thermocouples) in the peak cladding temperature zone. Some of the boil-off data obtained from the NEPTUN test facility are used for the assessment of the thermal-hydraulic transient computer codes. These calculations were performed extensively using the frozen version of TRAC-BD1/MOD1 (version 22). A limited number of assessment calculations were done with RELAP5/MOD2 (version 36.02). In this report the main results and conclusions of these calculations are presented with the identification of problem areas in relation to models relevant to boil-off phenomena. On the basis of further analysis and calculations done, changing some of the models such as the bubbly/slug flow interfacial friction correlation which eliminate some of the problems are recommended.

  14. Analysis by neutron activation analysis a some ancient Dacian ceramics

    CERN Document Server

    Olariu, A

    1999-01-01

    Ancient Dacian ceramics, from three different establishments from Romanian territory have been analyzed by neutron activation analysis. A series of elements has been determined: Ba, Eu, K, La, Mn, Na, Sc, Sm. Ba is the element that could be considered to differentiate relatively the three groups of ceramics.

  15. Activity Analysis and Cost Analysis in Medical Schools.

    Science.gov (United States)

    Koehler, John E.; Slighton, Robert L.

    There is no unique answer to the question of what an ongoing program costs in medical schools. The estimates of program costs generated by classical methods of cost accounting are unsatisfactory because such accounting cannot deal with the joint production or joint cost problem. Activity analysis models aim at calculating the impact of alternative…

  16. Status of Activities to Implement a Sustainable System of MC&A Equipment and Methodological Support at Rosatom Facilities

    Energy Technology Data Exchange (ETDEWEB)

    J.D. Sanders

    2010-07-01

    Under the U.S.-Russian Material Protection, Control and Accounting (MPC&A) Program, the Material Control and Accounting Measurements (MCAM) Project has supported a joint U.S.-Russian effort to coordinate improvements of the Russian MC&A measurement system. These efforts have resulted in the development of a MC&A Equipment and Methodological Support (MEMS) Strategic Plan (SP), developed by the Russian MEM Working Group. The MEMS SP covers implementation of MC&A measurement equipment, as well as the development, attestation and implementation of measurement methodologies and reference materials at the facility and industry levels. This paper provides an overview of the activities conducted under the MEMS SP, as well as a status on current efforts to develop reference materials, implement destructive and nondestructive assay measurement methodologies, and implement sample exchange, scrap and holdup measurement programs across Russian nuclear facilities.

  17. Analysis through indicators of the management of radioactive waste in a radioactive facility

    International Nuclear Information System (INIS)

    The evaluation of the management of radioactive waste in the center of isotopes of the Republic of Cuba is the objective of this work. To do so, all the operations of the management system are evaluated through indicators used by this radioactive facility over a decade ago. Available information is processed from 1996 until 2012. The major waste generators are identified through the indicator of annual generation of each working group by local and by worker and it were analyzed the available store radioactive inventory, the relationship between the variation of annual technological waste volume of waste and the annual total manipulated activity, the relationship generation-declassification and the percent of liquid effluents managed as waste. Indicators of unconditional clearance, as well as the of the gaseous and liquid discharges are presented. It is concluded, with all these indicators, that it is possible to determine where are the causes of the behavior in the generation of radioactive waste if it is an increase of manipulated activity int the places of work or of worker, or improper application of the procedures of collection. It is controlled not only management, but also determines in which aspects can work to achieve the objective of minimizing the formation of these wastes, to be able to reduce the production costs. National shedding environmental regulations are met and the results are acceptable)

  18. Computational Analysis of Shock Layer Emission Measurements in an Arc-Jet Facility

    Science.gov (United States)

    Gokcen, Tahir; Park, Chung S.; Newfield, Mark E.; Fletcher, Douglas G.

    1998-01-01

    This paper reports computational analysis of radiation emission experiments in a high enthalpy arc-jet wind tunnel at NASA Ames Research Center. Recently, as part of ongoing arc-jet characterization work, spectroscopic radiation emission experiments have been conducted at the 20 MW NASA Ames arc-jet facility. The emission measurements were obtained from the arc-jet freestream and from a shock layer formed in front of flatfaced models. Analysis of these data is expected to provide valuable information about the thermodynamic state of the gas in the arc-jet freestream and in the shock layer as well as thermochemical equilibration processes behind the shock in arc-jet flows. Knowledge of the thermodynamic state of the gas in arc-jet test flows and especially within the shock layer is essential to interpret the heat transfer measurements such as in surface catalysis experiments. The present work is a continuation of previous work and focuses on analysis of the emission data obtained at relatively low-pressure conditions for which the arc-jet shock layer is expected to be in thermal and chemical nonequilibrium. Building blocks of the present computational analysis are: (1) simulation of nonequilibrium expanding flow in the converging-diverging conical nozzle and supersonic jet; (2) simulation of nonequilibrium shock layer formed in front of the flat-faced cylinder model; and (3) prediction of line-of-sight radiation from the computed flowfield. For computations of the nonequilibrium flow in the conical nozzle and shock layer, multi-temperature nonequilibrium codes with the axisymmetric formulation are used. For computations of line-of-sight radiation. a nonequilibrium radiation code (NEQAIR) is used to predict emission spectra from the computed flowfield. Computed line-of-sight averaged flow properties such as vibrational and rotational temperatures, species number densities within the shock layer will be compared with those deduced from the experimental spectra

  19. Notifiable work activities in water supply facilities - execution experience from Bavaria

    Energy Technology Data Exchange (ETDEWEB)

    Reifenhaeuser, C.; Koerner, S. [Bayerisches Landesamt fuer Umweltschutz, Augsburg (Germany)

    2008-05-15

    Since 2001, the protection against natural radiation is implemented in the German Radiation Protection Ordinance. Water supply facilities are now obliged to estimate the radon exposure of their staff. In 75 water supply facilities in Bavaria, Germany, radon exposures above the action limit of 6 mSv per year were determined. In these facilities the radon exposure has to be continuously monitored. By th proposal of the Bavarian Environment Agency (LfU), this should be done by continuous wearing of personal track-etch detectors, that are changed every three months. The results are sent to the LfU and reported to the central German dose register. Because of measuring periods of three months a high radon exposure that could probably exceed the annual limit of 20 mSv can be recognised at an early stage and immediate protection measures can be taken. In collaboration with the University of Regensburg remedial strategies for the permanent reduction of the radon exposure have been developed. (orig.)

  20. Notifiable work activities in water supply facilities - execution experience from Bavaria

    International Nuclear Information System (INIS)

    Since 2001, the protection against natural radiation is implemented in the German Radiation Protection Ordinance. Water supply facilities are now obliged to estimate the radon exposure of their staff. In 75 water supply facilities in Bavaria, Germany, radon exposures above the action limit of 6 mSv per year were determined. In these facilities the radon exposure has to be continuously monitored. By th proposal of the Bavarian Environment Agency (LfU), this should be done by continuous wearing of personal track-etch detectors, that are changed every three months. The results are sent to the LfU and reported to the central German dose register. Because of measuring periods of three months a high radon exposure that could probably exceed the annual limit of 20 mSv can be recognised at an early stage and immediate protection measures can be taken. In collaboration with the University of Regensburg remedial strategies for the permanent reduction of the radon exposure have been developed. (orig.)

  1. A Matric System Combining NPP facilities information and decommissioning activity information

    Energy Technology Data Exchange (ETDEWEB)

    Park, Hee Seong; Park, Seung Kook; Song, Chan Ho; Moon, Jei kwon [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2014-10-15

    D-D (Decontamination and Decommissioning) research divisions have experience in dismantling the uranium conversion plant and KRR-2 (Korean Research Reactor 2, TRIGA Mark type III) of 1998-2009. Using data obtained through the dismantled KRR-2, the divisions have studied how to dismantle a commercial nuclear power plant. There are lots of problems to apply directly dismantled data of the research reactor into the dismantling of a commercial reactor. The paper introduces a matrix system to manage a decommissioning project in preparing the dismantling of nuclear power plants as the first phase of solving the problems. The matrix, which is a system that combines the WBS code and the facility code of the nuclear power plant to be dismantled, has the decommissioning information of dismantling of the NPP. The matrix system has an important role in the evaluation of the amount of dismantling waste and decommissioning schedule and cost in conjunction with a database system that has been developed. To apply the information obtained from the dismantling of the KRR-2 into NPP dismantling, a matrix system has been devised. The matrix system is configured with data related to the dismantling of the ISDC information and WBS used during the dismantling of KRR-2 and the facilities information of the NPP. The code in the matrix system has all specifications of the facility and information about the device, as well as the unit operation obtained from the research reactors.

  2. Multiscale statistical analysis of coronal solar activity

    CERN Document Server

    Gamborino, Diana; Martinell, Julio J

    2016-01-01

    Multi-filter images from the solar corona are used to obtain temperature maps which are analyzed using techniques based on proper orthogonal decomposition (POD) in order to extract dynamical and structural information at various scales. Exploring active regions before and after a solar flare and comparing them with quiet regions we show that the multiscale behavior presents distinct statistical properties for each case that can be used to characterize the level of activity in a region. Information about the nature of heat transport is also be extracted from the analysis.

  3. The Influence of Urban Land-Use and Public Transport Facilities on Active Commuting in Wellington, New Zealand: Active Transport Forecasting Using the WILUTE Model

    Directory of Open Access Journals (Sweden)

    Joreintje Dingena Mackenbach

    2016-03-01

    Full Text Available Physical activity has numerous physical and mental health benefits, and active commuting (walking or cycling to work can help meet physical activity recommendations. This study investigated socioeconomic differences in active commuting, and assessed the impact of urban land-use and public transport policies on active commuting in the Wellington region in New Zealand. We combined data from the New Zealand Household Travel Survey and GIS data on land-use and public transport facilities with the Wellington Integrated Land-Use, Transportation and Environment (WILUTE model, and forecasted changes in active commuter trips associated with changes in the built environment. Results indicated high income individuals were more likely to commute actively than individuals on low income. Several land-use and transportation factors were associated with active commuting and results from the modelling showed a potential increase in active commuting following an increase in bus frequency and parking fees. In conclusion, regional level policies stimulating environmental factors that directly or indirectly affect active commuting may be a promising strategy to increase population level physical activity. Access to, and frequency of, public transport in the neighbourhood can act as a facilitator for a more active lifestyle among its residents without negatively affecting disadvantaged groups.

  4. Nondestructive gamma activation analysis of mineral materials

    International Nuclear Information System (INIS)

    The basic problems are described related to the use of gamma activation analysis. The applicability was studied of instrumental gamma activation analysis (IGAA) in geology. A number of minerals, rocks, marine sediments and reference materials were studied. For irradiation a betatron and a microtron were used. The results show that IGAA allows the simultaneous determination of a number of trace elements at concentrations of tenths of ppm. The results are given of comparisons made of the analytical possibilities of microtron IGAA and reactor INAA in geology. Tables show the results of the application of IGAA, the main products and parameters of photoexcitation reactions and graphically represented are the gamma spectra of measured materials. (J.B.)

  5. Facile solid state synthesis of ZnO hexagonal nanogranules with excellent photocatalytic activity

    Energy Technology Data Exchange (ETDEWEB)

    Pudukudy, Manoj, E-mail: manojpudukudy@gmail.com [Fuel Cell Institute, Universiti Kebangsaan Malaysia, Bangi 43600, Selangor (Malaysia); Department of Chemical and Process Engineering, Faculty of Engineering and Built Environment, Universiti Kebangsaan Malaysia, UKM, Bangi 43600, Selangor (Malaysia); Yaakob, Zahira, E-mail: zahirayaakob65@gmail.com [Department of Chemical and Process Engineering, Faculty of Engineering and Built Environment, Universiti Kebangsaan Malaysia, UKM, Bangi 43600, Selangor (Malaysia)

    2014-02-15

    In this article, ZnO nanogranules were synthesised rapidly by the thorough solid state mixing of nitrate precursor with citric acid followed by aging and calcination at two different temperatures of 400 °C and 600 °C. Here, citric acid played a superior role in the development of porous ZnO nanostructures. The ZnO nanogranules obtained in this way were characterised by different techniques. X-ray diffraction patterns indicated a hexagonal wurtzite structure of ZnO with high crystallinity and nanocrystalline size. Scanning and transmission electron microscopy images indicated the uniformly well separated hexagonal morphology of the ZnO nanoparticles, with granular shape. BET surface area-porosity analysis confirmed the presence of a mesoporous network in both samples, with high surface area and a monomodal pore size distribution. Room temperature Photoluminescence spectra of the samples exhibited characteristic blue and green emission bands in accordance with the calcination temperature. The photocatalytic performance of the ZnO nanogranules was studied using methylene blue degradation and found that the ZnO prepared at 400 °C exhibited higher photocatalytic activity due to its high surface area and more oxygen vacancies. High concentrations of several hazardous dye pollutants were effectively degraded, when the solution was passed over 50 mg of ZnO nanogranules under UV-light illumination.

  6. Elementary Analysis on the Technological Features of an Engineering Equipment Facile Diagnosis System

    Institute of Scientific and Technical Information of China (English)

    2001-01-01

    From the point of systemic engineering, the general properties of an engineering equipment fault diagnosis system and the studying object of diagnosis engineering were discussed. With the developing course of fault diagnosis technology, the relationship be-tween facile diagnosis system and diagnosis engineering were also discussed. The basic structure and feature of a facile diagnosis system were discussed, and the isomorphic of a facile diagnosis system and precise diagnosis system was presented. The facile diagnosis requires the perfection of method, pertinence and apriority of knowledge , adaptability of the object being diagnosed and the approach to the aim of the diagnosis result, as well as the outstanding of main functions.

  7. Ammonia and hydrogen sulfide emissions from swine production facilities in North America: a meta-analysis.

    Science.gov (United States)

    Liu, Z; Powers, W; Murphy, J; Maghirang, R

    2014-04-01

    Literature on NH3 and H2S emissions from swine production facilities in North America was reviewed, and a meta-analysis was conducted on measured emissions data from swine houses and manure storage facilities as well as concentration data in the vicinity of swine production facilities. Results from more than 80 studies were compiled with results from the 11 swine sites in the National Air Emissions Monitoring Study (NAEMS). Data across studies were analyzed statistically using the MIXED procedures of SAS. The median emission rates from swine houses across various production stages and manure handling systems were 2.78 and 0.09 kg/yr per pig for NH3 and H2S, respectively. The median emission rates from swine storage facilities were 2.08 and 0.20 kg/yr per pig for NH3 and H2S, respectively. The size of swine farm that may trigger the need to report NH3 emissions under the Emergency Planning and Community Right-to-Know Act (EPCRA) is 3,410 pigs on the basis of the median NH3 emission rate (4.86 kg/yr per pig), but the threshold can be as low as 992 pigs on the basis of the 90th-percentile emission rates (16.71 kg/yr per pig). Swine hoop houses had significantly higher NH3 emission rate (14.80 kg/yr per pig) than other manure-handling systems (P pig, P = 0.03). Farrowing houses had the highest H2S emission rate (2.50 kg/yr per pig), followed by gestation houses, and finishing houses had the lowest H2S emission rate (P < 0.01). Regression models for NH3 and H2S emission rates were developed for finishing houses with deep pits, recharge pits, and lagoons. The NH3 emission rates increased with increasing air temperature, but effects of air temperature on H2S emission rates were not significant. The recharge interval of manure pits significantly affected H2S but not NH3 emission rates. The H2S emission rates were also influenced by the size of the operation. Although NH3 and H2S concentrations at the edge of swine houses or lagoons were often higher than corresponding

  8. Reactor neutron activation analysis of industrial materials

    International Nuclear Information System (INIS)

    The specific application of neutron activation analysis (n.a.a.) for industrial materials is demonstrated by the determination of impurities in BeO, Al, Si, Cu, Ge, GaP, GaAs, steel, and irradiated uranium. A group scheme gives an orientation about the possibilities of n.a.a. The use of different standards, methods for the measurement of low radioactivities and errors caused by recoil reaction and radiation stimulated diffusion are discussed. (author)

  9. Mental Disorders among Adolescents in Juvenile Detention and Correctional Facilities: A Systematic Review and Metaregression Analysis of 25 Surveys

    Science.gov (United States)

    Fazel, Seena; Doll, Helen; Langstrom, Niklas

    2008-01-01

    The article presents a meta-analysis of all existing surveys on the prevalence of psychiatric morbidity in adolescents in juvenile detention and correctional facilities in order to assess the prevalence of mental disorders. Findings indicate adolescents in detention are 10 times more likely to suffer from psychosis than the general adolescent…

  10. Activation Analysis and Public Health. Survey Paper

    International Nuclear Information System (INIS)

    The technique of activation analysis has useful and distinctive applications, not yet fully recognized or exploited, in public health. Three areas of usefulness may be recognized. 1. Industrial hygiene. Activation analysis offers a simple and efficient method for assessing and controlling occupational hazards associated with the handling of toxic materials, such as compounds of arsenic and of mercury. Examination of hair and nail samples, taken at six-monthly intervals, will yield a surprising amount of information regarding the influence on occupational exposure of individual variation in working habits, and inadequacy or non-observance of hygienic rules and other prescribed safety measures. 2. Epidemiology. The advantage conferred by activation analysis lies in the possibility of rapid and accurate estimation of trace element concentrations in small samples of tissue or other materials, such as can readily be obtained from population groups large enough to be statistically significant. Surveys of this kind have interesting potentialities in relation to dental caries, cancer, cirrhosis of the liver and heart disease. 3. Recognition of essential trace elements. Surveys of trace element concentrations suggest that the variability of tissue levels among members of a population is smaller for essential trace elements than for non-essential elements. It is possible also that tissue levels show a normal distribution for essential elements and a log-normal distribution for non-essential elements. (author)

  11. Neutron Activation analysis of waste water

    International Nuclear Information System (INIS)

    An instrumental neutron activation analysis for the simultaneous determination of chlorine, bromine, sodium, manganese, cobalt, copper, chromium, zinc, nickel, antimony and iron in waste water is described. They were determined in waste water samples under normal conditions by non-destructive neutron activation simultaneously using a suitable monostandard method. Standardized water samples were used and irradiated in polyethylene ampoules at a neutron flux of 1013 cm-2 s-1 for periods of 1 minute, 1 and 10 hours. A Ge hyperpure detector was used for your activity determination, with count times of 60, 180, 300 and 600 seconds. The obtained results show than the method can be utilized for the determination of this elements without realize anything previous treatment of the samples. (Author)

  12. Supply-side barriers to maternity-care in India: a facility-based analysis.

    Directory of Open Access Journals (Sweden)

    Santosh Kumar

    Full Text Available BACKGROUND: Health facilities in many low- and middle-income countries face several types of barriers in delivering quality health services. Availability of resources at the facility may significantly affect the volume and quality of services provided. This study investigates the effect of supply-side determinants of maternity-care provision in India. METHODS: Health facility data from the District-Level Household Survey collected in 2007-2008 were analyzed to explore the effects of supply-side factors on the volume of delivery care provided at Indian health facilities. A negative binomial regression model was applied to the data due to the count and over-dispersion property of the outcome variable (number of deliveries performed at the facility. RESULTS: Availability of a labor room (Incidence Rate Ratio [IRR]: 1.81; 95% Confidence Interval [CI]: 1.68-1.95 and facility opening hours (IRR: 1.43; CI: 1.35-1.51 were the most significant predictors of the volume of delivery care at the health facilities. Medical and paramedical staff were found to be positively associated with institutional deliveries. The volume of deliveries was also higher if adequate beds, essential obstetric drugs, medical equipment, electricity, and communication infrastructures were available at the facility. Findings were robust to the inclusion of facility's catchment area population and district-level education, health insurance coverage, religion, wealth, and fertility. Separate analyses were performed for facilities with and without a labor room and results were qualitatively similar across these two types of facilities. CONCLUSIONS: Our study highlights the importance of supply-side barriers to maternity-care India. To meet Millennium Development Goals 4 and 5, policymakers should make additional investments in improving the availability of medical drugs and equipment at primary health centers (PHCs in India.

  13. Formulation and preparation on Hanford Waste Treatment Plan direct feed low activity waste effluent management facility core simulant

    Energy Technology Data Exchange (ETDEWEB)

    McCabe, Daniel J. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Nash, Charles A. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL; Adamson, Duane J. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL

    2016-05-01

    The Hanford Waste Treatment and Immobilization Plant (WTP) Low Activity Waste (LAW) vitrification facility will generate an aqueous condensate recycle stream (LAW Melter Off-Gas Condensate, LMOGC) from the off-gas system. The baseline plan for disposition of this stream during full WTP operations is to send it to the WTP Pretreatment Facility, where it will be blended with LAW, concentrated by evaporation and recycled to the LAW vitrification facility. However, during the Direct Feed LAW (DFLAW) scenario, planned disposition of this stream is to evaporate it in a new evaporator in the Effluent Management Facility (EMF) and then return it to the LAW melter. It is important to understand the composition of the effluents from the melter and new evaporator so that the disposition of these streams can be accurately planned and accommodated. Furthermore, alternate disposition of the LMOGC stream would eliminate recycling of problematic components, and would enable less integrated operation of the LAW melter and the Pretreatment Facilities. Alternate disposition would also eliminate this stream from recycling within WTP when it begins operations and would decrease the LAW vitrification mission duration and quantity of glass waste, amongst the other problems such a recycle stream present. This LAW Melter Off-Gas Condensate stream will contain components that are volatile at melter temperatures and are problematic for the glass waste form, such as halides and sulfate. Because this stream will recycle within WTP, these components accumulate in the Melter Condensate stream, exacerbating their impact on the number of LAW glass containers that must be produced. Diverting the stream reduces the halides and sulfate in the recycled Condensate and is a key outcome of this work. This overall program examines the potential treatment and immobilization of this stream to enable alternative disposal. The objective of this task was to formulate and prepare a simulant of the LAW Melter

  14. Analysis of ayurvedic medicinal leaves by instrumental neutron activation analysis

    International Nuclear Information System (INIS)

    Concentrations of 15 elements were determined in medicinally important ayurvedic medicinal leaves. Instrumental neutron activation analysis was employed for the determination of the elements viz. Na, K, Br, Sm, Cr, Zn, Th, Rb, Sr, Fe, La, Co, Ce, Cs and Eu. The samples were neutron irradiated at 100 kW TRIGA -Mainz nuclear reactor and the induced activities were measured by gamma ray spectrometry using an efficiency calibrated high resolution high purity germanium (HPGe) detector. The concentrations of these elements in the medicinal leaves and their medicinal importance are discussed. (author)

  15. Multielemental analysis of soils by instrumental neutron activation analysis

    International Nuclear Information System (INIS)

    The results of an instrumental neutron activation analysis of some elemental concentrations in different soil samples near the industrial areas at Tirupati, India, are reported. Altogether 14 elements, Sm, La, Cr, Co, Zn, Cs, Ce, Th, Rb, Na, K, Sr, Fe and Eu were determined. The samples were irradiated with neutrons at the 100 kW Triga - Mainz research reactor and the induced activities were measured by gamma-ray spectrometry using an efficiency calibrated high resolution high purity germanium (HPGe) detector in connection with a multichannel analyzer. The results are discussed. (author)

  16. Results from the CDE phase activity on neutron dosimetry for the international fusion materials irradiation facility test cell

    CERN Document Server

    Esposito, B; Maruccia, G; Petrizzi, L; Bignon, G; Blandin, C; Chauffriat, S; Lebrun, A; Recroix, H; Trapp, J P; Kaschuck, Y

    2000-01-01

    The international fusion materials irradiation facility (IFMIF) project deals with the study of an accelerator-based, deuterium-lithium source, producing high energy neutrons at sufficient intensity and irradiation volume to test samples of candidate materials for fusion energy reactors. IFMIF would also provide calibration and validation of data from fission reactor and other accelerator based irradiation tests. This paper describes the activity on neutron/gamma dosimetry (necessary for the characterization of the specimens' irradiation) performed in the frame of the IFMIF conceptual design evaluation (CDE) neutronics tasks. During the previous phase (conceptual design activity (CDA)) the multifoil activation method was proposed for the measurement of the neutron fluence and spectrum and a set of suitable foils was defined. The cross section variances and covariances of this set of foils have now been used for tests on the sensitivity of the IFMIF neutron spectrum determination to cross section uncertainties...

  17. Stakeholder issues and involvement in decommissioning nuclear facilities. Lessons learnt from WPDD and FSC activities and documentation

    International Nuclear Information System (INIS)

    , there is a need to consider also views of stakeholders that represent national interests. As the decision process moves from issues concerned with the shutdown of the plant to strategies for its dismantling, the importance of purely local interests becomes greater. For this reason, it is necessary to develop dialogue and cooperation among regulators, implementers, and local stakeholders as early as practicable. The host municipalities for nuclear facilities tend to focus their attention on the day-to-day issues arising from the activities at the plant and, as regards decommissioning, will generally favour the early reuse of the site for economic or cultural purposes. As in other phases of the nuclear facility life cycle, it is necessary to develop trust among stakeholders in decommissioning and dismantling projects. This may be accomplished through involving local and regional actors in decision-making, but also in monitoring activities, so as to have a better grip on the continuous changes taking place at the site. Transparency is needed in decision-making and in the respective roles played by regulators, implementers and local authorities. At all times, proactive information, and efforts to 'translate' technical information into language meaningful to the chosen audience, will contribute to building mutual understanding and trust. Partnership arrangements, by which institutions enter into structured project-management relationships with local communities, have been found beneficial. Decommissioning in both nuclear and non-nuclear areas may be viewed as an opportunity to improve the sustainability of the host community. The creation of added cultural or economic value can contribute to increasing quality of life over the years. More recent designs integrating reflection on the end use of the facility and site, or technical provisions for quick transitions to other types of facilities, provide better assurance to the host community that there will be

  18. Chemical mass balance modeling for air quality analysis near a waste-to-energy facility in a complex urban area: Program design

    International Nuclear Information System (INIS)

    This paper describes the design and implementation of an ambient monitoring and receptor modeling study to evaluate air quality impacts from a state-of-the-art municipal waste management facility in a major urban area. The Robbins Resource Recovery Facility (RRRF), located in the Chicago metropolitan area, processes municipal solid waste (MSW) to recover recyclables, process the residual waste to create refuse-derived fuel (RDF), and burns the RDF to reduce the residual waste volume and recover energy. The RRRF is cooperating with the Illinois Environmental Protection Agency (IEPA) and the Illinois Office of the Attorney General (OAG) to analyze air quality and facility impacts in the plant vicinity. An ambient monitoring program began one year before plant operation and will continue for five years after startup. Because the impacts of the RRRF are projected to be very low, and because the Chicago area includes a complex mix of existing industrial, commercial, and residential activity, the ambient data will be analyzed using Version 7.0 of the USEPA s Chemical Mass Balance (CMB) model to estimate the extent of the RRRF's impact on air quality in the area. The first year of pre-operational ambient data is currently under analysis. This paper describes the study design considerations, ambient monitoring program, emission data acquisition, background source data needs, and data analysis procedures developed to conduct CMB modeling in a complex industrialized area

  19. The state of art of the NIES-TERRA (Accelerator analysis facility, National Institute for Environmental Studies)

    Energy Technology Data Exchange (ETDEWEB)

    Yoneda, Minoru; Shibata, Yasuyuki; Tanaka, Atsushi; Uchida, Masao; Hirota, Masashi; Uehiro, Takashi; Morita, Masatoshi [National Inst. for Environmental Studies Tsukuba, Ibaraki (Japan)

    2001-02-01

    The status of the NIES-TERRA accelerator facility in FY1999 is presented. Accelerator Mass Spectrometry (AMS) has been performed mainly for the routine measurement of environmental, geological, archaeological samples. Analysis has been done for Al-26, Be-10, as well as C-14. The operation experiences are described. The accelerator has been operated 23000 hours since its construction. Minor troubles during the operation are reported. The pretreatment system, required for the analysis in further precision, is under development. (A. Yamamoto)

  20. Inadvertent Intruder Analysis For The Portsmouth On-Site Waste Disposal Facility (OSWDF)

    Energy Technology Data Exchange (ETDEWEB)

    Smith, Frank G.; Phifer, Mark A.

    2014-01-22

    The inadvertent intruder analysis considers the radiological impacts to hypothetical persons who are assumed to inadvertently intrude on the Portsmouth OSWDF site after institutional control ceases 100 years after site closure. For the purposes of this analysis, we assume that the waste disposal in the OSWDF occurs at time zero, the site is under institutional control for the next 100 years, and inadvertent intrusion can occur over the following 1,000 year time period. Disposal of low-level radioactive waste in the OSWDF must meet a requirement to assess impacts on such individuals, and demonstrate that the effective dose equivalent to an intruder would not likely exceed 100 mrem per year for scenarios involving continuous exposure (i.e. chronic) or 500 mrem for scenarios involving a single acute exposure. The focus in development of exposure scenarios for inadvertent intruders was on selecting reasonable events that may occur, giving consideration to regional customs and construction practices. An important assumption in all scenarios is that an intruder has no prior knowledge of the existence of a waste disposal facility at the site. Results of the analysis show that a hypothetical inadvertent intruder at the OSWDF who, in the worst case scenario, resides on the site and consumes vegetables from a garden established on the site using contaminated soil (chronic agriculture scenario) would receive a maximum chronic dose of approximately 7.0 mrem/yr during the 1000 year period of assessment. This dose falls well below the DOE chronic dose limit of 100 mrem/yr. Results of the analysis also showed that a hypothetical inadvertent intruder at the OSWDF who, in the worst case scenario, excavates a basement in the soil that reaches the waste (acute basement construction scenario) would receive a maximum acute dose of approximately 0.25 mrem/yr during the 1000 year period of assessment. This dose falls well below the DOE acute dose limit of 500 mrem/yr. Disposal inventory

  1. Survivability analysis of a sewage treatment facility using hybrid Petri nets

    NARCIS (Netherlands)

    Ghasemieh, Hamed; Remke, Anne; Haverkort, Boudewijn R.

    2015-01-01

    Waste water treatment facilities clean sewage water from households and industry in several cleaning steps. Such facilities are dimensioned to accommodate a maximum intake. However, in the case of very bad weather conditions or failures of system components, the system might not be able to accommoda

  2. Universal definition of loss to follow-up in HIV treatment programs: a statistical analysis of 111 facilities in Africa, Asia, and Latin America.

    Directory of Open Access Journals (Sweden)

    Benjamin H Chi

    2011-10-01

    Full Text Available Although patient attrition is recognized as a threat to the long-term success of antiretroviral therapy programs worldwide, there is no universal definition for classifying patients as lost to follow-up (LTFU. We analyzed data from health facilities across Africa, Asia, and Latin America to empirically determine a standard LTFU definition.At a set "status classification" date, patients were categorized as either "active" or "LTFU" according to different intervals from time of last clinic encounter. For each threshold, we looked forward 365 d to assess the performance and accuracy of this initial classification. The best-performing definition for LTFU had the lowest proportion of patients misclassified as active or LTFU. Observational data from 111 health facilities-representing 180,718 patients from 19 countries-were included in this study. In the primary analysis, for which data from all facilities were pooled, an interval of 180 d (95% confidence interval [CI]: 173-181 d since last patient encounter resulted in the fewest misclassifications (7.7%, 95% CI: 7.6%-7.8%. A secondary analysis that gave equal weight to cohorts and to regions generated a similar result (175 d; however, an alternate approach that used inverse weighting for cohorts based on variance and equal weighting for regions produced a slightly lower summary measure (150 d. When examined at the facility level, the best-performing definition varied from 58 to 383 d (mean=150 d, but when a standard definition of 180 d was applied to each facility, only slight increases in misclassification (mean=1.2%, 95% CI: 1.0%-1.5% were observed. Using this definition, the proportion of patients classified as LTFU by facility ranged from 3.1% to 45.1% (mean=19.9%, 95% CI: 19.1%-21.7%.Based on this evaluation, we recommend the adoption of ≥180 d since the last clinic visit as a standard LTFU definition. Such standardization is an important step to understanding the reasons that underlie patient

  3. A facile preparation of crystalline GeS{sub 2} nanoplates and their photocatalytic activity

    Energy Technology Data Exchange (ETDEWEB)

    Wang, Qifan [School of Chemical and Environmental Engineering, Shanghai Institute of Technology, Shanghai 201418 (China); Kang, Shi-Zhao, E-mail: kangsz@sit.edu.cn [School of Chemical and Environmental Engineering, Shanghai Institute of Technology, Shanghai 201418 (China); Li, Xiangqing [School of Chemical and Environmental Engineering, Shanghai Institute of Technology, Shanghai 201418 (China); Yang, Ying-Wei [State Key Laboratory of Supramolecular Structure and Materials, College Of Chemistry, Jilin University, 2699 Qianjin Street, Changchun 130012 (China); Qin, Lixia [School of Chemical and Environmental Engineering, Shanghai Institute of Technology, Shanghai 201418 (China); Mu, Jin, E-mail: mujin@sit.edu.cn [School of Chemical and Environmental Engineering, Shanghai Institute of Technology, Shanghai 201418 (China)

    2015-05-15

    Graphical abstract: The crystalline GeS{sub 2} nanoplates have been successfully prepared in the low temperature solvothermal process. Meanwhile, the as-prepared crystalline GeS{sub 2} nanoplates show considerable photocatalytic activity for hydrogen evolution from water, implying that GeS{sub 2} nanomaterials have great potential in the field of hydrogen generation from light-driven water splitting. - Highlights: • GeS{sub 2} nanoplates were prepared by a low temperature solvothermal process. • GeS{sub 2} nanoplates obtained possess high crystallinity. • Nanostructured GeS{sub 2} is first applied in the photocatalytic H{sub 2} evolution. - Abstract: Crystalline GeS{sub 2} nanoplates were prepared by low temperature solvothermal process and characterized with X-ray diffraction, transmission electron microscopy, energy-dispersion X-ray analysis, X-ray photoelectron spectroscopy, nitrogen adsorption, Raman spectroscopy, FT-IR spectroscopy and UV–vis–NIR diffuse reflectance absorption spectroscopy. Photocatalytic hydrogen evolution from water over the as-prepared GeS{sub 2} nanoplates was explored using Na{sub 2}S and K{sub 2}SO{sub 3} as sacrificial reagents. The results indicate that the crystalline orthorhombic GeS{sub 2} nanoplates can be obtained at 140 °C using this simple method and acetic acid as the solvent plays an important role in the formation of the GeS{sub 2} nanoplates. More importantly, the as-prepared GeS{sub 2} nanoplates can serve as a potential photocatalyst with a rate of H{sub 2} evolution of 144 μmol g{sup −1} h{sup −1} for hydrogen production from water when a xenon lamp is used as a light source. In addition, the formation mechanism of GeS{sub 2} nanoplates was preliminarily discussed.

  4. The Case for the Application of Worldwide Marine Radioactivity Studies In the Search for Undeclared Facilities and Activities

    Energy Technology Data Exchange (ETDEWEB)

    Mark Schanfein

    2013-06-01

    Undeclared nuclear facilities unequivocally remain the most difficult safeguards challenge facing the International Atomic Energy Agency (IAEA). Recent cases of undeclared facilities revealed in Iran and Syria, which are NPT signatory States, show both the difficulty and the seriousness of this threat to nonproliferation. In the case of undeclared nuclear facilities, the most effective deterrent against proliferation is the application of Wide-Area Environmental Sampling (WAES); however, WAES is currently cost-prohibitive. As with any threat, the most effective countering strategy is a multifaceted approach. Some of the approaches applied by the IAEA include: open source analysis, satellite imagery, on-site environmental sampling, complementary access under the Additional Protocol (where in force), traditional safeguards inspections, and information provided by member States. These approaches, naturally, are focused on specific States. Are there other opportunities not currently within the IAEA purview to assess States that may provide another opportunity to detect clandestine facilities? In this paper, the author will make the case that the IAEA Department of Safeguards should explore the area of worldwide marine radioactivity studies as one possible opportunity. One such study was released by the IAEA Marine Environment Laboratory in January 2005. This technical document focused on 90Sr, 137Cs, and 239/240Pu. It is clearly a challenging area because of the many sources of anthropogenic radionuclides in the world’s oceans and seas including: nuclear weapons testing, reprocessing, accidents, waste dumping, and industrial and medical radioisotopes, whose distributions change based on oceanographic, geochemical, and biological processes, and their sources. It is additionally challenging where multiple States share oceans, seas, and rivers. But with the application of modern science, historical sampling to establish baselines, and a focus on the most relevant

  5. Negotiated compensation for solid-waste disposal facility siting: An analysis of the Wisconsin experience

    Energy Technology Data Exchange (ETDEWEB)

    Nieves, L.A. (Argonne National Lab., IL (United States)); Himmelberger, J.J.; Ratick, S.J. (Clark Univ., Worcester, MA (United States)); White, A.L. (Clark Univ., Worcester, MA (United States) Tellus Institute, Boston, MA (United States))

    1992-12-01

    Since enacting a unique facility siting law in 1981, Wisconsin has had unusual success in siting solid-waste management facilities. The law mandates a state-level technical review and licensing process and a local-level negotiation/arbitration process that deals with host community impacts and concerns. Data from the negotiated compensation agreements, a survey of facility proposers, and secondary data for the host communities are analyzed in relation to compensation levels. Concerns with community image and health risks and with facility management and equity issues are found to significantly and substantially increase negotiated compensation levels. In contrast, a focus on logistics and transportation concerns is associated with lower levels of compensation. Compensation increases with facility capacity but at a less than proportional rate. Higher levels of compensation are obtained by communities that accept compensation in kind in the form of free or reduced fees for host community waste disposal.

  6. Accident analysis for aircraft crash into hazardous facilities: A statistical primer

    International Nuclear Information System (INIS)

    The DOE Standard 3014-96, Accident Analysis for Aircraft Crash into Hazardous Facilities provides a robust statistical framework useful for assessing the release frequency for hazardous materials used in many industrial operations. The formulae and the verbal instructions for calculating screening quantities and frequencies in the DOE Standard are consistent with an unstated underlying six-term expression for estimating the annual number of aircraft-impact-related releases. The six-term formula is here shown to result from iterated application of Bayes' rule. The statistical concepts underlying this formula are explained; the six-term model is then developed and its components related to the corresponding elements of the four-factor model presented in the Standard. The six-term model is shown to be consistent with the instructions given in the Standard for calculating the screening and evaluation quantities using the four-factor model. The difference between screening and evaluation of release frequencies is clarified. Discussion of the six-term model shows clearly how conservative approximations to its conditional probability terms lead to simple and efficient screening formulae. A numerical example is provided to demonstrate a screening calculation

  7. CFD analysis and optimization of a liquid lead–bismuth loop target for ISOL facilities

    International Nuclear Information System (INIS)

    In the context of the forthcoming next generation of Radioactive Ion Beams (RIBs) facilities based on an Isotope Separation On Line (ISOL) method, the development of production targets capable of dissipating the high power deposited by the primary beam is a major challenge. The concept of a high-power target based on a liquid Pb–Bi loop incorporating a heat-exchanger and a diffusion chamber was proposed within EURISOL DS and is being developed within the LIEBE project. Due to the non-static character of the target, specific hydrodynamics issues are of concern. In this paper, these issues are studied mostly based on three-dimensional (3D) Computational Fluid Dynamics analysis of the flow of the Lead Bismuth Eutectic (LBE) target, resulting in optimized designs. The concept and hydrodynamic challenges of generating RIBs from a liquid-metal-loop target irradiated with a high-power primary beam are presented. The optimization of the target design has been conducted keeping in mind the need for a fast and efficient release of short-lived isotopes. This study shows that approximately 100 ms after the proton pulse the irradiated liquid-metal is entirely and uniformly evacuated from the irradiation volume and spread in a shower of small droplets (100-μm radii), in order to reduce the diffusion length of isotopes. Solutions to deal with the typical cavitation risk due to the presence of low-pressure zones in the liquid have also been found and simulated

  8. CFD analysis and optimization of a liquid lead–bismuth loop target for ISOL facilities

    Energy Technology Data Exchange (ETDEWEB)

    Houngbo, D., E-mail: dhoungbo@sckcen.be [Belgian Nuclear Research Centre (SCK-CEN), Boeretang 200, B-2400 Mol (Belgium); Department of Flow, Heat and Combustion Mechanics, Ghent University (UGent), St.-Pietersnieuwstraat 41, B-9000 Gent (Belgium); Popescu, L.; Schuurmans, P. [Belgian Nuclear Research Centre (SCK-CEN), Boeretang 200, B-2400 Mol (Belgium); Delonca, M.; Losito, R.; Maglioni, C.; Stora, T. [CERN, 1211 Geneva 23 (Switzerland); Bricault, P. [TRIUMF, 4004 Wesbrook Mall, Vancouver, B.C., V6T 2A3 (Canada); Vierendeels, J. [Department of Flow, Heat and Combustion Mechanics, Ghent University (UGent), St.-Pietersnieuwstraat 41, B-9000 Gent (Belgium)

    2015-03-21

    In the context of the forthcoming next generation of Radioactive Ion Beams (RIBs) facilities based on an Isotope Separation On Line (ISOL) method, the development of production targets capable of dissipating the high power deposited by the primary beam is a major challenge. The concept of a high-power target based on a liquid Pb–Bi loop incorporating a heat-exchanger and a diffusion chamber was proposed within EURISOL DS and is being developed within the LIEBE project. Due to the non-static character of the target, specific hydrodynamics issues are of concern. In this paper, these issues are studied mostly based on three-dimensional (3D) Computational Fluid Dynamics analysis of the flow of the Lead Bismuth Eutectic (LBE) target, resulting in optimized designs. The concept and hydrodynamic challenges of generating RIBs from a liquid-metal-loop target irradiated with a high-power primary beam are presented. The optimization of the target design has been conducted keeping in mind the need for a fast and efficient release of short-lived isotopes. This study shows that approximately 100 ms after the proton pulse the irradiated liquid-metal is entirely and uniformly evacuated from the irradiation volume and spread in a shower of small droplets (100-μm radii), in order to reduce the diffusion length of isotopes. Solutions to deal with the typical cavitation risk due to the presence of low-pressure zones in the liquid have also been found and simulated.

  9. Sampling and analysis plan for the preoperational environmental survey of the spent nuclear fuel project facilities

    International Nuclear Information System (INIS)

    This sampling and analysis plan will support the preoperational environmental monitoring for construction, development, and operation of the Spent Nuclear Fuel (SNF) Project facilities, which have been designed for the conditioning and storage of spent nuclear fuels; particularly the fuel elements associated with the operation of N-Reactor. The SNF consists principally of irradiated metallic uranium, and therefore includes plutonium and mixed fission products. The primary effort will consist of removing the SNF from the storage basins in K East and K West Areas, placing in multicanister overpacks, vacuum drying, conditioning, and subsequent dry vault storage in the 200 East Area. The primary purpose and need for this action is to reduce the risks to public health and safety and to the environment. Specifically these include prevention of the release of radioactive materials into the air or to the soil surrounding the K Basins, prevention of the potential migration of radionuclides through the soil column to the nearby Columbia River, reduction of occupational radiation exposure, and elimination of the risks to the public and to workers from the deterioration of SNF in the K Basins

  10. Analysis of shielding calculation methods for 16- and 64-slice computed tomography facilities

    Energy Technology Data Exchange (ETDEWEB)

    Moreno, C; Cenizo, E; Bodineau, C; Mateo, B; Ortega, E M, E-mail: c_morenosaiz@yahoo.e [Servicio de RadiofIsica Hospitalaria, Hospital Regional Universitario Carlos Haya, Malaga (Spain)

    2010-09-15

    The new multislice computed tomography (CT) machines require some new methods of shielding calculation, which need to be analysed. NCRP Report No. 147 proposes three shielding calculation methods based on the following dosimetric parameters: weighted CT dose index for the peripheral axis (CTDI{sub w,per}), dose-length product (DLP) and isodose maps. A survey of these three methods has been carried out. For this analysis, we have used measured values of the dosimetric quantities involved and also those provided by the manufacturer, making a comparison between the results obtained. The barrier thicknesses when setting up two different multislice CT instruments, a Philips Brilliance 16 or a Philips Brilliance 64, in the same room, are also compared. Shielding calculation from isodose maps provides more reliable results than the other two methods, since it is the only method that takes the actual scattered radiation distribution into account. It is concluded therefore that the most suitable method for calculating the barrier thicknesses of the CT facility is the one based on isodose maps. This study also shows that for different multislice CT machines the barrier thicknesses do not necessarily become bigger as the number of slices increases, because of the great dependence on technique used in CT protocols for different anatomical regions.

  11. Sampling and analysis plan for the preoperational environmental survey of the spent nuclear fuel project facilities

    Energy Technology Data Exchange (ETDEWEB)

    MITCHELL, R.M.

    1999-04-01

    This sampling and analysis plan will support the preoperational environmental monitoring for construction, development, and operation of the Spent Nuclear Fuel (SNF) Project facilities, which have been designed for the conditioning and storage of spent nuclear fuels; particularly the fuel elements associated with the operation of N-Reactor. The SNF consists principally of irradiated metallic uranium, and therefore includes plutonium and mixed fission products. The primary effort will consist of removing the SNF from the storage basins in K East and K West Areas, placing in multicanister overpacks, vacuum drying, conditioning, and subsequent dry vault storage in the 200 East Area. The primary purpose and need for this action is to reduce the risks to public health and safety and to the environment. Specifically these include prevention of the release of radioactive materials into the air or to the soil surrounding the K Basins, prevention of the potential migration of radionuclides through the soil column to the nearby Columbia River, reduction of occupational radiation exposure, and elimination of the risks to the public and to workers from the deterioration of SNF in the K Basins.

  12. Calibration Report for the WRAP Facility Gamma Energy Analysis System [104-ND-06-102A

    Energy Technology Data Exchange (ETDEWEB)

    WILLS, C.E.

    2000-02-15

    The Waste Receiving And Processing facility (WRAP) adheres to providing gamma-ray spectroscopy instrument calibrations traceable to the National Institute for Standards and Technology (NIST) standards. The detectors are used to produce quantitative results for the Waste Isolation Pilot Plant (WIPP) and must meet calibration programmatic calibration goals. Instruments must meet portions of ANSI N42.14, 1978 guide for Germanium detectors. The Non-Destructive Assay (NDA) Gamma Energy Analysis (GEA) utilizes NIST traceable line source standards for the detector system calibrations. The counting configuration is a series of drums containing the line sources and different density filler matrices. The drums are used to develop system efficiencies with respect to density. The efficiency and density correction factors are required for the processing of drummed waste materials of similar densities. The calibration verification is carried out after the calibration is deemed final, by counting a second drum of NIST traceable sources. Three in-depth calibrations have been completed on one of the two systems to date, the first being the system acceptance plan. This report has a secondary function; that being the development of the instrument calibration errors which are to be folded into the Total Instrument Uncertainty document, HNF-4050.

  13. Analysis of touch used by occupational therapy practitioners in skilled nursing facilities.

    Science.gov (United States)

    Morris, Douglas; Henegar, J; Khanin, S; Oberle, G; Thacker, S

    2014-09-01

    Instrumental touch is identified as having purposeful physical contact in order to complete a task. Expressive touch is identified as warm, friendly physical contact and is not solely for performing a task. Expressive touch has been associated with improved client status, increased rapport and greater gains made during therapy. The purpose of the study was to observe the frequency of expressive and instrumental touch utilized by an occupational therapist during an occupational therapy session. Thirty-three occupational therapy professionals, including occupational therapists and occupational therapy assistants, employed at skilled nursing facilities in southwest Florida were observed. Data were collected on the Occupational Therapy Interaction Assessment. The results of the data analysis showed a positive relationship between the gender of the therapist and the frequency of expressive touch. The data also showed that a large majority of touches were instrumental touch and pertained to functional mobility. The results of the study can contribute to a better understanding of the holistic aspects of occupational therapy. By the use of more expressive touch, occupational therapy practitioners may have a positive, beneficial effect on both the client and the therapy process as a whole. Further research is needed to determine the effect an occupational therapy setting has on the frequency of instrumental and expressive touch. A larger sample size and a distinction between evaluation and treatment sessions would benefit future studies.

  14. Calibration Report for the WRAP Facility Gamma Energy Analysis System (104-ND-06-102A)

    Energy Technology Data Exchange (ETDEWEB)

    WILLS, C.E.

    2000-03-13

    The Waste Receiving And Processing facility (WRAP) adheres to providing gamma-ray spectroscopy instrument calibrations traceable to the National Institute for Standards and Technology (NIST) standard{sup (4)}. The detectors are used to produce quantitative results for the Waste Isolation Pilot Plant (WIPP) and must meet calibration programmatic calibration goals. Instruments must meet portions of ANSI N42.14, 1978 guide for Germanium detectors. The Non-Destructive Assay (NDA) Gamma Energy Analysis (GEA) utilizes NIST traceable line source standards for the detector system calibrations. The counting configuration is a series of drums containing the line sources and different density filler matrices. The drums are used to develop system efficiencies with respect to density. The efficiency and density correction factors are required for the processing of drummed waste materials of similar densities. The calibration verification is carried out after the calibration is deemed final, by counting a second drum of NIST traceable sources. Three in-depth calibrations have been completed on one of the two systems to date, the first being the system acceptance plan. This report has a secondary function; that being the development of the instrument calibration errors which are to be folded into the Total Instrument Uncertainty document, HNF-4050.

  15. Facile synthesis of porous ZnO microbelts and analysis of their gas-sensing property

    Energy Technology Data Exchange (ETDEWEB)

    Huang, Jiarui, E-mail: jrhuang@mail.anhu.edu.cn; Shi, Chengcheng; Fu, Guijun; Sun, Pingping; Wang, Xinyue; Gu, Cuiping, E-mail: cpgu2008@mail.ahnu.edu.cn

    2014-04-01

    Porous ZnO microbelts were achieved using a facile chemical solution method combined with subsequent calcination. The micro-nanostructures were characterized through X-ray diffraction, field emission scanning electron microscopy, thermogravimetric-differential thermal analysis, and Brunauer–Emmett–Teller N{sub 2} adsorption-desorption analyses, among others. The BET surface area of the porous ZnO microbelts was calculated at 23.0 m² g{sup −1}. Furthermore, the gas sensing properties of the as-prepared porous ZnO microbelts were investigated using volatile organic compounds. Compared with ZnO microflowers, the porous ZnO microbelts exhibited higher response with certain organic vapors, such as formaldehyde, acetone, and ethanol. The responses to 100 ppm formaldehyde, acetone, and ethanol were 45.7, 40.6, and 38.4, respectively, at a working temperature of 300 °C. The results showed that the porous ZnO microbelts are highly promising candidates for gas sensing applications. - Highlights: • Zinc glycinate monohydrate microwires were obtained by a chemical solution method. • Porous ZnO microbelts were achieved after calcinations. • The porous ZnO microbelts exhibit superior gas-sensing property.

  16. Multiattribute utility analysis as a framework for public participation in siting a hazardous waste management facility

    Energy Technology Data Exchange (ETDEWEB)

    Merkhofer, M.W. [Applied Decision Analysis, Inc., Menlo Park, CA (United States); Conway, R. [Sandia National Labs., Albuquerque, NM (United States); Anderson, R.G. [Los Alamos National Lab., NM (United States)

    1997-11-01

    In an attempt to facilitate the resolution of contentious environmental problems public and private organizations are experimenting with collaborative approaches wherein stakeholders participate in the decision-making process. A dilemma for the design of collaborative approaches is the technical complexity of many environmental problems. How can members of the public play a meaningful role in decisions that involve complicated scientific arguments? This paper describes a public participation exercise in which stakeholders used an approach based on multiattribute utility analysis to select a site for a hazardous waste management facility. The key to success was the ability to separate and address two types of judgments inherent in environmental decisions-technical judgments regarding the likely consequences of alternative choices and value judgments regarding the importance or seriousness of those consequences. The approach enabled technical specialists to communicate the essential technical considerations and allowed stakeholders to establish the value judgments for the decision. Although rarely used in public participation, the multiattribute utility approach appears to provide a useful framework for the collaborative resolution of complex environmental decision problems.

  17. Industrial applications of neutron activation analysis

    International Nuclear Information System (INIS)

    Neutron activation analysis has been widely used in the industry and over the years played a key role in the development of manufacturing process as well as monitoring of the process flow. In this context NAA has been utilized both in R and D, and in the factory as a flexible analytical tool. It has been used successfully in numerous industries including broad categories such as Chemical, Pharmaceutical, Mining, Photographic, Oil and Gas, Automobile, Defense, Semiconductor and Electronic industries. Dow Chemical owns and operates a research reactor for analytical measurements of samples generated in both R and D, and manufacturing area in its plant in Midland, Michigan. Although most industries do not have reactors on their campus but use an off site reactor regularly, and often have in-house neutron sources such as a 252Cf used primarily for NAA. In most industrial materials analysis laboratory NAA is part of a number of analytical techniques such as ICP-MS, AA, SIMS, FTIR, XRF, TXRF etc. Analysis of complex industrial samples may require data from each of these methods to provide a clear picture of the materials issues involved. With the improvement of classical analytical techniques, and the introduction of new techniques, e.g. TXRF, the role of NAA continues to be a key bench mark technique that provides accurate and reliable data. The strength of the NAA in bulk analysis is balanced by its weakness in providing surface sensitive or spatially resolved analysis as is required by many applications. (author)

  18. The analysis of interface emulsion detector for the OPERA experiment in JAPAN Scanning facility

    Science.gov (United States)

    Fukuda, T.; Kodama, K.; Komatsu, M.; Miyamoto, S.; Morishima, K.; Nakano, T.; Omura, T.; Sakatani, Y.; Sato, O.

    2010-04-01

    The OPERA experiment, designed to search for neutrino oscillations, started its physics run in July 2008. It is the most recent emulsion-counter hybrid experiment. In this experiment two different types of emulsion detectors are used. One is called Emulsion Cloud Chamber (ECC), and is used as a target. The other is called Changeable Sheet (CS), which is attached to the downstream side of each ECC to identify the ECC in which a tagged neutrino interaction occurred. The CS interfaces rough tracking information obtained in the electronic detectors to the ECC and therefore is a key element of the emulsion-counter hybrid experiment. As a first step, a CS selected by electronic detectors is scanned and analyzed to decide if the ECC is to be developed and analyzed in detail; a few CS are usually to be analyzed to identify an ECC for each tagged event due to the inaccuracy of the electronic detectors. The CS has a large scanning area and therefore Japan and Europe (Gran Sasso) are sharing in the CS analysis load to handle the scanning job. In this paper, the CS analysis method developed for the Japan scanning facility is described in detail. 100 million tracks are read out on each CS by an automatic emulsion read-out system ( S-UTS ), most of them are so-called fake tracks mainly due to low momentum Compton electrons or random noise and a few real tracks from a tagged neutrino interaction have to be picked up among a huge background. A dedicated method to reject this background without losing real tracks has been developed on the basis of analyzing track data obtained by S-UTS and combining these data with a final selection using additional information on multiple Coulomb scattering of candidate tracks obtained by human eye check to eliminate a remaining background. Performance of this method is shown to be sufficient for the OPERA experiment.

  19. Measurement of zinc-65 in Japanese 5-yen coins in various places activated by neutron originated from the critical accident at JCO facility

    International Nuclear Information System (INIS)

    Activated zinc-65 in Japanese 5-yen coins, which include 37 wt% of zinc, was measured to obtain the basic data on neutron doses in various places assumed to be attacked by the nuclear-fuel processing facility in Tokaimura, Japan on 30 September, 1999. The isotope was detected in the coins picked up from the houses 100 to 550 meters from the facility and its activity was from 39.6 to 0.76 Bq/kg-Zn. These data can be used to estimate neutron doses of people who were living or working around the facility and whose doses have not been estimated yet. (author)

  20. Risk assessment and optimization (ALARA) analysis for the environmental remediation of Brookhaven National Laboratory`s hazardous waste management facility

    Energy Technology Data Exchange (ETDEWEB)

    Dionne, B.J.; Morris, S.C. III; Baum, J.W. [and others

    1998-01-01

    The Department of Energy`s (DOE) Office of Environment, Safety, and Health (EH) sought examples of risk-based approaches to environmental restoration to include in their guidance for DOE nuclear facilities. Extensive measurements of radiological contamination in soil and ground water have been made at Brookhaven National Laboratory`s Hazardous Waste Management Facility (HWMF) as part of a Comprehensive Environmental Response, Compensation and Liability Act (CERCLA) remediation process. This provided an ideal opportunity for a case study. This report provides a risk assessment and an {open_quotes}As Low as Reasonably Achievable{close_quotes} (ALARA) analysis for use at other DOE nuclear facilities as an example of a risk-based decision technique. This document contains the Appendices for the report.

  1. New-doses limits introduction analysis for the design and operation of teletherapy facilities established by IAEA

    International Nuclear Information System (INIS)

    A design of a typical teletherapy facility was made considering a Co-60 rotating unit and using critical parameters, taking into account as a design base the dose limits established in the Safety Series No. 9 (1), and Safety Series No.115-I (2), shielding thickness when the dose limits were changed. An increment in the required thickness of 1,35 CHR for controlled areas and 2,37 CHR for non-controlled areas were found. This work considered the selection of four different types of teletherapy facilities using Co-60 sources, with different design and type of used unit. An analysis of thickness was made taking into account both the original values for the design and the real operation values in each facility. In order to determine the necessary changes for the wall thicknesses when the new recommendations are applied. (authors). 4 refs., 3 tabs

  2. Risk assessment and optimization (ALARA) analysis for the environmental remediation of Brookhaven National Laboratory`s hazardous waste management facility

    Energy Technology Data Exchange (ETDEWEB)

    Dionne, B.J.; Morris, S. III; Baum, J.W. [and others

    1998-03-01

    The Department of Energy`s (DOE) Office of Environment, Safety, and Health (EH) sought examples of risk-based approaches to environmental restoration to include in their guidance for DOE nuclear facilities. Extensive measurements of radiological contamination in soil and ground water have been made at Brookhaven National Laboratory`s Hazardous Waste Management Facility (HWMF) as part of a Comprehensive Environmental Response, Compensation and Liability Act (CERCLA) remediation process. This provided an ideal opportunity for a case study. This report provides a risk assessment and an {open_quotes}As Low as Reasonably Achievable{close_quotes} (ALARA) analysis for use at other DOE nuclear facilities as an example of a risk-based decision technique.

  3. Risk assessment and optimization (ALARA) analysis for the environmental remediation of Brookhaven National Laboratory's hazardous waste management facility

    International Nuclear Information System (INIS)

    The Department of Energy's (DOE) Office of Environment, Safety, and Health (EH) sought examples of risk-based approaches to environmental restoration to include in their guidance for DOE nuclear facilities. Extensive measurements of radiological contamination in soil and ground water have been made at Brookhaven National Laboratory's Hazardous Waste Management Facility (HWMF) as part of a Comprehensive Environmental Response, Compensation and Liability Act (CERCLA) remediation process. This provided an ideal opportunity for a case study. This report provides a risk assessment and an open-quotes As Low as Reasonably Achievableclose quotes (ALARA) analysis for use at other DOE nuclear facilities as an example of a risk-based decision technique. This document contains the Appendices for the report

  4. 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...

  5. FY2010 ANNUAL REVIEW E-AREA LOW-LEVEL WASTE FACILITY PERFORMANCE ASSESSMENT AND COMPOSITE ANALYSIS

    Energy Technology Data Exchange (ETDEWEB)

    Butcher, T.; Swingle, R.; Crapse, K.; Millings, M.; Sink, D.

    2011-01-01

    The E-Area Low-Level Waste Facility (ELLWF) consists of a number of disposal units described in the Performance Assessment (PA)(WSRC, 2008b) and Composite Analysis (CA)(WSRC, 1997; WSRC, 1999): Low-Activity Waste (LAW) Vault, Intermediate Level (IL) Vault, Trenches (Slit Trenches [STs], Engineered Trenches [ETs], and Component-in-Grout [CIG] Trenches), and Naval Reactor Component Disposal Areas (NRCDAs). This annual review evaluates the adequacy of the approved 2008 ELLWF PA along with the Special Analyses (SAs) approved since the PA was issued. The review also verifies that the Fiscal Year (FY) 2010 low-level waste (LLW) disposal operations were conducted within the bounds of the PA/SA baseline, the Savannah River Site (SRS) CA, and the Department of Energy (DOE) Disposal Authorization Statement (DAS). Important factors considered in this review include waste receipts, results from monitoring and research and development (R&D) programs, and the adequacy of controls derived from the PA/SA baseline. Sections 1.0 and 2.0 of this review are a summary of the adequacy of the PA/SA and CA, respectively. An evaluation of the FY2010 waste receipts and the resultant impact on the ELLWF is summarized in Section 3.1. The results of the monitoring program, R&D program, and other relevant factors are found in Section 3.2, 3.3 and 3.4, respectively. Section 4.0 contains the CA annual determination similarly organized. SRS low-level waste management is regulated under DOE Order 435.1 (DOE, 1999a) and is authorized under a DAS as a federal permit. The original DAS was issued by the DOE-Headquarters (DOE-HQ) on September 28, 1999 (DOE, 1999b) for the operation of the ELLWF and the Saltstone Disposal Facility (SDF). The 1999 DAS remains in effect for the regulation of the SDF. Those portions of that DAS applicable to the ELLWF were superseded by revision 1 of the DAS on July 15, 2008 (DOE, 2008b). The 2008 PA and DAS were officially implemented by the facility on October 31, 2008

  6. Current Activities of Neutron Imaging Facilities in KUR (Kyoto University Research Reactor)

    Science.gov (United States)

    Kawabata, Yuji; Saito, Yasushi

    Kyoto University research Reactor (KUR) restarted in Spring 2010 with low enriched fuel (20%) after 4 years tentative interruption for fuel conversion. There are two facilities for neutron imaging: 1) B4 port at supermirror neutron guide tube (5x107 n/cm2/s at 5 MW, 1 cmx7.5 cm), 2) E2 port (3x105 n/cm2/s at 5 MW, 15 cm dia.). As we have large experimental space at the end of the guide tube and need small shielding because the neutron flux of KUR is not high, we have very large flexibility in the experimental set up. Thus, experiments in B4 should be specialized in the measurements which require large and/or unconventional equipments to accommodate special sample conditions. The E2 port with the low neutron flux is used for experiments which need very long or frequent machine times.

  7. A facile synthesis of nanorods of ZnO/graphene oxide composites with enhanced photocatalytic activity

    Energy Technology Data Exchange (ETDEWEB)

    Qin, Jiaqian, E-mail: jiaqian.q@chula.ac.th [Metallurgy and Materials Science Research Institute, Chulalongkorn University, Bangkok 10330 (Thailand); State Key Laboratory of Metastable Materials Science and Technology, Yanshan University, Qinhuangdao 066004 (China); Zhang, Xinyu, E-mail: xyzhang@ysu.edu.cn [State Key Laboratory of Metastable Materials Science and Technology, Yanshan University, Qinhuangdao 066004 (China); Xue, Yannan [State Key Laboratory of Metastable Materials Science and Technology, Yanshan University, Qinhuangdao 066004 (China); Kittiwattanothai, Nutsakun [Department of Physics, King Mongkut' s University of Technology Thonburi (Thailand); Kongsittikul, Pongsakorn [Department of Petrochemicals and Polymer Science, Chulalongkorn University (Thailand); Rodthongkum, Nadnudda; Limpanart, Sarintorn [Metallurgy and Materials Science Research Institute, Chulalongkorn University, Bangkok 10330 (Thailand); Ma, Mingzhen; Liu, Riping [State Key Laboratory of Metastable Materials Science and Technology, Yanshan University, Qinhuangdao 066004 (China)

    2014-12-01

    Graphical abstract: - Highlights: • Room temperature method to prepare ZnO–GO composites. • ZnO–GO composites exhibit superior absorption ability and photocatalytic performance. • With GO content increasing, the absorption and photocatalytic ability increased. - Abstract: Graphene oxide (GO)–ZnO nanorods composites were successfully synthesized by a facile room-temperature approach using the colloidal coagulation effect. The samples are characterized by X-ray diffraction, scanning electron microscopy, transmission electron microscopy, specific surface area, and UV–vis spectroscopy. The photodegradation of methylene blue (MB) has been investigated in the presence of composites. It is observed that the absorption capacity and photocatalytic effect could be enhanced by adding graphene oxide.

  8. Analysis of Hanford-based Options for Sustainable DOE Facilities on the West Coast

    Energy Technology Data Exchange (ETDEWEB)

    Warwick, William M.

    2012-06-30

    Large-scale conventional energy projects result in lower costs of energy (COE). This is true for most renewable energy projects as well. The Office of Science is interested in its facilities meeting the renewable energy mandates set by Congress and the Administration. Those facilities on the west coast include a cluster in the Bay Area of California and at Hanford in central Washington State. Land constraints at the California facilities do not permit large scale projects. The Hanford Reservation has land and solar insolation available for a large scale solar project as well as access to a regional transmission system that can provide power to facilities in California. The premise of this study is that a large-scale solar project at Hanford may be able to provide renewable energy sufficient to meet the needs of select Office of Science facilities on the west coast at a COE that is competitive with costs in California despite the lower solar insolation values at Hanford. The study concludes that although the cost of solar projects continues to decline, estimated costs for a large-scale project at Hanford are still not competitive with avoided power costs for Office of Science facilities on the west coast. Further, although it is possible to transmit power from a solar project at Hanford to California facilities, the costs of doing so add additional costs. Consequently, development of a large- scale solar project at Hanford to meet the renewable goals of Office of Science facilities on the west coast is currently uneconomic. This may change as solar costs decrease and California-based facilities face increasing costs for conventional and renewable energy produced in the state. PNNL should monitor those cost trends.

  9. Scalable histopathological image analysis via active learning.

    Science.gov (United States)

    Zhu, Yan; Zhang, Shaoting; Liu, Wei; Metaxas, Dimitris N

    2014-01-01

    Training an effective and scalable system for medical image analysis usually requires a large amount of labeled data, which incurs a tremendous annotation burden for pathologists. Recent progress in active learning can alleviate this issue, leading to a great reduction on the labeling cost without sacrificing the predicting accuracy too much. However, most existing active learning methods disregard the "structured information" that may exist in medical images (e.g., data from individual patients), and make a simplifying assumption that unlabeled data is independently and identically distributed. Both may not be suitable for real-world medical images. In this paper, we propose a novel batch-mode active learning method which explores and leverages such structured information in annotations of medical images to enforce diversity among the selected data, therefore maximizing the information gain. We formulate the active learning problem as an adaptive submodular function maximization problem subject to a partition matroid constraint, and further present an efficient greedy algorithm to achieve a good solution with a theoretically proven bound. We demonstrate the efficacy of our algorithm on thousands of histopathological images of breast microscopic tissues. PMID:25320821

  10. Activation Analysis and Nuclear Research in Burma

    International Nuclear Information System (INIS)

    Research endeavours in the field of Nuclear Sciences in Burma appear to be concentrated in three main Institutions. These are the Chemistry and Physics Departments of the Rangoon Arts & Science University and the Union of Burma Applied Research Institute (UBARI). In view of possible forthcoming developments an expanded research programme, which is to be implemented on the basis of a five year plan, has been drawn up. Research topics included in this programme are predominantly of practical interest and aimed at a contribution by nuclear methods, in particular activation analysis, to the technological and industrial needs of the country

  11. DOE standard: Integration of environment, safety, and health into facility disposition activities. Volume 1 of 2: Technical standard

    International Nuclear Information System (INIS)

    This Department of Energy (DOE) technical standard (referred to as the Standard) provides guidance for integrating and enhancing worker, public, and environmental protection during facility disposition activities. It provides environment, safety, and health (ES and H) guidance to supplement the project management requirements and associated guidelines contained within DOE O 430.1A, Life-Cycle Asset Management (LCAM), and amplified within the corresponding implementation guides. In addition, the Standard is designed to support an Integrated Safety Management System (ISMS), consistent with the guiding principles and core functions contained in DOE P 450.4, Safety Management System Policy, and discussed in DOE G 450.4-1, Integrated Safety Management System Guide. The ISMS guiding principles represent the fundamental policies that guide the safe accomplishment of work and include: (1) line management responsibility for safety; (2) clear roles and responsibilities; (3) competence commensurate with responsibilities; (4) balanced priorities; (5) identification of safety standards and requirements; (6) hazard controls tailored to work being performed; and (7) operations authorization. This Standard specifically addresses the implementation of the above ISMS principles four through seven, as applied to facility disposition activities

  12. Health facility-based Active Management of the Third Stage of Labor: findings from a national survey in Tanzania

    Directory of Open Access Journals (Sweden)

    Mfinanga Godfrey S

    2009-04-01

    Full Text Available Abstract Background Hemorrhage is the leading cause of obstetric mortality. Studies show that Active Management of Third Stage of Labor (AMTSL reduces Post Partum Hemorrhage (PPH. This study describes the practice of AMTSL and barriers to its effective use in Tanzania. Methods A nationally-representative sample of 251 facility-based vaginal deliveries was observed for the AMTSL practice. Standard Treatment Guidelines (STG, the Essential Drug List and medical and midwifery school curricula were reviewed. Drug availability and storage conditions were reviewed at the central pharmaceutical storage site and pharmacies in the selected facilities. Interviews were conducted with hospital directors, pharmacists and 106 health care providers in 29 hospitals visited. Data were collected between November 10 and December 15, 2005. Results Correct practice of AMTSL according to the ICM/FIGO definition was observed in 7% of 251 deliveries. When the definition of AMTSL was relaxed to allow administration of the uterotonic drug within three minutes of fetus delivery, the proportion of AMTSL use increased to 17%. The most significant factor contributing to the low rate of AMTSL use was provision of the uterotonic drug after delivery of the placenta. The study also observed potentially-harmful practices in approximately 1/3 of deliveries. Only 9% out of 106 health care providers made correct statements regarding the all three components of AMTSL. The national formulary recommends ergometrine (0.5 mg/IM or oxytocin (5 IU/IM on delivery of the anterior shoulder or immediately after the baby is delivered. Most of facilities had satisfactory stores of drugs and supplies. Uterotonic drugs were stored at room temperature in 28% of the facilities. Conclusion The knowledge and practice of AMTSL is very low and STGs are not updated on correct AMTSL practice. The drugs for AMTSL are available and stored at the right conditions in nearly all facilities. All providers used

  13. Data Sharing Report for the Quantification of Removable Activity in Various Surveillance and Maintenance Facilities at the Oak Ridge National Laboratory Oak Ridge TN

    Energy Technology Data Exchange (ETDEWEB)

    King, David A

    2013-12-12

    The U.S. Department of Energy (DOE) Oak Ridge Office of Environmental Management (OR-EM) 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 American Recovery and Reinvestment Act (ARRA) funds. Specifically, DOE OR-EM requested that ORAU plan and implement a sampling and analysis campaign targeting potential removable radiological contamination that may be transferrable to future personal protective equipment (PPE) and contamination control materials—collectively referred to as PPE throughout the remainder of this report—used in certain URS|CH2M Oak Ridge, LLC (UCOR) Surveillance and Maintenance (S&M) Project facilities at the Oak Ridge National Laboratory (ORNL). Routine surveys in Bldgs. 3001, 3005, 3010, 3028, 3029, 3038, 3042, 3517, 4507, and 7500 continuously generate PPE. The waste is comprised of Tyvek coveralls, gloves, booties, Herculite, and other materials used to prevent worker exposure or the spread of contamination during routine maintenance and monitoring activities. This report describes the effort to collect and quantify removable activity that may be used by the ORNL S&M Project team to develop radiation instrumentation “screening criteria.” Material potentially containing removable activity was collected on smears, including both masselin large-area wipes (LAWs) and standard paper smears, and analyzed for site-related constituents (SRCs) in an analytical laboratory. The screening criteria, if approved, may be used to expedite waste disposition of relatively clean PPE. The ultimate objectives of this effort were to: 1) determine whether screening criteria can be developed for these facilities, and 2) provide process knowledge information for future site planners. The screening criteria, if calculated, must be formally approved by Federal Facility Agreement parties prior to use for

  14. Multi-element analysis of the obese subject by in vivo neutron activation analysis

    International Nuclear Information System (INIS)

    The Leeds facility for in vivo neutron activation analysis has been modified and calibrated for the simultaneous measurement of nitrogen, potassium, sodium, chlorine, phosphorus and calcium in obese patients weighing up to 210 kg. The effects of body size and shape were incorporated into the calibration by measuring 14 anthropomorphic phantoms of known composition representing individual patients being treated for obesity. The phantoms were constructed from tissue substitutes representing lean skeletal and adipose tissues, arranged to simulate the distributions of the corresponding tissues within the patients, as visualised by CT scanning. The precision of the method, determined by measuring a single phantom ten times over a period of ten weeks, is between two and three per cent for all elements except calcium, for which it is 11.3%. Accuracy is estimated to be similar to precision. The procedure has been used to study changes in body composition of patients undergoing therapeutic starvation. (author)

  15. Analysis of some egyptian cosmetic samples by using fast neutron activation analysis

    International Nuclear Information System (INIS)

    A description of our neutron generator (NG) facility for neutron activation analysis is presented. As an example, the concentration of Na, Mg, Al, Si, K, Cl, Ca and Fe elements were determined in two domestic brands of face powder by using a beam of 14 MeV neutrons. An empirical expression for detector efficiency in terms of incident gamma ray energy and the source-detector distance has been obtained for a hyper pure germanium detector (HPGe) using different standard point sources. The comparison of the calculated efficiencies and the measured values in the energy range from 59.5 to 1332.2 keV and for source-to-detector distances of 5-30 cm show the agreement between the calculated values and the measured experimental values

  16. Pedestrian choice behavior analysis and simulation of vertical walking facilities in transfer station

    Science.gov (United States)

    Li, Yong-Xing; Jia, Hong-Fei; Li, Jun; Zhou, Ya-Nan; Yuan, Zhi-Lu; Li, Yan-Zhong

    2016-10-01

    Considering the interlayer height, luggage, the difference between queuing pedestrians, and walking speed, the pedestrian choice model of vertical walking facilities is established based on a support vector machine. This model is verified with the pedestrian flow data of Changchun light-rail transfer station and Beijing Xizhimen transfer station. Adding the pedestrian choice model of vertical walking facilities into the pedestrian simulation model which is based on cellular automata, the pedestrian choice behavior is simulated. In the simulation, the effects of the dynamic influence factors are analyzed. To reduce the conflicts between pedestrians in opposite directions, the layout of vertical walking facilities is improved. The simulations indicate that the improved layout of vertical walking facilities can improve the efficiency of pedestrians passing. Project supported by the National Natural Science Foundation of China (Grant Nos. 51278221 and 51378076) and the Science Technology Development Project of Jilin Province, China (Grant No. 20140204027SF).

  17. Stress Analysis and Evaluation of Piping System in Uranium Liquor Critical Facility

    Institute of Scientific and Technical Information of China (English)

    2008-01-01

    <正>The piplines of the piping system in the uranium liquor critical facility are very thin, so the piping rigidity is bad, the measuring cylinders piping system (Fig. 1) connects the vessel the pump and the rigid

  18. International conference on lessons learned from the decommissioning of nuclear facilities and the safe termination of nuclear activities. Contributed papers

    International Nuclear Information System (INIS)

    The International Atomic Energy Agency (IAEA), in cooperation with the European Commission (EC), Nuclear Energy Agency to the Organisation for Economic Co-operation and Development (OECD/NEA), and the World Nuclear Association (WNA), organized an International Conference on Lessons Learned from the Decommissioning of Nuclear Facilities and the Safe Termination of Nuclear Activities from 11 to 15 December 2006 in Athens, Greece. This Book of Contributed Papers contains technical papers and posters contributed by experts from operating organisations, regulatory bodies, technical support organisations, and other institutions on issues falling within the scope of the Conference. The following main topics were covered: Evolution of national and international policies and criteria for the safe and efficient decommissioning of nuclear facilities and safe termination of nuclear activities; Review of lessons learned from ongoing or completed activities associated with decommissioning; Improvement of safety and efficiency through the use of new and innovative technologies; Practical aspects in the management of material, waste and sites resulting from decommissioning, including the management of waste in the absence of repositories and waste acceptance requirements; Procedures for demonstrating compliance with clearance criteria; Experience from radiological assessments associated with decommissioning; Involvement of the local communities and the impact that decommissioning activities has on them. The presented papers and posters were reviewed and accepted following the guidelines established by the Conference Programme Committee for consideration at the Conference. The material compiled in this Book of Contributed Papers has not undergone rigorous editing by the editorial staff of the IAEA. However, certain modifications were made: a unified format was adopted for all papers; and minor corrections were made in the text where required. Each paper and poster has been indexed

  19. 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.

  20. Estimation of nickel-63 in steel and copper activated at high-energy accelerator facilities

    International Nuclear Information System (INIS)

    63Ni(β-decay; t1/2 = 100.1 y) is produced abundantly in stainless steel and copper hardware at high-energy accelerators. A measurement method using a liquid-scintillation counter has been developed. Its approximate activity could be estimated based on the thermal and fast-neutron fluxes measured by an activation method using gold and copper. After a few tens of years from beam-off, the existence of a no γ-radiation level from this accelerator hardware does not necessarily mean that all activity has decayed out, since there is still a possibility that an appreciable amount of 63Ni remains. (Author)