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Sample records for analysis iba facility

  1. Penyingkapan Diri Ibas Yudhoyono Dalam Instagram Dan Reaksi Ani Yudhoyono Terhadap Postingan Instagram Ibas

    Directory of Open Access Journals (Sweden)

    Suzy Azeharie

    2015-07-01

    Full Text Available Edy Baskoro Yudhoyono’s or well known as Ibas is the youngest son of the former President SBY and currently active as a politician for Democratic Party and member of Parliament. Thus it is important for Ibas as a political actor to do self-disclosure and convey political messages through his social media accounts. The main object of this paper is Ibas’s post in his Instagram account as a media for unveiling himself. This paper will also discuss about Mrs. Ani Yudhoyono or Ibas’s mother, the former first lady, in given response and reaction on the Ibas’s post. Methodology used for data collection in this paper is content analysis. The results of the content analysis show that Ibas was frequently post pictures of his family than his political activities. Moreover Ibas himself never respond to all incoming comments from his followers. Eventhough it was positive comments. Surprisingly, reaction and response was given by Mrs. Ani Yudhoyono. In many of Ibas’s post, Mrs. Ani Yudhoyono was sharp and yet keen on responding to the comments coming from Ibas’s followers. Mrs. Ani Yudhoyono response was often received disapproval and negative comments from other followers, because to their concern Mrs. Ani Yudhoyono was not using the right grammar of English and this eventually led to a hot debate between fellow follower's comments. The final conclusion that can be obtained is Ibas did not make his Instagram account as a media unveiling herself but only using his account as a medium for sharing photos. Which appear to be more active in doing communication and self-disclosure is Mrs. Ani Yudhoyono herself. Edy Baskoro Yudhoyono atau lebih dikenal dengan nama Ibas merupakan putra bungsu dari mantan presiden SBY dan saat ini aktif sebagai politikus Partai Demokrat dan juga anggota DPR RI. fokus utama dalam penelitian ini adalah postingan Ibas dalam akun instagramnya yang merupakan sarana untuk penyingkapan dirinya, serta bagaimana reaksi Ibu Ani

  2. Elemental analysis by IBA and NAA — A critical comparison

    Science.gov (United States)

    Watterson, J. I. W.

    1988-12-01

    In this review neutron activation analysis (NAA) and ion beam analysis (IBA) have been compared in the context of the entire field of analytical science using the discipline of scientometrics, as developed by Braun and Lyon. This perspective on the relative achievements of the two methods is modified by considering and comparing their particular attributes and characteristics, particularly in relation to their differing degree of maturity. This assessment shows that NAA, as the more mature method, is the most widely applied nuclear technique, but the special capabilities of IBA give it the ability to provide information about surface composition and elemental distribution that is unique, while it is still relatively immature and it is not yet possible to define its ultimate role with any confidence.

  3. SIRIUS - A new 6 MV accelerator system for IBA and AMS at ANSTO

    Science.gov (United States)

    Pastuovic, Zeljko; Button, David; Cohen, David; Fink, David; Garton, David; Hotchkis, Michael; Ionescu, Mihail; Long, Shane; Levchenko, Vladimir; Mann, Michael; Siegele, Rainer; Smith, Andrew; Wilcken, Klaus

    2016-03-01

    The Centre for Accelerator Science (CAS) facility at ANSTO has been expanded with a new 6 MV tandem accelerator system supplied by the National Electrostatic Corporation (NEC). The beamlines, end-stations and data acquisition software for the accelerator mass spectrometry (AMS) were custom built by NEC for rare isotope mass spectrometry, while the beamlines with end-stations for the ion beam analysis (IBA) are largely custom designed at ANSTO. An overview of the 6 MV system and its performance during testing and commissioning phase is given with emphasis on the IBA end-stations and their applications for materials modification and characterisation.

  4. Development of a versatile user-friendly IBA experimental chamber

    Energy Technology Data Exchange (ETDEWEB)

    Kakuee, Omidreza; Fathollahi, Vahid; Lamehi-Rachti, Mohammad

    2016-03-15

    Reliable performance of the Ion Beam Analysis (IBA) techniques is based on the accurate geometry of the experimental setup, employment of the reliable nuclear data and implementation of dedicated analysis software for each of the IBA techniques. It has already been shown that geometrical imperfections lead to significant uncertainties in quantifications of IBA measurements. To minimize these uncertainties, a user-friendly experimental chamber with a heuristic sample positioning system for IBA analysis was recently developed in the Van de Graaff laboratory in Tehran. This system enhances IBA capabilities and in particular Nuclear Reaction Analysis (NRA) and Elastic Recoil Detection Analysis (ERDA) techniques. The newly developed sample manipulator provides the possibility of both controlling the tilt angle of the sample and analyzing samples with different thicknesses. Moreover, a reasonable number of samples can be loaded in the sample wheel. A comparison of the measured cross section data of the {sup 16}O(d,p{sub 1}){sup 17}O reaction with the data reported in the literature confirms the performance and capability of the newly developed experimental chamber.

  5. Development of a versatile user-friendly IBA experimental chamber

    Science.gov (United States)

    Kakuee, Omidreza; Fathollahi, Vahid; Lamehi-Rachti, Mohammad

    2016-03-01

    Reliable performance of the Ion Beam Analysis (IBA) techniques is based on the accurate geometry of the experimental setup, employment of the reliable nuclear data and implementation of dedicated analysis software for each of the IBA techniques. It has already been shown that geometrical imperfections lead to significant uncertainties in quantifications of IBA measurements. To minimize these uncertainties, a user-friendly experimental chamber with a heuristic sample positioning system for IBA analysis was recently developed in the Van de Graaff laboratory in Tehran. This system enhances IBA capabilities and in particular Nuclear Reaction Analysis (NRA) and Elastic Recoil Detection Analysis (ERDA) techniques. The newly developed sample manipulator provides the possibility of both controlling the tilt angle of the sample and analyzing samples with different thicknesses. Moreover, a reasonable number of samples can be loaded in the sample wheel. A comparison of the measured cross section data of the 16O(d,p1)17O reaction with the data reported in the literature confirms the performance and capability of the newly developed experimental chamber.

  6. SIRIUS – A new 6 MV accelerator system for IBA and AMS at ANSTO

    Energy Technology Data Exchange (ETDEWEB)

    Pastuovic, Zeljko, E-mail: zkp@ansto.gov.au; Button, David; Cohen, David; Fink, David; Garton, David; Hotchkis, Michael; Ionescu, Mihail; Long, Shane; Levchenko, Vladimir; Mann, Michael; Siegele, Rainer; Smith, Andrew; Wilcken, Klaus

    2016-03-15

    The Centre for Accelerator Science (CAS) facility at ANSTO has been expanded with a new 6 MV tandem accelerator system supplied by the National Electrostatic Corporation (NEC). The beamlines, end-stations and data acquisition software for the accelerator mass spectrometry (AMS) were custom built by NEC for rare isotope mass spectrometry, while the beamlines with end-stations for the ion beam analysis (IBA) are largely custom designed at ANSTO. An overview of the 6 MV system and its performance during testing and commissioning phase is given with emphasis on the IBA end-stations and their applications for materials modification and characterisation.

  7. System on chip (SoC) microcontrollers (μC) as digitisers for ion beam analysis (IBA) instruments

    Energy Technology Data Exchange (ETDEWEB)

    Whitlow, Harry J., E-mail: harry.j@whitlow.se

    2016-09-15

    Data digitisation of the analogue signals from detectors to digital data is an essential process in ion beam analysis (IBA). The low-cost, easy availability and development environments that have a low learning threshold makes system-on-chip (SoC) microcontrollers (μC) attractive for this task. These μC combine, on one die, analogue and digital inputs and outputs with serial USB interfaces, which opens up simple implementation of tailor-made interfaces for specific IBA measurement systems. We have investigated the design and performance limitations based on development of three different digitisation interfaces for IBA. These were a two-channel nuclear instrumentation module (NIM) ADC event mode interface (EMI) for a high-resolution magnetic RBS spectrometer, a simple headless-multi-channel analyser (MCA) and a combined dual channel headless MCA and EMI. It is shown that SoC μC based interfaces for digitisation of analogue spectroscopy pulses in IBA systems can be implemented for material costs less than 100 €. The performance of the SoC devices for many IBA applications is close to what can be achieved with state-of-the-art instruments. The simple pulse spectroscopy interface circuit and software are included in the auxiliary archive.

  8. IBA in deformed nuclei

    International Nuclear Information System (INIS)

    Casten, R.F.; Warner, D.D.

    1982-01-01

    The structure and characteristic properties and predictions of the IBA in deformed nuclei are reviewed, and compared with experiment, in particular for 168 Er. Overall, excellent agreement, with a minimum of free parameters (in effect, two, neglecting scale factors on energy differences), was obtained. A particularly surprising, and unavoidable, prediction is that of strong β → γ transitions, a feature characteristically absent in the geometrical model, but manifest empirically. Some discrepancies were also noted, principally for the K=4 excitation, and the detailed magnitudes of some specific B(E2) values. Considerable attention is paid to analyzing the structure of the IBA states and their relation to geometric models. The bandmixing formalism was studied to interpret both the aforementioned discrepancies and the origin of the β → γ transitions. The IBA states, extremely complex in the usual SU(5) basis, are transformed to the SU(3) basis, as is the interaction Hamiltonian. The IBA wave functions appear with much simplified structure in this way as does the structure of the associated B(E2) values. The nature of the symmetry breaking of SU(3) for actual deformed nuclei is seen to be predominantly ΔK=0 mixing. A modified, and more consistent, formalism for the IBA-1 is introduced which is simpler, has fewer free parameters (in effect, one, neglecting scale factors on energy differences), is in at least as good agreement with experiment as the earlier formalism, contains a special case of the 0(6) limit which corresponds to that known empirically, and appears to have a close relationship to the IBA-2. The new formalism facilitates the construction of contour plots of various observables (e.g., energy or B(E2) ratios) as functions of N and chi/sub Q/ which allow the parameter-free discussion of qualitative trajectories or systematics

  9. The IBAS image analyser and its use in particle size measurement

    International Nuclear Information System (INIS)

    Snelling, K.W.

    1984-10-01

    The Kontron image analyser (IBAS) is used at Winfrith primarily for size analysis of aerosol particles. The system incorporates two computers, IBAS 1 for system communication and control, and IBAS 2 containing the main image memories. The first is accessed via a keyboard or digitiser tablet, and output can be displayed on a monitor or in printed form. The contents of the image memories are displayed on a colour monitor. Automatic image analysis is described, with typical applications, including the measurement of monodisperse particles, sodium fire aerosols, reactor crud particles and cadmium-silver aerosol particles. (U.K.)

  10. iTRAQ-Based Proteomic Analysis Reveals Potential Regulation Networks of IBA-Induced Adventitious Root Formation in Apple

    Directory of Open Access Journals (Sweden)

    Chao Lei

    2018-02-01

    Full Text Available Adventitious root (AR formation, which is controlled by endogenous and environmental factors, is indispensable for vegetative asexual propagation. However, comprehensive proteomic data on AR formation are still lacking. The aim of this work was to study indole-3-butyric acid (IBA-induced AR formation in the dwarf apple rootstock ‘T337’. In this study, the effect of IBA on AR formation was analysed. Subsequent to treatment with IBA, both the rooting rate and root length of ‘T337’ increased significantly. An assessment of hormone levels in basal stem cuttings suggested that auxin, abscisic acid, and brassinolide were higher in basal stem cuttings that received the exogenous IBA application; while zeatin riboside, gibberellins, and jasmonic acid were lower than non-treated basal stem cuttings. To explore the underlying molecular mechanism, an isobaric tags for relative and absolute quantification (iTRAQ-based proteomic technique was employed to identify the expression profiles of proteins at a key period of adventitious root induction (three days after IBA treatment. In total, 3355 differentially expressed proteins (DEPs were identified. Many DEPs were closely related to carbohydrate metabolism and energy production, protein homeostasis, reactive oxygen and nitric oxide signaling, and cell wall remodeling biological processes; as well as the phytohormone signaling, which was the most critical process in response to IBA treatment. Further, RT-qPCR analysis was used to evaluate the expression level of nine genes that are involved in phytohormone signaling and their transcriptional levels were mostly in accordance with the protein patterns. Finally, a putative work model was proposed. Our study establishes a foundation for further research and sheds light on IBA-mediated AR formation in apple as well as other fruit rootstock cuttings.

  11. A tailored 200 parameter VME based data acquisition system for IBA at the Lund Ion Beam Analysis Facility – Hardware and software

    International Nuclear Information System (INIS)

    Elfman, Mikael; Ros, Linus; Kristiansson, Per; Nilsson, E.J. Charlotta; Pallon, Jan

    2016-01-01

    With the recent advances towards modern Ion Beam Analysis (IBA), going from one- or few-parameter detector systems to multi-parameter systems, it has been necessary to expand and replace the more than twenty years old CAMAC based system. A new VME multi-parameter (presently up to 200 channels) data acquisition and control system has been developed and implemented at the Lund Ion Beam Analysis Facility (LIBAF). The system is based on the VX-511 Single Board Computer (SBC), acting as master with arbiter functionality and consists of standard VME modules like Analog to Digital Converters (ADC’s), Charge to Digital Converters (QDC’s), Time to Digital Converters (TDC’s), scaler’s, IO-cards, high voltage and waveform units. The modules have been specially selected to support all of the present detector systems in the laboratory, with the option of future expansion. Typically, the detector systems consist of silicon strip detectors, silicon drift detectors and scintillator detectors, for detection of charged particles, X-rays and γ-rays. The data flow of the raw data buffers out from the VME bus to the final storage place on a 16 terabyte network attached storage disc (NAS-disc) is described. The acquisition process, remotely controlled over one of the SBCs ethernet channels, is also discussed. The user interface is written in the Kmax software package, and is used to control the acquisition process as well as for advanced online and offline data analysis through a user-friendly graphical user interface (GUI). In this work the system implementation, layout and performance are presented. The user interface and possibilities for advanced offline analysis are also discussed and illustrated.

  12. A tailored 200 parameter VME based data acquisition system for IBA at the Lund Ion Beam Analysis Facility – Hardware and software

    Energy Technology Data Exchange (ETDEWEB)

    Elfman, Mikael, E-mail: Mikael.Elfman@nuclear.lu.se; Ros, Linus; Kristiansson, Per; Nilsson, E.J. Charlotta; Pallon, Jan

    2016-03-15

    With the recent advances towards modern Ion Beam Analysis (IBA), going from one- or few-parameter detector systems to multi-parameter systems, it has been necessary to expand and replace the more than twenty years old CAMAC based system. A new VME multi-parameter (presently up to 200 channels) data acquisition and control system has been developed and implemented at the Lund Ion Beam Analysis Facility (LIBAF). The system is based on the VX-511 Single Board Computer (SBC), acting as master with arbiter functionality and consists of standard VME modules like Analog to Digital Converters (ADC’s), Charge to Digital Converters (QDC’s), Time to Digital Converters (TDC’s), scaler’s, IO-cards, high voltage and waveform units. The modules have been specially selected to support all of the present detector systems in the laboratory, with the option of future expansion. Typically, the detector systems consist of silicon strip detectors, silicon drift detectors and scintillator detectors, for detection of charged particles, X-rays and γ-rays. The data flow of the raw data buffers out from the VME bus to the final storage place on a 16 terabyte network attached storage disc (NAS-disc) is described. The acquisition process, remotely controlled over one of the SBCs ethernet channels, is also discussed. The user interface is written in the Kmax software package, and is used to control the acquisition process as well as for advanced online and offline data analysis through a user-friendly graphical user interface (GUI). In this work the system implementation, layout and performance are presented. The user interface and possibilities for advanced offline analysis are also discussed and illustrated.

  13. Consultation and IBA negotiations in wind projects

    Energy Technology Data Exchange (ETDEWEB)

    Merle, Alexander [Bull Housser and Tupper LLP (Canada)

    2011-07-01

    This presentation aimed at providing more information on consultation and IBA negotiations in wind energy projects, it was given by a law firm Bull, Housser and Tupper LLP. The subjects tackled by this paper are: the duty to consult, what First Nations are expecting from IBAs, if IBAs will differ from one wind project to another, if templates assist in achieving equity, who should be responsible for financing IBAs, and whether benefits or payments of money can achieve equity. The presentation emphasised that it is important to cooperate and share information in determining what the role of the Crown should be. In addition, the authors believe that an innovative resolution table should be established and that legal certainty should be obtained. This presentation provided First Nations with useful information on consultation and IBA negotiations in wind energy projects.

  14. Transcriptomic analysis reveals the gene expression profile that specifically responds to IBA during adventitious rooting in mung bean seedlings.

    Science.gov (United States)

    Li, Shi-Weng; Shi, Rui-Fang; Leng, Yan; Zhou, Yuan

    2016-01-12

    Auxin plays a critical role in inducing adventitious rooting in many plants. Indole-3-butyric acid (IBA) is the most widely employed auxin for adventitious rooting. However, the molecular mechanisms by which auxin regulate the process of adventitious rooting are less well known. The RNA-Seq data analysis indicated that IBA treatment greatly increased the amount of clean reads and the amount of expressed unigenes by 24.29 % and 27.42 % and by 4.3 % and 5.04 % at two time points, respectively, and significantly increased the numbers of unigenes numbered with RPKM = 10-100 and RPKM = 500-1000 by 13.04 % and 3.12 % and by 24.66 % and 108.2 % at two time points, respectively. Gene Ontology (GO) enrichment analysis indicated that the enrichment of down-regulated GOs was 2.87-fold higher than that of up-regulated GOs at stage 1, suggesting that IBA significantly down-regulated gene expression at 6 h. The GO functional category indicated that IBA significantly up- or down-regulated processes associated with auxin signaling, ribosome assembly and protein synthesis, photosynthesis, oxidoreductase activity and extracellular region, secondary cell wall biogenesis, and the cell wall during the development process. Kyoto Encyclopedia of Genes and Genomes (KEGG) pathway enrichment indicated that ribosome biogenesis, plant hormone signal transduction, pentose and glucuronate interconversions, photosynthesis, phenylpropanoid biosynthesis, sesquiterpenoid and triterpenoid biosynthesis, ribosome, cutin, flavonoid biosynthesis, and phenylalanine metabolism were the pathways most highly regulated by IBA. A total of 6369 differentially expressed (2-fold change > 2) unigenes (DEGs) with 3693 (58 %) that were up-regulated and 2676 (42 %) down-regulated, 5433 unigenes with 2208 (40.6 %) that were up-regulated and 3225 (59.4 %) down-regulated, and 7664 unigenes with 3187 (41.6 %) that were up-regulated and 4477 (58.4 %) down-regulated were detected at stage 1

  15. The IBA Easy-E-Beam™ Integrated Processing System

    Science.gov (United States)

    Cleland, Marshall R.; Galloway, Richard A.; Lisanti, Thomas F.

    2011-06-01

    IBA Industrial Inc., (formerly known as Radiation Dynamics, Inc.) has been making high-energy and medium-energy, direct-current proton and electron accelerators for research and industrial applications for many years. Some industrial applications of high-power electron accelerators are the crosslinking of polymeric materials and products, such as the insulation on electrical wires, multi-conductor cable jackets, heat-shrinkable plastic tubing and film, plastic pipe, foam and pellets, the partial curing of rubber sheet for automobile tire components, and the sterilization of disposable medical devices. The curing (polymerization and crosslinking) of carbon and glass fiber-reinforced composite plastic parts, the preservation of foods and the treatment of waste materials are attractive possibilities for future applications. With electron energies above 1.0 MeV, the radiation protection for operating personnel is usually provided by surrounding the accelerator facility with thick concrete walls. With lower energies, steel and lead panels can be used, which are substantially thinner and more compact than the equivalent concrete walls. IBA has developed a series of electron processing systems called Easy-e-Beam™ for the medium energy range from 300 keV to 1000 keV. These systems include the shielding as an integral part of a complete radiation processing facility. The basic concepts of the electron accelerator, the product processing equipment, the programmable control system, the configuration of the radiation shielding and some performance characteristics are described in this paper.

  16. The IBA Easy-E-Beam Integrated Processing System

    International Nuclear Information System (INIS)

    Cleland, Marshall R.; Galloway, Richard A.; Lisanti, Thomas F.

    2011-01-01

    IBA Industrial Inc., (formerly known as Radiation Dynamics, Inc.) has been making high-energy and medium-energy, direct-current proton and electron accelerators for research and industrial applications for many years. Some industrial applications of high-power electron accelerators are the crosslinking of polymeric materials and products, such as the insulation on electrical wires, multi-conductor cable jackets, heat-shrinkable plastic tubing and film, plastic pipe, foam and pellets, the partial curing of rubber sheet for automobile tire components, and the sterilization of disposable medical devices. The curing (polymerization and crosslinking) of carbon and glass fiber-reinforced composite plastic parts, the preservation of foods and the treatment of waste materials are attractive possibilities for future applications. With electron energies above 1.0 MeV, the radiation protection for operating personnel is usually provided by surrounding the accelerator facility with thick concrete walls. With lower energies, steel and lead panels can be used, which are substantially thinner and more compact than the equivalent concrete walls. IBA has developed a series of electron processing systems called Easy-e-Beam for the medium energy range from 300 keV to 1000 keV. These systems include the shielding as an integral part of a complete radiation processing facility. The basic concepts of the electron accelerator, the product processing equipment, the programmable control system, the configuration of the radiation shielding and some performance characteristics are described in this paper.

  17. IBA analysis of some precolumbian gilded-copper samples

    Science.gov (United States)

    Andrade, E.; Murillo, G.; Policroniades, R.; Acosta, L.; Zavala, E. P.; Rocha, M. F.; Centeno, S. A.

    2005-10-01

    The elemental composition and depth profiles obtained by IBA techniques on some gilded-copper fragments from the Moche site of Loma Negra, in the Piura Valley, on the Northern Coast of Perú are presented in this article. A previous radiocarbon dating of a wooden fragment indicated that Loma Negra was occupied around 295 AD. A PIXE analysis using a 2.6 MeV external proton beam, was used to obtain the concentration of trace elements in the samples. RBS analyses using 2.72 MeV 4He+ and 12.0 MeV 12C3+ were used to obtain the Au, Ag, Cu atomic profiles. NRA with a 1.02 MeV deuteron beam was used to measure the oxygen and carbon concentrations through the 16O(d,p) 17O, 16O(d,α) 14N and 12C(d,p0) 13C reactions.

  18. IBA analysis of some precolumbian gilded-copper samples

    Energy Technology Data Exchange (ETDEWEB)

    Andrade, E. [Departamento de Fisica Experimental, Instituto de Fisica, Universidad Nacional Autonoma de Mexico, Apartado Postal 20-364, 01000 Mexico, DF (Mexico)]. E-mail: andrade@fisica.unam.mx; Murillo, G. [Departamento del Acelerador Instituto Nacional de Investigaciones Nucleares Apartado postal 18-1027, 11801 Mexico, DF (Mexico); Policroniades, R. [Departamento del Acelerador Instituto Nacional de Investigaciones Nucleares Apartado postal 18-1027, 11801 Mexico, DF (Mexico); Acosta, L. [Departamento de Fisica Experimental, Instituto de Fisica, Universidad Nacional Autonoma de Mexico, Apartado Postal 20-364, 01000 Mexico, DF (Mexico); Zavala, E.P. [Departamento de Fisica Experimental, Instituto de Fisica, Universidad Nacional Autonoma de Mexico, Apartado Postal 20-364, 01000 Mexico, DF (Mexico); Rocha, M.F. [Escuela Superior de Ingenieria Mecanica y Electrica, IPN, CP 07738 Mexico, DF (Mexico); Centeno, S.A. [Department of Scientific Research, The Metropolitan Museum of Art, 1000 Fifth Avenue, New York, NY 10028 (United States)

    2005-10-15

    The elemental composition and depth profiles obtained by IBA techniques on some gilded-copper fragments from the Moche site of Loma Negra, in the Piura Valley, on the Northern Coast of Peru are presented in this article. A previous radiocarbon dating of a wooden fragment indicated that Loma Negra was occupied around 295 AD. A PIXE analysis using a 2.6 MeV external proton beam, was used to obtain the concentration of trace elements in the samples. RBS analyses using 2.72 MeV {sup 4}He{sup +} and 12.0 MeV {sup 12}C{sup 3+} were used to obtain the Au, Ag, Cu atomic profiles. NRA with a 1.02 MeV deuteron beam was used to measure the oxygen and carbon concentrations through the {sup 16}O(d,p) {sup 17}O, {sup 16}O(d,{alpha}) {sup 14}N and {sup 12}C(d,p{sub 0}) {sup 13}C reactions.

  19. Comparison between XRF and IBA techniques in analysis of fine aerosols collected in Rijeka, Croatia

    Energy Technology Data Exchange (ETDEWEB)

    Ivošević, Tatjana [Faculty of Engineering, University of Rijeka, Vukovarska 58, HR-51000 Rijeka (Croatia); Mandić, Luka, E-mail: lukam@phy.uniri.hr [Department of Physics, University of Rijeka, Radmile Matejčić 2, HR-51000 Rijeka (Croatia); Orlić, Ivica [Department of Physics, University of Rijeka, Radmile Matejčić 2, HR-51000 Rijeka (Croatia); Stelcer, Eduard; Cohen, David D. [Institute for Environmental Research, Australian Nuclear Science and Technology Organisation, Kirrawee DC, NSW 2232 (Australia)

    2014-10-15

    The new system for energy dispersive X-ray fluorescence (EDXRF) analysis has been installed at the Laboratory for Elemental Micro-Analysis (LEMA) at the University of Rijeka. Currently the key application of this new XRF system is in the field of environmental science, i.e. in the analysis of fine airborne particles. In this work, results of initial multi-elemental analysis of PM{sub 2.5} fraction is reported for the first time in the region of Rijeka, Croatia. Sampling was performed at the Rijeka City center, during a continuous 9-day period in February/March 2012. All samples were collected on stretched Teflon filters in 12 h periods. To check the reliability of the new XRF system, results of XRF analysis are compared with the results obtained by the well-established Ion Beam Analysis (IBA) laboratory at Australian Nuclear Science and Technology Organisation (ANSTO). The concentrations of H, Na, Al, Si, P, S, Cl, K, Ca, Ti, V, Cr, Mn, Fe, Co, Ni, Cu, Zn, Br and Pb were determined. In addition, black carbon was determined by Laser Integrating Plate Method (LIPM). Very good agreement between XRF and IBA techniques is obtained for all elements detected by both techniques. Elemental concentrations were correlated with the traffic volume and wind speed and direction. The summary of our findings is presented and discussed in this paper.

  20. Survey of experimental tests of the IBA model

    International Nuclear Information System (INIS)

    Casten, R.F.

    1980-01-01

    A survey of experimental tests of the Interacting Boson Approximation (IBA) Model is presented covering even and odd mass nuclei in the region from A approx. 80 to A approx. 230. Both positive and negative parity states with both high and low spin are discussed. Topics included concern energy levels, electromagnetic transition rates, two nucleon transfer and inelastic scattering. Special attention is given to nuclear symmetries and transitional regions. Comparison with other models is made where appropriate. The distinction between IBA-1 and IBA-2 is discussed including their respective areas of applicability

  1. Axial asymmetry, finite particle number and the IBA

    International Nuclear Information System (INIS)

    Casten, R.F.

    1984-01-01

    Although the IBA-1 contains no solutions corresponding to a rigid triaxial shape, it does contain an effective asymmetry. This arises from zero point motion in a γ-soft potential leading to a non-zero mean or rms γ. Three aspects of this feature will be discussed: (1) The relation between IBA-1 calculations and the corresponding γ. This point is developed in the context of the Consistent Q Formalism (CQF) of the IBA. (2) The dependence of this asymmetry on boson number, N, and the exploitation of this dependence to set limits on both the relative and absolute values of N for deformed nuclei. (3) The relation between this asymmetry and the triaxiality arising from the introduction of cubic terms into the IBA Hamiltonian. Various observables will be inspected in order both to determine their sensitivity to these two structural features and to explore empirical ways of distinguishing which origin of asymmetry applies in any given nucleus. 16 references

  2. IBA: The interest based approach for analyzing Fenofibrates

    International Nuclear Information System (INIS)

    Younes, G; Saad, I; Zahraman, K; Nsouli, B; Bejjani, A; Mahmoud, R; El-Yazbi, F

    2008-01-01

    Fenofibrate, an antihyperlipidemic drug, has been widely used as a lipid regulating agent, indicated as adjunctive therapy to diet to reduce elevated LDL-C, Total-C, Triglycerides and Apo B, and to increase HDL-C in adult patients with primary hypercholesterolemia or mixed dyslipidemia. A fast and precise method for the determination of fenofibrates was highly desirable to support formulation screening and quality control. An Ion Beam Analysis (IBA) technique method was developed for the drug quantification through the determination of the heteroatoms present within the drug molecular formula. In comparison with the other wet chemical techniques, IBA technique has the advantage of being rapid; the time needed for the analysis is very short, in minutes range and it is applied on the pharmaceutical preparation in its solid form without any previous dissolution steps. In this work, ion beam analysis was applied on an antihyperlipidemic drug Fenofibrate where it contains a Cl atom which is considered as heavy atom quantified by particle induced X-ray emission PIXE technique. The obtained results were found to be in good agreement with the labeled concentration and with those obtained using UV spectroscopic technique.(author)

  3. IBA: The interest based approach for analyzing Fenofibrates

    Energy Technology Data Exchange (ETDEWEB)

    Younes, G; Saad, I [Beirut Arab University, Faculty of Science, Chemistry Department, Beirut (Lebanon); Zahraman, K; Nsouli, B; Bejjani, A [Lebanese Atomic Energy Commission, National Council for Scientific Research, Beirut (Lebanon); Mahmoud, R; El-Yazbi, F [Beirut Arab University, Faculty of Pharmacy, Department of Pharmaceutical and Analytical Chemistry, Beirut, (Lebanon)

    2008-07-01

    Fenofibrate, an antihyperlipidemic drug, has been widely used as a lipid regulating agent, indicated as adjunctive therapy to diet to reduce elevated LDL-C, Total-C, Triglycerides and Apo B, and to increase HDL-C in adult patients with primary hypercholesterolemia or mixed dyslipidemia. A fast and precise method for the determination of fenofibrates was highly desirable to support formulation screening and quality control. An Ion Beam Analysis (IBA) technique method was developed for the drug quantification through the determination of the heteroatoms present within the drug molecular formula. In comparison with the other wet chemical techniques, IBA technique has the advantage of being rapid; the time needed for the analysis is very short, in minutes range and it is applied on the pharmaceutical preparation in its solid form without any previous dissolution steps. In this work, ion beam analysis was applied on an antihyperlipidemic drug Fenofibrate where it contains a Cl atom which is considered as heavy atom quantified by particle induced X-ray emission PIXE technique. The obtained results were found to be in good agreement with the labeled concentration and with those obtained using UV spectroscopic technique.(author)

  4. Determination of the angular dependence of the detector matrix Matrix X-evolution of IBA; Determinacion de la dependencia angular del detector matricicial Matrix-X-evolution de IBA

    Energy Technology Data Exchange (ETDEWEB)

    Mateos, J. C.; Luis, F. J.; Sanchez, G.; Herrados, M.

    2011-07-01

    The objective of this work consists in determining the correction for the angular dependence of the detector-Evolution Matrix x matrix (IBA, Germany), when used in the multi cube dummy (IBA, Germany), verification of treatment VMAT IMRT, using the software OP'IMRT (IBA, Germany).

  5. Progress report of the innovated KIST ion beam facility

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Joonkon; Eliades, John A.; Yu, Byung-Yong; Lim, Weon Cheol; Chae, Keun Hwa; Song, Jonghan, E-mail: jonghansong@gmail.com

    2017-01-15

    The Korea Institute of Science and Technology (KIST, Seoul, Republic of (S.) Korea) ion beam facility consists of three electrostatic accelerators: a 400 kV single ended ion implanter, a 2 MV tandem accelerator system and a 6 MV tandem accelerator system. The 400 kV and 6 MV systems were purchased from High Voltage Engineering Europa (HVEE, Netherlands) and commissioned in 2013, while the 2 MV system was purchased from National Electrostatics Corporation (NEC, USA) in 1995. These systems are used to provide traditional ion beam analysis (IBA), isotope ratio analysis (ex. accelerator mass spectrometry, AMS), and ion implantation/irradiation for domestic industrial and academic users. The main facility is the 6 MV HVEE Tandetron system that has an AMS line currently used for {sup 10}Be, {sup 14}C, {sup 26}Al, {sup 36} Cl, {sup 41}Ca and {sup 129}I analyses, and three lines for IBA that are under construction. Here, these systems are introduced with their specifications and initial performance results.

  6. Effects of humidity level and IBA dose application on the softwood ...

    African Journals Online (AJOL)

    IBA) doses on softwood top cuttings of two black mulberry (Types 1 and 2) and one white mulberry (Type 3) types were studied. Cuttings were taken from early June (14 Haziran) and applied to the different IBA doses (0, 1000, 2000, 3000 and ...

  7. Selection of the best consultant for SAP ERP project using combined AHP-IBA approach

    Directory of Open Access Journals (Sweden)

    Martinović Nataša

    2014-01-01

    Full Text Available In this paper we propose a combined AHP-IBA model for selecting the best SAP consultant for an SAP ERP project. The goal of the SAP Project Manager is to choose the best consultant, the one who is able to implement standard SAP functionalities with quality and on time. When making a decision on the basis of multiple criteria, the traditional Analytic Hierarchy Process (AHP method does not take into account the fact that attributes may correlate, assuming that there are no dependencies between them. However, the dependencies of the attributes can often be used to model important knowledge for multiple criteria decision analysis. We propose an extension to the traditional AHP method by applying Interpolative realization of Boolean algebra (IBA, using AHP to determine the criteria weights, and IBA to model the logical interactions among criteria. The research conducted on ERP consultant selection suggests that the decision making process is modelled more accurately if logical interactions between attributes are modelled before applying AHP.

  8. IBA studies of helium mobility in nuclear materials revisited

    Energy Technology Data Exchange (ETDEWEB)

    Trocellier, P., E-mail: patrick.trocellier@cea.fr [CEA, DEN, Service de Recherches de Métallurgie Physique, Laboratoire JANNUS, F-91191 Gif-sur-Yvette (France); Agarwal, S.; Miro, S. [CEA, DEN, Service de Recherches de Métallurgie Physique, Laboratoire JANNUS, F-91191 Gif-sur-Yvette (France); Vaubaillon, S. [CEA, DEN, Service de Recherches de Métallurgie Physique, Laboratoire JANNUS, F-91191 Gif-sur-Yvette (France); CEA, INSTN, UEPTN, F-91191 Gif-sur-Yvette (France); Leprêtre, F.; Serruys, Y. [CEA, DEN, Service de Recherches de Métallurgie Physique, Laboratoire JANNUS, F-91191 Gif-sur-Yvette (France)

    2015-12-15

    The aim of this paper is to point out and to discuss some features extracted from the study of helium migration in nuclear materials performed during the last fifteen years using ion beam analysis (IBA) measurements. The first part of this paper is devoted to a brief description of the two main IBA methods used, i.e. deuteron induced nuclear reaction for {sup 3}He depth profiling and high-energy heavy-ion induced elastic recoil detection analysis for {sup 4}He measurement. In the second part, we provide an overview of the different studies carried out on model nuclear waste matrices and model nuclear reactor structure materials in order to illustrate and discuss specific results in terms of key influence parameters in relation with thermal or radiation activated migration of helium. Finally, we show that among the key parameters we have investigated as able to influence the height of the helium migration barrier, the following can be considered as pertinent: the experimental conditions used to introduce helium (implanted ion energy and implantation fluence), the grain size of the matrix, the lattice cell volume, the Young's modulus, the ionicity degree of the chemical bond between the transition metal atom M and the non-metal atom X, and the width of the band gap.

  9. Effect of indole-3-butyric acid (IBA) on in vitro root induction in ...

    African Journals Online (AJOL)

    Root induction pre-developed in vitro plantlets of orchid was carried out using indole-3-butyric acid (IBA) (0, 0.5, 1.0, 1.5, 2.0, 2.5 and 3 mM) on basal Murashige and Skoog (MS) medium. Among the concentrations of IBA, the number of roots per plantlet with 1 mM IBA was found to be the highest (2.25 roots per plantlet) ...

  10. Nuclear reaction data for IBA applications to cultural heritage diagnostics

    Energy Technology Data Exchange (ETDEWEB)

    Maino, G.; Menapace, E. [Bologna Univ., ENEA (Italy)

    2008-07-01

    Main aspects are discussed concerning nuclear reaction cross-sections for PIXE and PIGE (Particle Induced Gamma-ray Emission) analyses, especially referring to cultural heritage diagnostics, within the framework of ion beam analysis (IBA) methods, also reviewing recent results from international Conferences on Nuclear Data for Science and Technology and from NEANSC meetings and IAEA initiatives on the matter.To sum up this work, it is then worth remarking the following items: IBA techniques are powerful tools to derive unique information as for corrosion, degradation and, generally, conservation conditions of materials. Careful analyses of specific systems require accurate evaluations and establishment of complete databases, in particular for stopping powers and relevant cross sections. The physical parameters to be accurately determined are, therefore, nuclear reaction cross sections of importance for NRA analysis of light elements and stopping powers and ranges of light and heavy ions in various matrices. Light elements (H, Li, B, C, N, O, etc.) play an important role as constituents of many important organic as well inorganic materials in historical and artistic objects. To a large extent these materials occur in the near-surface area of a material with altered or degraded composition.

  11. Nuclear reaction data for IBA applications to cultural heritage diagnostics

    International Nuclear Information System (INIS)

    Maino, G.; Menapace, E.

    2008-01-01

    Main aspects are discussed concerning nuclear reaction cross-sections for PIXE and PIGE (Particle Induced Gamma-ray Emission) analyses, especially referring to cultural heritage diagnostics, within the framework of ion beam analysis (IBA) methods, also reviewing recent results from international Conferences on Nuclear Data for Science and Technology and from NEANSC meetings and IAEA initiatives on the matter.To sum up this work, it is then worth remarking the following items: IBA techniques are powerful tools to derive unique information as for corrosion, degradation and, generally, conservation conditions of materials. Careful analyses of specific systems require accurate evaluations and establishment of complete databases, in particular for stopping powers and relevant cross sections. The physical parameters to be accurately determined are, therefore, nuclear reaction cross sections of importance for NRA analysis of light elements and stopping powers and ranges of light and heavy ions in various matrices. Light elements (H, Li, B, C, N, O, etc.) play an important role as constituents of many important organic as well inorganic materials in historical and artistic objects. To a large extent these materials occur in the near-surface area of a material with altered or degraded composition

  12. Rasadnik Čibača (1911-1932

    Directory of Open Access Journals (Sweden)

    Benić-Penava, Marija

    2017-10-01

    Full Text Available Based on archival material and relevant literature, this article traces the history of the Čibača Plant Nursery from its establishment in 1911 to 1932, when it was closed down. The initial purpose of setting up a nursery in Čibača, 7 km east of Dubrovnik, was to combat the spreading of grape vine disease in southern Dalmatia by producing American vine rootstocks. The Nursery’s original activity later also included the cultivation of Mediterranean plants—olives, figs, carob beans, oranges, lemons, ornamental plants and aromatic herbs. In addition, the Nursery promoted other agricultural activities, such as apiculture and sericulture, as well as the growth of tansy. From 1927 onwards, the Nursery organised agrarian courses which, unfortunately, the people ge-nerally attended only to fulfil the necessary qualifications in order to obtain the USA immigration visa. Following the initial success during Austrian rule, in the interwar Yugosla-via the Nursery stagnated due mainly to unprofessional management and poor financial support. A disease caused by Bacterium tumefaciens, coupled by political intereference in the Nursery’s operation resulted in 1932 in its closing down, the activities being relocated to Toplica near Bar in Montenegro. Despite the mentioned flaws, diversified activities of the Nursery in Čibača no doubt contributed to the agriculture of the Dubrovnik region and economic development of southern Croatia.

  13. Aplicação de IBA para o enraizamento de miniestacas de Eucalyptus benthamii Maiden & Cambage x Eucalyptus dunnii Maiden = IBA application for rooting of Eucalyptus benthamii Maiden and Cambage x Eucalyptus dunnii Maiden minicuttings

    Directory of Open Access Journals (Sweden)

    Gilvano Ebling Brondani

    2010-10-01

    Full Text Available O Eucalyptus apresenta grande importância no setor florestal e muitos avanços na área do melhoramento foram conquistados com o advento da biotecnologia. Contudo, alguns genótipos promissores ainda não possuem protocolos de multiplicação com técnicas de clonagem, como a miniestaquia. Objetivou-se avaliar concentrações de IBA na sobrevivência, enraizamento e vigor vegetativo de miniestacas de E. benthamii x E. dunnii, com a determinação da dose de máxima eficiência técnica. Minicepas dos clones H12, H19 e H20 foram manejadas em minijardim clonal em sistema semi-hidropônico. Para o enraizamento, mergulhou-se a porção basal da miniestaca em soluções hidroalcoólicas, cujas concentrações foram: 0, 2.000, 4.000, 6.000 e 8.000 mg L-1 de IBA. O experimento foi conduzido no delineamento inteiramente casualizado, sendo constituído por três clones e cinco concentrações de IBA, com cinco repetições, contendo dez miniestacas por repetição. O IBA influenciou positivamente os processos rizogênicos das miniestacas com resposta diferenciada entre os clones, a qual variou de 30,32 a 55,45% de enraizamento. Para os clones H12 e H19, os incrementos positivos ocorreram até a maiorconcentração de IBA. Contudo, a faixa situada entre os tratamentos de 4.000 e 6.000 mg L-1 de IBA promoveu os melhores resultados de enraizamento para o clone H20. Eucalyptus has great importance in the forestry sector and many advances in the area of improvement have been achieved with the advent of biotechnological techniques. However, some promising genotypes still do not have multiplication protocols with cloning techniques, such as minicutting. The study aimed to evaluate IBA concentrations for survival, rooting and vegetative vigor of E. benthamii x E. dunnii minicuttings, and determine the maximum technical efficiency dose. Ministumps H12, H19 and H20 clones were cultivated in a clonal minigarden under a semi-hydroponic system. For rooting, the

  14. Rooting success using IBA auxin on endangered Leucadendron ...

    African Journals Online (AJOL)

    STORAGESEVER

    2008-10-06

    Oct 6, 2008 ... The bark and polystyrene medium supplied with zero IBA had the ... L. laxum can speed up the replacement of plants on damaged and reclaimed land and also increase produc- tion of cut ..... Propagating South African trees.

  15. The ANTARES accelerator: a facility for environmental monitoring and materials characterisation

    International Nuclear Information System (INIS)

    Tuniz, C.

    1997-01-01

    An analytical facility for Accelerator Mass Spectrometry (AMS) and Ion Beam Analysis (IBA) has been under development since 1989 on the 8-MV tandem accelerator ANTARES at the Lucas Heights Science and Technology Centre. Three beamlines are presently dedicated to the AMS analysis of long-lived radionuclides and one is used for the study of multilayered semiconductor structures by heavy ion recoil spectrometry. Having accomplished the task of transforming the old nuclear physics accelerator from Rutgers University into a world-class analytical facility, ANSTO scientists are now promoting research projects based on the capability of the ANTARES instruments. New instruments are being constructed on the ANTARES accelerator for future programs in environmental monitoring, safeguards, nuclear waste disposal and applications in advanced materials. A new AMS beamline has been designed that is expected to be capable of measuring rare heavy radionuclides, such as 236 U, 229 , 230T h and 244 Pu, in natural samples with ultra-high sensitivity. A novel, heavy ion microprobe will allow IBA of surfaces with a spatial resolution of 10 μm for high-energy ions (20-100 MeV) from chlorine to iodine. These instruments are complementary to other advanced analytical tools developed by ANSTO, such as the synchrotron radiation beamline at the Australian National Beamline Facility

  16. Rooting success using IBA auxin on endangered Leucadendron ...

    African Journals Online (AJOL)

    Leucadendron laxum (Marsh rose Leucadendron) was tested for its rooting ability as an endangered plant species for reintroduction into the natural habitat, using IBA liquid hormone preparations and four growth media. The treatments included a control, 500, 1000, 2000 and 4000 ppm concentrations. Four growth media ...

  17. Genetic recombination and Cryptosporidium hominis virulent subtype IbA10G2.

    Science.gov (United States)

    Li, Na; Xiao, Lihua; Cama, Vitaliano A; Ortega, Ynes; Gilman, Robert H; Guo, Meijin; Feng, Yaoyu

    2013-10-01

    Little is known about the emergence and spread of virulent subtypes of Cryptosporidium hominis, the predominant species responsible for human cryptosporidiosis. We conducted sequence analyses of 32 genetic loci of 53 C. hominis specimens isolated from a longitudinally followed cohort of children living in a small community. We identified by linkage disequilibrium and recombination analyses only limited genetic recombination, which occurred exclusively within the 60-kDa glycoprotein gene subtype IbA10G2, a predominant subtype for outbreaks in industrialized nations and a virulent subtype in the study community. Intensive transmission of virulent subtype IbA10G2 in the study area might have resulted in genetic recombination with other subtypes. Moreover, we identified selection for IbA10G2 at a 129-kb region around the 60-kDa glycoprotein gene in chromosome 6. These findings improve our understanding of the origin and evolution of C. hominis subtypes and the spread of virulent subtypes.

  18. Micro-IBA analysis of Au/Si eutectic “crop-circles”

    Energy Technology Data Exchange (ETDEWEB)

    Amato, Giampiero [The Quantum Research Lab, INRiM, Strada delle Cacce 91, 10135 Torino (Italy); Battiato, Alfio [Physics Department, NIS Research Centre and CNISM, University of Torino, via P. Giuria 1, 10125 Torino (Italy); Croin, Luca [The Quantum Research Lab, INRiM, Strada delle Cacce 91, 10135 Torino (Italy); Department of Applied Science and Technology, Politecnico di Torino, Corso Duca degli Abruzzi 24, 10129 Torino (Italy); Jaksic, Milko; Siketic, Zdravko [Department for Experimental Physics, Ruđer Bošković Institute, P.O. Box 180, 10002 Zagreb (Croatia); Vignolo, Umberto [Physics Department, NIS Research Centre and CNISM, University of Torino, via P. Giuria 1, 10125 Torino (Italy); Vittone, Ettore, E-mail: ettore.vittone@unito.it [Physics Department, NIS Research Centre and CNISM, University of Torino, via P. Giuria 1, 10125 Torino (Italy)

    2015-04-01

    Highlights: •Gold “crop circles” after annealing Au thin films deposited onto native silicon oxide. •Morphological and IBA analysis confirms the model proposed by Matthews et al. [1]. •The shape of the Au central polygon is determined by the Si orientation. -- Abstract: When a thin gold layer is deposited onto the native oxide of a silicon wafer and is annealed at temperatures greater than 600 °C, peculiar circular features, few micrometers in diameter, with a regular polygon at the centre of each circle, reminiscent of so called “alien” crop circles, can be observed. A model has been recently proposed in Matthews et al. [1], where the formation of such circular structures is attributed to the interdiffusion of gold and silicon through holes in the native oxide induced by the weakening of the amorphous silica matrix occurring during the annealing process. The rupture of the liquid Au/Si eutectic disc surrounding the pinhole in the oxide causes the debris to be pulled to the edges of the disk, forming Au droplets around it and leaving an empty zone of bare silicon oxide. In this paper, we present a morphological study and a RBS/PIXE analyses of these circular structures, carried out by scanning electron microscopy and by 4 MeV C microbeam, respectively. The results confirm the depletion of gold in the denuded circular zones, and the presence of gold droplets in the centers, which can be attributed to the Au segregation occurring during the cooling stage.

  19. IBA for the plastics industry. a brief investigation

    International Nuclear Information System (INIS)

    Vickridge, I.C.; Whineray, S.

    1994-01-01

    As part of an NSOF programme, GNS has developed a small capability for Ion Beam Analysis of polymers, and has investigated the possibilities applying these analytic tools to polymer problems in New Zealand. In the first part of the report, the basis of the IBA method is described, together with experimental measurements of polymer mixing made with the 3 MV KN Van de Graaff accelerator of the Institute. In the second part, reports on a series of visits to industrial plants and other organisations involved in plastics manufacturing and recycling are given. Finally, we draw the conclusion that Ion Beam Analysis should play an important role in future polymer research in New Zealand, but that Industry funding for such research seems unlikely at present. In the meantime, it is proposed that GNS should make a strategic investment by maintaining a small polymer project as a framework within which to maintain contact with New Zealand's polymer research community. (authors) 9 refs., 4 figs

  20. Occupational radiation exposure at the self-shielded IBA CYCLONE 10/5, cyclotron of the Austin and Repatriation Medical Centre, Melbourne, Australia

    International Nuclear Information System (INIS)

    Tochon-Danguy, H.; Sachinidis, J.I.; U, P.; Egan, G.; Mukherjee, B.

    1999-01-01

    A series of health physics measurements was carried out at the IBA CYCLONE 10/5 Medical Cyclotron of the Austin and Repatriation Medical Centre, Melbourne. The neutron attenuation factor of the cyclotron shielding was estimated using the Superheated Bubble dosimeters. The neutron and gamma dose rates at various public access and radiation worker's area in the vicinity of the cyclotron facility were evaluated during the 11 C, 18 F, 13 N and 15 O production conditions. (authors)

  1. 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.

    1994-12-31

    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.

  2. 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.

  3. Overview of experimental tests of the IBA

    International Nuclear Information System (INIS)

    Casten, R.F.

    1980-01-01

    A broad overview is presented of the principal tests to date of the IBA, or both even and odd nuclei, and including the evidence concerning the possible existence of the recently proposed supersymmetries. Although some details are presented, the aim is rather to survey the principal characteristics of the model, to assess the overall quality and extent of the agreement with experiment, and to indicate where further testing would be most useful

  4. The new IBA self-shielded dynamitron accelerator for industrial applications

    International Nuclear Information System (INIS)

    Galloway, R.A.; DeNeuter, S.; Lisanti, T.F.; Cleland, M.R.

    2004-01-01

    Radiation Dynamics Inc. (RDI), currently a member of the IBA Group (Ion Beam Applications based Louvain-la-Neuve, Belgium), has been supplying accelerators since its founding in 1958. These systems supplied for both industrial processing and research application for electrons and ions have proven to be reliable and robust. Today's demands in the industrial sector have driven the design and development of a new version of our Dynamitron [reg] . This new system, envisioned to operate at electron energies up to 1.5 MeV, in many cases can be supplied with integral shielding providing a small footprint requirement for placement in a facility. In the majority of these lower energy applications this allows the appropriate material handling system to be installed inside the steel radiation enclosure. Designed to deliver beam power outputs as high as 100 kW, this new system is capable of servicing the high throughput demands of today's manufacturing lines. Still retaining the positive aspects of the industrially proven Dynamitron system, this compact system can be tailored to meet a variety of in-line or off-line processing applications

  5. Effect of different concentrations of indole butyric acid (IBA) and age of shoot on air layering of mango (Mangifera indica Linn.)

    International Nuclear Information System (INIS)

    Naz, S.; Aslam, M.

    2003-01-01

    The experiment was conducted at Faiz-e-Chamman Mango Orchard, Khanewal Road, Multan. The research was conducted to standardize the method of air layering in mango under climatic conditions of Multan. Different concentrations of IBA, 1000, 2000, 3000, 4000, 5000 ppm and control (0,000 ppm), were applied on one, two and three years old shoots of mango variety-Sindhri. The data were collected on number of roots and length of roots. The results showed maximum number of roots in two years old shoot treated with IBA concentration at the rate of 2000 ppm, whereas one year old shoot failed to produce roots with the application of different concentrations of IBA except 2000 ppm IBA concentration. There were no significant differences in length of roots among shoots treated with IBA concentrations of 1000, 2000, 3000 ppm and control, which produced maximum length of roots. Shoots treated with IBA concentration of 5000 ppm resulted in minimum length of roots.(author)

  6. The Escherichia coli BolA Protein IbaG Forms a Histidine-Ligated [2Fe-2S]-Bridged Complex with Grx4.

    Science.gov (United States)

    Dlouhy, Adrienne C; Li, Haoran; Albetel, Angela-Nadia; Zhang, Bo; Mapolelo, Daphne T; Randeniya, Sajini; Holland, Ashley A; Johnson, Michael K; Outten, Caryn E

    2016-12-13

    Two ubiquitous protein families have emerged as key players in iron metabolism, the CGFS-type monothiol glutaredoxins (Grxs) and the BolA proteins. Monothiol Grxs and BolA proteins form heterocomplexes that have been implicated in Fe-S cluster assembly and trafficking. The Escherichia coli genome encodes members of both of these proteins families, namely, the monothiol glutaredoxin Grx4 and two BolA family proteins, BolA and IbaG. Previous work has demonstrated that E. coli Grx4 and BolA interact as both apo and [2Fe-2S]-bridged heterodimers that are spectroscopically distinct from [2Fe-2S]-bridged Grx4 homodimers. However, the physical and functional interactions between Grx4 and IbaG are uncharacterized. Here we show that co-expression of Grx4 with IbaG yields a [2Fe-2S]-bridged Grx4-IbaG heterodimer. In vitro interaction studies indicate that IbaG binds the [2Fe-2S] Grx4 homodimer to form apo Grx4-IbaG heterodimer as well as the [2Fe-2S] Grx4-IbaG heterodimer, altering the cluster stability and coordination environment. Additionally, spectroscopic and mutagenesis studies provide evidence that IbaG ligates the Fe-S cluster via the conserved histidine that is present in all BolA proteins and by a second conserved histidine that is present in the H/C loop of two of the four classes of BolA proteins. These results suggest that IbaG may function in Fe-S cluster assembly and trafficking in E. coli as demonstrated for other BolA homologues that interact with monothiol Grxs.

  7. IBA of ZrO2:Yb/Si thin films produced by the spray pyrolysis method

    International Nuclear Information System (INIS)

    Andrade, E.; Ramirez, E.B.; Alonso, J.C.; Rocha, M.F.

    2008-01-01

    A spray pyrolysis method was used to produce thin films of ZrO 2 doped with different Yb concentrations on Si(1 0 0). The films of these ionic semiconductors have potential applications as solid electrolytes in modern ceramic fuel cells of second generation. The determination of the atomic composition of the films is very important because it strongly affects the chemical and thermal stability, as well as electrical properties of the films. A combination of two Ion Beam Analysis (IBA) methods was applied to obtain the atomic composition of the films. A nuclear reaction analysis (NRA) method using a low energy deuterium beam was applied to measure the oxygen content of the films. Heavy ion Rutherford backscattering (HI-RBS) method using a 12 C 3+ beam was applied to measure the Yb and Zr atomic profiles of the samples. X-ray diffraction (XRD) and ellipsometry were also employed to determine structural properties and refractive index of the films, respectively. The IBA, XRD and the ellipsometry supply a wide range of information about the film layers, which can be used for qualification as well as for feedback to the films production

  8. Conserving the grassland Important Bird Areas (IBAs) of southern South America: Argentina, Uruguay, Paraguay, and Brazil

    Science.gov (United States)

    Adrian S. Di Giacomo; Santiago Krapovickas

    2005-01-01

    In the southern part of South America, knowledge about bird species distribution is still not used as a tool for land use planning and conservation priority-setting. BirdLife International’s Important Bird Areas (IBA) Program is an appropriate vehicle for analyzing existing information about birds, and to generate new data where necessary. IBA inventories...

  9. Effect of Humic Acid on As Redox Transformation and Kinetic Adsorption onto Iron Oxide Based Adsorbent (IBA

    Directory of Open Access Journals (Sweden)

    Hoda Fakour

    2014-10-01

    Full Text Available Due to the importance of adsorption kinetics and redox transformation of arsenic (As during the adsorption process, the present study elucidated natural organic matter (NOM effects on As adsorption-desorption kinetics and speciation transformation. The experimental procedures were conducted by examining interactions of arsenate and arsenite with different concentrations of humic acid (HA as a model representative of NOM, in the presence of iron oxide based adsorbent (IBA, as a model solid surface in three environmentally relevant conditions, including the simultaneous adsorption of both As and HA onto IBA, HA adsorption onto As-presorbed IBA, and As adsorption onto HA-presorbed IBA. Experimental adsorption-desorption data were all fitted by original and modified Lagergren pseudo-first and -second order adsorption kinetic models, respectively. Weber’s intraparticle diffusion was also used to gain insight into the mechanisms and rate controlling steps, which the results suggested that intraparticle diffusion of As species onto IBA is the main rate-controlling step. Different concentrations of HA mediated the redox transformation of As species, with a higher oxidation ability than reduction. The overall results indicated the significant effect of organic matter on the adsorption kinetics and redox transformation of As species, and consequently, the fate, transport and mobility of As in different environmentally relevant conditions.

  10. Avaliação do enraizamento de estacas de crisântemo (Chrysanthemum morifolium L. cv. white Reagan 606 tratadas com ácido indolbutírico (IBA Rooting evaluation in Chrysanthemum morifolium cv. white Reagan 606 stem cuttings as affected by indolbutyric acid (IBA

    Directory of Open Access Journals (Sweden)

    F.L. Cuquel

    1992-01-01

    Full Text Available Avaliou-se o efeito de doses crescentes do ácido indolbutírico (IBA e de diferentes tempos de imersão no enraizamento de estacas de Chrysanthemum morifolium cv. White Reagan 606. O fator doses foi aplicado em quatro níveis: 0, 500, 1000 e 1500 ppm de IBA e o fator tempo em três níveis: 5s, 1h e 2h. O delineamento utilizado foi o de blocos completos casualizados com parcelas subdivididas, onde as dosagens de IBA foram aplicadas como tratamento principal. O experimento foi instalado em caixas de isopor, em casa de vegetação sob nebulização, tendo vermiculita como substrato. O momento adequado para o transplante foi avaliado através da leitura de uma repetição adicional utilizada como controle. Obteve-se enraizamento em todas as combinações de tratamento, mesma na ausência de IBA. De maneira geral o tratamento rápido tende a ser mais facilmente eficiente quando combinado com as maiores dosagens, enquanto os tratamentos mais demorados com as menores dosagens.The effect of rising concentrations of indolbutyric acid (IBA solutions was evaluated with different exposition times in stem cuttings of Chrysanthemum morifolium cv. White Reagan 606. The applied concentrations were 0,500,1000 and 1500 ppm of IBA during 5s, 1h and 2h, in a randomized complete split-plot block design, with IBA concentrations as main treatment. The experiment was installed in styrofoam trays in a green-house with a mist device and vermiculite as substrate. Transplanting time was determined by an additional block. All treatments induced rooting even in the absence of IBA. In a general sense the fastest treatments tended to be the more efficient when combined with higher concentrations.

  11. IBA in the museum

    International Nuclear Information System (INIS)

    Menu, M.

    1990-01-01

    The Research Laboratory of the Museums of France (LRMF) has been a part of the Louvre Museum since 1931. At the beginning, paintings were only examined by means of optical microscopy, under UV or IR light, or by X-ray radiography. With the development of archaeometry in the early 1960s, different spectrometric techniques have been applied to the analysis of works of art and archaeological objects: UV spectrometry, XRF, and even SEM coupled to an X-ray Si(Li) detector. Crystalline objects were investigated with XRD and Fourier transform infrared spectrometry (FTIR); organic matter with gas chromatography, FTIR, UV and visible spectrophotometry. Thus the principal aim of the LRMF is to characterize the materials and the techniques involved in the creation of art and archaeological objects, for example, methods of production, provenance studies, authentication, and conservation. (The problem of dating is for the time being only a minor subject of research at the LRMF). Because of the valuable nature of such objects, nondestructive methods of analysis have been developed, and consequently the results have to be more and more accurate to answer the questions put to us by the art historian. Moreover, the works of art must stay inside the security area of the museum. Therefore, it was decided in 1982 to install within the Louvre an accelerator dedicated solely to museum problems. The installation of AGLAE, begun in 1984, has now been completed. The accelerator system, a Pelletron 6SDH2 from NEC, was rendered operational in June 1988. A general consensus with regard to the applications of the ion beam techniques in art and archaeology was arrived at during the International Workshop held in Pont-a-Mousson, France in 1985, which brought together museum scientists as well as IBA physicists who had applied these techniques to archaeology, geology and metallurgy. (orig./WL)

  12. Pax6 interacts with Iba1 and shows age-associated alterations in brain of aging mice.

    Science.gov (United States)

    Maurya, Shashank Kumar; Mishra, Rajnikant

    2017-07-01

    The Pax6, a transcriptional regulator and multifunctional protein, has been found critical for neurogenesis, neuro-degeneration, mental retardation, neuroendocrine tumors, glioblastoma and astrocytomas. The age-associated alteration in the expression of Pax6 in neuron and glia has also been observed in the immunologically privileged brain. Therefore, it is presumed that Pax6 may modulate brain immunity by activation of microglia either directly interacting with genes or proteins of microglia or indirectly though inflammation associated with neurodegeneration. This report describes evaluation of expression, co-localization and interactions of Pax6 with Ionized binding protein1 (Iba1) in brain of aging mice by Immunohistochemistry, Chromatin Immuno-precipitation (ChIP) and Co-immunoprecipitation (Co-IP), respectively. The co-localization of Pax6 with Iba1 was observed in the cerebellum, cerebral cortex, hippocampus, midbrain and olfactory lobe. The Pax6 and Iba1 also interact physically. The age-dependent alteration in their expression and co-localization were also observed in mice. Results indicate Pax6-dependent activities of Iba1 in the remodelling of microglia during immunological surveillance of the brain. Copyright © 2017 Elsevier B.V. All rights reserved.

  13. Characterization and performances of a monitoring ionization chamber dedicated to IBA-universal irradiation head for Pencil Beam Scanning

    Energy Technology Data Exchange (ETDEWEB)

    Courtois, C. [LPC (IN2P3-ENSICAEN-UNICAEN), 6 Boulevard Maréchal Juin, 14050 Caen (France); Boissonnat, G., E-mail: boissonnat@lpccaen.in2p3.fr [LPC (IN2P3-ENSICAEN-UNICAEN), 6 Boulevard Maréchal Juin, 14050 Caen (France); Brusasco, C. [IBA, 3 Chemin du Cyclotron, 31348 Louvain-la-Neuve (Belgium); Colin, J.; Cussol, D.; Fontbonne, J.M. [LPC (IN2P3-ENSICAEN-UNICAEN), 6 Boulevard Maréchal Juin, 14050 Caen (France); Marchand, B.; Mertens, T.; Neuter, S. de [IBA, 3 Chemin du Cyclotron, 31348 Louvain-la-Neuve (Belgium); Peronnel, J. [LPC (IN2P3-ENSICAEN-UNICAEN), 6 Boulevard Maréchal Juin, 14050 Caen (France)

    2014-02-01

    Every radiotherapy center has to be equipped with real-time beam monitoring devices. In 2008, we developed an ionization chamber in collaboration with the IBA (Ion Beam Applications) company. This monitoring device called IC2/3 was developed to be used in IBA universal irradiation head for Pencil Beam Scanning (PBS). Here we present the characterization of the IC2/3 monitor in the energy and flux ranges used in protontherapy. The equipment has been tested with an IBA cyclotron able to deliver proton beams from 70 to 230 MeV. This beam monitoring device has been validated and is now installed at the Westdeutsches Protonentherapiezentrum Essen protontherapy center (WPE, Germany). The results obtained in both terms of spatial resolution and dose measurements are at least equal to the initial specifications needed for PBS purposes. The detector measures the dose with a relative uncertainty lower than 1% in the range from 0.5 Gy/min to 8 Gy/min while the spatial resolution is better than 250μm. The technology has been patented and five IC2/3 chambers were delivered to IBA. Nowadays, IBA produces the IC2/3 beam monitoring device as a part of its Proteus 235 product.

  14. Rooting of Mugo pine (Pinus mugo) cuttings as affected by IBA, NAA and planting substrate

    Energy Technology Data Exchange (ETDEWEB)

    Sedaghathoor, S.; Kayghobadi, S.; Tajva, Y.

    2016-07-01

    Aim of the study. The effect of planting substrate and concentrations of indole-3-butyric acid (Ia) and naphthaleneacetic acid (Naca) hormones was studied on the rooting of mugo pine cuttings. Area of study: The research was carried out in Rasht city, Guilan province, Iran. Material and Methods: Both hormones (IBA and NAA) were applied at four concentrations of 0, 1000, 2000 and 4000 mg/l. Planting substrates included sand, perlite, cocopeat, sand + perlite, and sand + cocopeat (1:1). Main results: The highest rooting percentage (55%) was obtained under the trilateral treatment a2b4c1 (sand × 4000 mg/l NAA × 1000 mg/l IBA). Sand + cocopeat was found to be the best rooting substrate. Research highlights: It is recommended to apply sand with 4000 mg/l and 1000mg/l concentration of experimental hormones (NAA and IBA, respectively). (Author)

  15. IBA's state of art Proton Therapy System

    International Nuclear Information System (INIS)

    Ternier, Sonja

    2001-01-01

    Full text: In recent years, IBA has developed a state-of-the-art Proton Therapy System that is currently being implemented at the Northeast Proton Therapy Center in Boston. First patient treatment is predicted for the fourth quarter of 2001. The IBA Proton Therapy System consists of a 230 MeV accelerator (a fixed energy isochronous cyclotron), an Energy Selection System that can decrease the energy down to 70 MeV and up to five treatment rooms. There are two types of treatment rooms. A gantry treatment room in which a patient can be treated from virtually any angle or a fixed horizontal beam line aimed at treatments of the of the head and neck. The system is equipped with a Therapy Control System and a Global Safety Management System. The Integrated Therapy Control System is an integrated system ensuring the control of the treatment sessions through independent but networked therapy control units and, therefore, the control of each equipment subsystem. The integrated safety management system, independent of the Therapy Control System, includes a set of hard-wired safety devices, ensuring the safety of the patient and personnel. The system will be capable of delivering proton treatments in four-treatment modes: Double Scattering, Single Scattering, Wobbling and Pencil Beam Scanning. The presentation will show the most important subsystems and treatment modes capabilities as well as the most recent advances in the technology. (author)

  16. Effects of IAA, IBA, NAA, and GA3 on rooting and morphological features of Melissa officinalis L. stem cuttings.

    Science.gov (United States)

    Sevik, Hakan; Guney, Kerim

    2013-01-01

    This study analyzed the potential of producing Melissa officinalis L. using stem cuttings. Four different hormones (IAA, IBA, NAA, and GA3) were applied to the cuttings, with and without buds, in two doses (1000 mg/L and 5000 mg/L), and after 60 days, 10 morphological characteristics of newly generated plants were detected, and a statistical analysis was carried out. The results of the study show that the cuttings with at least one bud must be used in order to produce M. officinalis using stem cuttings. Even though the auxin group hormones (IAA, IBA, and NAA) do not have an apparent effect on rooting percentage, these hormones were detected to affect the morphological characteristics of the newly generated plants, especially root generation. GA3 application has a considerable effect on stem height.

  17. SigmaCalc recent development and present status of the evaluated cross-sections for IBA

    Energy Technology Data Exchange (ETDEWEB)

    Gurbich, A.F.

    2016-03-15

    A new version of the SigmaCalc Internet site ( (http://sigmacalc.iate.obninsk.ru)) intended to provide evaluated differential cross-sections for spectra simulation is presented. Results of the revision of previously evaluated cross-sections and new evaluations including data for PIGE were made available to the IBA community through a simple interface. New SigmaCalc features allow users to compare evaluated differential cross-sections with the available results of the cross-section measurements taken on-the-fly from the IBANDL database and to validate them against benchmarks. The current status of the evaluated cross-sections for IBA is discussed.

  18. A new ion beam facility based on a 3 MV Tandetron™ at IFIN-HH, Romania

    Science.gov (United States)

    Burducea, I.; Straticiuc, M.; Ghiță, D. G.; Moșu, D. V.; Călinescu, C. I.; Podaru, N. C.; Mous, D. J. W.; Ursu, I.; Zamfir, N. V.

    2015-09-01

    A 3 MV Tandetron™ accelerator system has been installed and commissioned at the "Horia Hulubei" National Institute for Physics and Nuclear Engineering - IFIN-HH, Măgurele, Romania. The main purpose of this machine is to strengthen applied nuclear physics research ongoing in our institute for more than four decades. The accelerator system was developed by High Voltage Engineering Europa B.V. (HVE) and comprises three high energy beam lines. The first beam line is dedicated to ion beam analysis (IBA) techniques: Rutherford Backscattering Spectrometry - RBS, Nuclear Reaction Analysis - NRA, Particle Induced X-ray and γ-ray Emission - PIXE and PIGE and micro-beam experiments - μ-PIXE. The second beam line is dedicated to high energy ion implantation experiments and the third beam line was designed mainly for nuclear cross-sections measurements used in nuclear astrophysics. A unique feature, the first time in operation at an accelerator facility is the Na charge exchange canal (CEC), which is used to obtain high intensity beams of He- of at least 3 μA. The results of the acceptance tests demonstrate the huge potential of this new facility in various fields, from IBA to radiation hardness studies and from medical or environmental applications to astrophysics. The main features of the accelerator are presented in this paper.

  19. Preliminary Study and Improve the Production of Metabolites with Antifungal Activity by A Bacillus Sp Strain IBA 33

    Directory of Open Access Journals (Sweden)

    María Antonieta Gordillo

    2009-01-01

    Full Text Available Bacillus sp strain IBA 33 metabolites, isolated from decaying lemon fruits, were evaluated for the control of pathogenic and non-pathogenic fungi (Penicillium digitatum, Geotrichum candidum, Penicillium expansum, Aspergillus clavatus, Aspergillus flavus, Aspergillus niger, and Fusarium moniliforme. These metabolites were recovered from Landy medium (LM without aminoacids. In order to optimize metabolites production the LM was modified by adding different concentrations and sources of amino acids and carbohydrates at different culture conditions.Bacillus sp strain IBA 33 metabolites efficacy to control fungi were evaluated with in vitro and in vivo assays. A. flavus growth inhibition was 52% with the metabolites of Bacillus sp strain IBA 33 recovered from LM (MBLM in vitro assays. MBLM supplemented with 0.5% glutamic acid, inhibited the growth of P. digitatum, G. candidum, A. clavatus, A. niger and F. moniliforme by 65%, 88.44%, 84%, 34% and 92% respectively. The highest inhibition of P. expansum was 45% with MBLM supplemented with 0.5% aspartic acid. Similar results were obtained in vivo assays. These results showed that Bacillus sp strain IBA 33 metabolites specificity against fungi depended on the composition of the LM.

  20. Preliminary Study and Improve the Production of Metabolites with Antifungal Activity by A Bacillus Sp Strain IBA 33

    Directory of Open Access Journals (Sweden)

    María Antonieta Gordillo

    2009-04-01

    Full Text Available Bacillus sp strain IBA 33 metabolites, isolated from decaying lemon fruits, were evaluated for the control of pathogenic and non-pathogenic fungi (Penicillium digitatum, Geotrichum candidum, Penicillium expansum, Aspergillus clavatus, Aspergillus flavus, Aspergillus niger, and Fusarium moniliforme. These metabolites were recovered from Landy medium (LM without aminoacids. In order to optimize metabolites production the LM was modified by adding different concentrations and sources of amino acids and carbohydrates at different culture conditions. Bacillus sp strain IBA 33 metabolites efficacy to control fungi were evaluated with in vitro and in vivo assays. A. flavus growth inhibition was 52% with the metabolites of Bacillus sp strain IBA 33 recovered from LM (MBLM in vitro assays. MBLM supplemented with 0.5% glutamic acid, inhibited the growth of P. digitatum, G. candidum, A. clavatus, A. niger and F. moniliforme by 65%, 88.44%, 84%, 34% and 92% respectively. The highest inhibition of P. expansum was 45% with MBLM supplemented with 0.5% aspartic acid. Similar results were obtained in vivo assays. These results showed that Bacillus sp strain IBA 33 metabolites specificity against fungi depended on the composition of the LM.

  1. Interaction of IBA and NAA with enzymes in root induction of Crocus ...

    African Journals Online (AJOL)

    PRECIOUS

    2010-01-11

    Jan 11, 2010 ... Key words: Crocus sativus L., saffron, root formation, IBA, NAA. .... square coefficient. ... Interaction of medium and hormone and its effect on mean number of root per ... It is apparent in Table2 that the fluctuations in protein.

  2. the impact of effluent produced from ntak inyang and iba oku

    African Journals Online (AJOL)

    user

    as E.coli and others were also present. Effluents from the abattoir sites were found not to increase the ... animal product go through market and ... In many countries, the slaughter of ... obtained were compared with WHO and ... SAMPLING TECHNIQUE ..... Table 6: Micro-Organisms Isolated from Iba Oku and Ntak Inyang ...

  3. A new IBA-AMS laboratory at the Comenius University in Bratislava (Slovakia)

    Science.gov (United States)

    Povinec, Pavel P.; Masarik, Jozef; Kúš, Peter; Holý, Karol; Ješkovský, Miroslav; Breier, Robert; Staníček, Jaroslav; Šivo, Alexander; Richtáriková, Marta; Kováčik, Andrej; Szarka, Ján; Steier, Peter; Priller, Alfred

    2015-01-01

    A Centre for Nuclear and Accelerator Technologies (CENTA) has been established at the Comenius University in Bratislava comprising of a tandem laboratory designed for Ion Beam Analysis (IBA), Ion Beam Modification (IBM) of materials and Accelerator Mass Spectrometry (AMS). The main equipment of the laboratory, i.e. Alphatross and MC-SNICS ion sources, 3 MV Pelletron tandem accelerator, and analyzers of accelerated ions are described. Optimization of ion beam characteristics for different ion sources with gas and solid targets, for transmission of accelerated ions with different energy and charge state, for different parameters of the high-energy ion analyzers, as well as first AMS results are presented. The scientific program of the CENTA will be devoted mainly to nuclear, environmental, life and material sciences.

  4. MeV ion-beam analysis of optical data storage films

    Science.gov (United States)

    Leavitt, J. A.; Mcintyre, L. C., Jr.; Lin, Z.

    1993-01-01

    Our objectives are threefold: (1) to accurately characterize optical data storage films by MeV ion-beam analysis (IBA) for ODSC collaborators; (2) to develop new and/or improved analysis techniques; and (3) to expand the capabilities of the IBA facility itself. Using H-1(+), He-4(+), and N-15(++) ion beams in the 1.5 MeV to 10 MeV energy range from a 5.5 MV Van de Graaff accelerator, film thickness (in atoms/sq cm), stoichiometry, impurity concentration profiles, and crystalline structure were determined by Rutherford backscattering (RBS), high-energy backscattering, channeling, nuclear reaction analysis (NRA) and proton induced X-ray emission (PIXE). Most of these techniques are discussed in detail in the ODSC Annual Report (February 17, 1987), p. 74. The PIXE technique is briefly discussed in the ODSC Annual Report (March 15, 1991), p. 23.

  5. Sequential activation of microglia and astrocyte cytokine expression precedes increased Iba-1 or GFAP immunoreactivity following systemic immune challenge.

    Science.gov (United States)

    Norden, Diana M; Trojanowski, Paige J; Villanueva, Emmanuel; Navarro, Elisa; Godbout, Jonathan P

    2016-02-01

    Activation of the peripheral immune system elicits a coordinated response from the central nervous system. Key to this immune to brain communication is that glia, microglia, and astrocytes, interpret and propagate inflammatory signals in the brain that influence physiological and behavioral responses. One issue in glial biology is that morphological analysis alone is used to report on glial activation state. Therefore, our objective was to compare behavioral responses after in vivo immune (lipopolysaccharide, LPS) challenge to glial specific mRNA and morphological profiles. Here, LPS challenge induced an immediate but transient sickness response with decreased locomotion and social interaction. Corresponding with active sickness behavior (2-12 h), inflammatory cytokine mRNA expression was elevated in enriched microglia and astrocytes. Although proinflammatory cytokine expression in microglia peaked 2-4 h after LPS, astrocyte cytokine, and chemokine induction was delayed and peaked at 12 h. Morphological alterations in microglia (Iba-1(+)) and astrocytes (GFAP(+)), however, were undetected during this 2-12 h timeframe. Increased Iba-1 immunoreactivity and de-ramified microglia were evident 24 and 48 h after LPS but corresponded to the resolution phase of activation. Morphological alterations in astrocytes were undetected after LPS. Additionally, glial cytokine expression did not correlate with morphology after four repeated LPS injections. In fact, repeated LPS challenge was associated with immune and behavioral tolerance and a less inflammatory microglial profile compared with acute LPS challenge. Overall, induction of glial cytokine expression was sequential, aligned with active sickness behavior, and preceded increased Iba-1 or GFAP immunoreactivity after LPS challenge. © 2015 Wiley Periodicals, Inc.

  6. Effects of some humidity and IBA hormone dose applicatýons on ...

    African Journals Online (AJOL)

    In this study, softwood cuttings were taken from M9 dwarf apple rootstocks in early June. Different indole-3-butyric acid (IBA) concentrations [0 (control), 500, 1500, 2500 and 3500 ppm], different air humidity levels (85 - 90%, 95-100%) and rooting media of perlite effects on rooting capability and root formation of M9 apple ...

  7. PENGARUH PEMBERIAN IBA DAN KOMPOSISI MEDIA TERHADAP PERTUMBUHAN STEK Sansevieria cylindrica var. patula

    Directory of Open Access Journals (Sweden)

    Sesar Fikri Firmansyah

    2014-06-01

    Full Text Available Sansevieria is an ornamental plant commonly known as mother-in-law's tongue, devil's tongue, and snake tongue. It has many functions e.g. uses as medicine, its fiber for the textile industry, and as indoor air pollutants absorber. However, the growth of Sansevieria is slow. Therefore the supply of it seeds in large quantities in the short time was difficult. The use of Plant Growth Regulator (PGR was one solution to accelerate the propagation of Sansevieria leaf cuttings. This study aimed to determine the concentration of IBA and the composition of media to increase the leaf cuttings propagation of Sansevieria cylindrica var. patula. The method was randomized block design with factorials. Factor I was the IBA concentrations comprised of  K0 at 0 ppm, K1 at 50 ppm, K2 at 100 ppm, K3 at 150 ppm, and K4 at 200 ppm. Factor II was the ratio of manure:sand:rice-husk-ash as the growth media, comprised of M1 with 1:1:1 ratio, M2 with 1:2:1 ratio, and M3 with 1:1:2 ratio respectively. Each with three replicates overall was 45 experimental units. The parameters observed were a percentage of propagated cuttings, the number of roots, the longest length of roots, the number of shoots. The results showed the IBA could not increase the growth of cuttings in all media composition; however media compositions could enhance the number of shoots. The effective media composition propagated the cuttings was the M1 a 1:1:1 ratio of manure:sand:rice-husk-ash.

  8. Ion Beam Facilities at the National Centre for Accelerator based Research using a 3 MV Pelletron Accelerator

    Science.gov (United States)

    Trivedi, T.; Patel, Shiv P.; Chandra, P.; Bajpai, P. K.

    A 3.0 MV (Pelletron 9 SDH 4, NEC, USA) low energy ion accelerator has been recently installed as the National Centre for Accelerator based Research (NCAR) at the Department of Pure & Applied Physics, Guru Ghasidas Vishwavidyalaya, Bilaspur, India. The facility is aimed to carried out interdisciplinary researches using ion beams with high current TORVIS (for H, He ions) and SNICS (for heavy ions) ion sources. The facility includes two dedicated beam lines, one for ion beam analysis (IBA) and other for ion implantation/ irradiation corresponding to switching magnet at +20 and -10 degree, respectively. Ions with 60 kV energy are injected into the accelerator tank where after stripping positively charged ions are accelerated up to 29 MeV for Au. The installed ion beam analysis techniques include RBS, PIXE, ERDA and channelling.

  9. Recent development and progress of IBA cyclotrons

    Energy Technology Data Exchange (ETDEWEB)

    Kleeven, W., E-mail: Willem.Kleeven@iba-group.com [Ion Beam Applications s.a. Chemin du Cyclotron 3, Louvain-la-Neuve (Belgium); Abs, M., E-mail: Michel.Abs@iba-group.com [Ion Beam Applications s.a. Chemin du Cyclotron 3, Louvain-la-Neuve (Belgium); Delvaux, J.L., E-mail: Jean-Luc.Delvaux@iba-group.com [Ion Beam Applications s.a. Chemin du Cyclotron 3, Louvain-la-Neuve (Belgium); Forton, E., E-mail: Eric.Forton@iba-group.com [Ion Beam Applications s.a. Chemin du Cyclotron 3, Louvain-la-Neuve (Belgium); Jongen, Y., E-mail: Yves.Jongen@iba-group.com [Ion Beam Applications s.a. Chemin du Cyclotron 3, Louvain-la-Neuve (Belgium); Medeiros Romao, L., E-mail: Luis.MedeirosRomao@iba-group.com [Ion Beam Applications s.a. Chemin du Cyclotron 3, Louvain-la-Neuve (Belgium); Nactergal, B., E-mail: Benoit.Nactergal@iba-group.com [Ion Beam Applications s.a. Chemin du Cyclotron 3, Louvain-la-Neuve (Belgium); Nuttens, V., E-mail: Vincent.Nuttens@iba-group.com [Ion Beam Applications s.a. Chemin du Cyclotron 3, Louvain-la-Neuve (Belgium); Servais, T., E-mail: Thomas.Servais@iba-group.com [Ion Beam Applications s.a. Chemin du Cyclotron 3, Louvain-la-Neuve (Belgium); Vanderlinden, T., E-mail: Thierry.Vanderlinden@iba-group.com [Ion Beam Applications s.a. Chemin du Cyclotron 3, Louvain-la-Neuve (Belgium); Zaremba, S., E-mail: Simon.Zaremba@iba-group.com [Ion Beam Applications s.a. Chemin du Cyclotron 3, Louvain-la-Neuve (Belgium)

    2011-12-15

    Several cyclotron development projects were recently realized by Ion Beam Applications S.A. (IBA). This contribution presents three of them: (i) the intensity enhancement of the Cyclone 30 cyclotron, a machine mainly used for the production of SPECT isotopes. This project is related with the increased demand for {sup 201}Tl because of the shortage of Mo/Tc generators from nuclear reactors, (ii) development of a new versatile multiple-particle K = 30 isotope-production cyclotron (the Cyclone 30XP) being able to accelerate H{sup -}, D{sup -} and also {alpha}-particles. The {alpha}-beam of this cyclotron will allow the production of new therapeutic isotopes (e.g. {sup 211}At) and (iii) commissioning of the Cyclone 70 cyclotron installed for Arronax in France. This machine is similar to the C30XP but provides higher energy (K = 70) and allows research on new types of medical isotopes.

  10. The JANNUS Saclay facility: A new platform for materials irradiation, implantation and ion beam analysis

    Energy Technology Data Exchange (ETDEWEB)

    Pellegrino, S., E-mail: stephanie.pellegrino@cea.fr [CEA, INSTN, UEPTN, Laboratoire JANNUS, F-91191 Gif-sur-Yvette (France); Trocellier, P.; Miro, S.; Serruys, Y.; Bordas, E.; Martin, H. [CEA, DEN, Service de Recherches de Metallurgie Physique, Laboratoire JANNUS, F-91191 Gif-sur-Yvette (France); Chaabane, N.; Vaubaillon, S. [CEA, INSTN, UEPTN, Laboratoire JANNUS, F-91191 Gif-sur-Yvette (France); Gallien, J.P.; Beck, L. [CEA, DEN, Service de Recherches de Metallurgie Physique, Laboratoire JANNUS, F-91191 Gif-sur-Yvette (France)

    2012-02-15

    The third accelerator of the multi-ion irradiation platform JANNUS (Joint Accelerators for Nanosciences and NUclear Simulation), a 6SDH-2 Pelletron from National Electrostatic Corporation, Middleton was installed at Saclay in October 2009. The first triple beam irradiation combining Fe, He and H ion beams has been performed in March 2010. In the first part of this paper, we give a technical description of the triple beam facility, its performances and experimental capabilities. Typically, damage dose up to 100 dpa can be reached in 10 h irradiation with heavy ion beams, with or without simultaneous bombardment by protons, helium-4 ions or any other heavy ion beam. In the second part of this paper, we illustrate some IBA results obtained after irradiation and implantation experiments.

  11. Currents trends in the application of IBA techniques to air pollution source fingerprinting and source apportionment

    International Nuclear Information System (INIS)

    Cohen, David; Stelcer, Ed.; Atanacio, Armand; Crawford, Jagoda

    2013-01-01

    Full text: IBA techniques have been used for many years to characterise fine particle air pollution. This is not new the techniques are well established. Typically 2-3 MeV protons are used to bombard thin filter papers and up to four simultaneous techniques like PIXE, PIGE, RBS and ERDA will be applied to obtain (μg/g) concentrations for elements from hydrogen to lead. Generally low volume samplers are used to sample between 20-30 m 3 of air over a 24 hour period, this together with IBA's sensitivity means that concentrations down to 1 ng/m 3 of air sampled can be readily achieved with only a few minutes of proton irradiation. With these short irradiation times and low sensitivities for a broad range of elements in the periodic table, large numbers of samples can be obtained and analysed very quickly and easily. At ANSTO we have used IBA methods to acquire a database of over 50,000 filters from 85 different sites through Australia and Asia, each filter has been analysed for more than 21 different chemical species. Large databases extending over many years means that modern statistical techniques like positive matrix factorisation (PMF) can be used to define well characterised source fingerprints and source contributions for a range of different fine particle air pollutants. In this paper we will discuss these PMF techniques and show how they identify both natural sources like sea spray and windblown soils as well as anthropogenic sources like automobiles, biomass burning, coal-fired power stations and industrial emissions. These data are particularly useful for Governments, EPA's and managers of pollution to better understanding pollution sources and their relative contributions and hence to better manage air pollution. Current trends are to take these IBA and PMF techniques a step further and to combine them with wind speed and back trajectory data to better pin point and identify emission sources. We show how this is now being applied on both a local

  12. Currents trends in the application of IBA techniques to air pollution source fingerprinting and source apportionment

    Energy Technology Data Exchange (ETDEWEB)

    Cohen, David; Stelcer, Ed.; Atanacio, Armand; Crawford, Jagoda [Australian Nuclear Science and Technology Organisation, Kirrawee DC (Australia)

    2013-07-01

    Full text: IBA techniques have been used for many years to characterise fine particle air pollution. This is not new the techniques are well established. Typically 2-3 MeV protons are used to bombard thin filter papers and up to four simultaneous techniques like PIXE, PIGE, RBS and ERDA will be applied to obtain (μg/g) concentrations for elements from hydrogen to lead. Generally low volume samplers are used to sample between 20-30 m{sup 3} of air over a 24 hour period, this together with IBA's sensitivity means that concentrations down to 1 ng/m{sup 3} of air sampled can be readily achieved with only a few minutes of proton irradiation. With these short irradiation times and low sensitivities for a broad range of elements in the periodic table, large numbers of samples can be obtained and analysed very quickly and easily. At ANSTO we have used IBA methods to acquire a database of over 50,000 filters from 85 different sites through Australia and Asia, each filter has been analysed for more than 21 different chemical species. Large databases extending over many years means that modern statistical techniques like positive matrix factorisation (PMF) can be used to define well characterised source fingerprints and source contributions for a range of different fine particle air pollutants. In this paper we will discuss these PMF techniques and show how they identify both natural sources like sea spray and windblown soils as well as anthropogenic sources like automobiles, biomass burning, coal-fired power stations and industrial emissions. These data are particularly useful for Governments, EPA's and managers of pollution to better understanding pollution sources and their relative contributions and hence to better manage air pollution. Current trends are to take these IBA and PMF techniques a step further and to combine them with wind speed and back trajectory data to better pin point and identify emission sources. We show how this is now being applied on both

  13. The Analysis Of Intention To Buy Books Between Regular Students And Iba Students Of Faculty Of Economics And Business Sam Ratulangi University

    OpenAIRE

    Lelengboto, Jeane Elisabeth

    2014-01-01

    The study of Consumer Behavior has become essential. Consumer buying behavior has become an integral part of strategic market planning. Book is one of the most essentials part in learning process and activities. The purposes of this research are to analyze the difference of intention to buy books between International Business Administration (IBA) students and Regular students. The method that used in this research is Independent Sample t-test. Independent Sample t-test is a method to compare...

  14. IBA analysis and corrosion resistance of TiAlPtN/TiAlN/TiAl multilayer films deposited over a CoCrMo using magnetron sputtering

    Energy Technology Data Exchange (ETDEWEB)

    Canto, C.E., E-mail: carloscanto2012@yahoo.com.mx [Instituto de Física, Universidad Nacional Autónoma de México, Apartado Postal 20-364, 01000 México D.F. (Mexico); Andrade, E.; Lucio, O. de; Cruz, J.; Solís, C. [Instituto de Física, Universidad Nacional Autónoma de México, Apartado Postal 20-364, 01000 México D.F. (Mexico); Rocha, M.F. [ESIME-Z, IPN, U.P. ALM, Gustavo A. Madero, C.P. 07738 México D.F. (Mexico); Alemón, B. [Departamento de Ingeniería de Proyectos, CUCEI, Universidad de Guadalajara, J. Guadalupe Zuno 48, Los Belenes, Zapopan, Jalisco 45101 (Mexico); Tecnológico de Monterrey, Av. General Ramón Corona 2514, Col. Nuevo México, Zapopan, Jalisco 45201 (Mexico); Flores, M. [Departamento de Ingeniería de Proyectos, CUCEI, Universidad de Guadalajara, J. Guadalupe Zuno 48, Los Belenes, Zapopan, Jalisco 45101 (Mexico); Huegel, J.C. [Tecnológico de Monterrey, Av. General Ramón Corona 2514, Col. Nuevo México, Zapopan, Jalisco 45201 (Mexico)

    2016-03-15

    The corrosion resistance and the elemental profile of multilayer coatings of TiAlPtN/TiAlN/TiAl synthesized by Physical Vapor Deposition (PVD) reactive magnetron sputtering over a CoCrMo alloy substrate in 10 periods of 30 min each were analyzed and compared to those of the substrate alone and to that of a TiAlPtN single layer coating of the same thickness. The objective of the present work was to create multilayers with different amounts of Pt to enhance the corrosion resistance of a biomedical alloy of CoCrMo. Corrosion tests were performed using Simulated Body Fluid (SBF) using potentiodynamic polarization tests at typical body temperature. The elemental composition and thickness of the coatings were evaluated with the combination of two ion beam analysis (IBA) techniques: a Rutherford Backscattering Spectroscopy (RBS) with alpha beam and a Nuclear Reaction Analysis with a deuteron beam.

  15. IBA analysis and corrosion resistance of TiAlPtN/TiAlN/TiAl multilayer films deposited over a CoCrMo using magnetron sputtering

    International Nuclear Information System (INIS)

    Canto, C.E.; Andrade, E.; Lucio, O. de; Cruz, J.; Solís, C.; Rocha, M.F.; Alemón, B.; Flores, M.; Huegel, J.C.

    2016-01-01

    The corrosion resistance and the elemental profile of multilayer coatings of TiAlPtN/TiAlN/TiAl synthesized by Physical Vapor Deposition (PVD) reactive magnetron sputtering over a CoCrMo alloy substrate in 10 periods of 30 min each were analyzed and compared to those of the substrate alone and to that of a TiAlPtN single layer coating of the same thickness. The objective of the present work was to create multilayers with different amounts of Pt to enhance the corrosion resistance of a biomedical alloy of CoCrMo. Corrosion tests were performed using Simulated Body Fluid (SBF) using potentiodynamic polarization tests at typical body temperature. The elemental composition and thickness of the coatings were evaluated with the combination of two ion beam analysis (IBA) techniques: a Rutherford Backscattering Spectroscopy (RBS) with alpha beam and a Nuclear Reaction Analysis with a deuteron beam.

  16. Callus Induction of Gendarussa (Justicia gendarussa by Various Concentration of 2,4-D, IBA, and BAP

    Directory of Open Access Journals (Sweden)

    Dwi Kusuma Wahyuni

    2017-12-01

    Full Text Available Justicia gendarussa Burm.f., a medicinal plant, is Acanthaceae that has many functions. Furthermore, the compounds in gendarussa must be produced in high quantity and quality by applying callus culture method. Accordingly, it is important to study the effects of plant growth regulators (2,4-D, IBA, and BAP on callus induction of gendarussa leaves. This research design utilized a factorial design with two factors (2,4-D and IBA: 0.5, 1, 1.5 mg/L and BAP: 0.5, 1, 1.5, 2 mg/L. The experiment consisted of 24 treatments, each of which was repeated 3 times. Observation was carried out in 6 weeks. Data on the time of callus formation, percentage of explants formed callus, and callus morphology were analyzed descriptively,while data on fresh and dry weight were analyzed by Two-Way ANOVA (α = 0.5. Interestingly, the results showed that various concentration of plant growth regulators (2,4-D, IBA, and BAP affected callus induction from leaf explants of gendarussa. We concluded that the most optimal treatment combination of concentration of plant growth regulators in inducing callus from leaf explants of gendarussa is 1.5 mg/L 2,4-D and 2 mg/L BAP with a relatively long period of callus formation at the earliest, i.e. on day 5, 2.247 g of fresh weight, 0.108 gof dry weight, white callus translucent, and friable. Moreover, the optimum treatment will be used to produce secondary metabolite and seed synthetic by cell suspension culture.

  17. IBA levels and substrates in the rooting of UENF/CALIMAN 02 hybrid papaya minicuttings in a semi-hydroponic system

    Directory of Open Access Journals (Sweden)

    Márcio José Vieira de Oliveira

    2018-02-01

    Full Text Available Abstract Mini-cutting is a technique with large applications in various crops, mainly due to the increase in the percentage and quality of adventitious roots, reducing time for the formation of clonal seedlings. The aim of this study was to evaluate IBA levels and substrates on the rooting of UENF/CALIMAN 02 hybrid papaya mini-cuttings. To perform the experiment, papaya mini-cuttings were taken from mother plants grown in pots in greenhouse, induced to produce shoots through pruning and growth regulator applications. Mini-cuttings were fixed in vermiculite or coconut fiver substrates placed in alveolate trays with 4.5x4.5x5.0 cm cells, and styrofoam trays were placed in plastic trays where different IBA levels were added in a modified Hoagland solution. After 45 days, rooted buds were transplanted to plastic pots of 600 mL of volume with soil, sand, well-cured bovine fertilizer, in the proportion of 3:1:1, remaining for 45 days. When they were taken from pots, roots were carefully washed, and the length of shoots, length of the largest root, dried mass of shoots and radicular system and root percentage were measured. The experiment was set up in a randomized complete block 5 x 2 factorial design, with 5 IBA levels: 0; 2.5; 5.0; 7.5 and 10 mg L-1, two substrates: vermiculite and coconut fiber, three replicates, with six plants per replicate. IBA levels of 5.0 mg L-1 and substrate vermiculite are the most adequate for the rooting of ‘UENF/CALIMAN 02’ papaya mini-cuttings in semi-hydroponic system in alveolate styrofoam trays with 4.5x4.5x5.0 cm cells.

  18. Ion beam analysis: New trends and challenges

    Energy Technology Data Exchange (ETDEWEB)

    Zucchiatti, Alessandro, E-mail: alessandro.zucchiatti@uam.es [Centro de Micro Análisis de Materiales, Universidad Autónoma de Madrid, Calle de Faraday 3, 28049 Madrid (Spain); Redondo-Cubero, Andrés [Instituto Superior Técnico, Universidade Técnica de Lisboa, Campus Tecnológico e Nuclear, Estrada Nacional 10 s/n, Bobadela LRS (Portugal)

    2014-07-15

    The development and diffusion of IBA analysis are shortly reviewed paying attention to most competitive and recent advances produced within the IBA community. The paper remarks the potential that IBA maintains in terms of analytical capabilities and points out some future perspectives of the field in terms of innovation and competitiveness.

  19. Internet Based Activities (IBAs): Seniors' Experiences of the Conditions Required for the Performance of and the Influence of these Conditions on their Own Participation in Society

    Science.gov (United States)

    Larsson, Ellinor; Larsson-Lund, Maria; Nilsson, Ingeborg

    2013-01-01

    The digital gap is a threat to the participation of senior citizens in society, as a large proportion of seniors are not involved in Internet based activities (IBAs). To be able to overcome this disadvantage for seniors, there is a need to both learn more about the conditions that make seniors start performing IBAs and to be able to provide them…

  20. The application of IBA techniques to air pollution source fingerprinting and source apportionment

    Energy Technology Data Exchange (ETDEWEB)

    Cohen, D.D., E-mail: dcz@ansto.gov.au; Stelcer, E.; Atanacio, A.; Crawford, J.

    2014-01-01

    IBA techniques have been used to measure elemental concentrations of more than 20 different elements found in fine particle (PM2.5) air pollution. These data together with their errors and minimum detectable limits were used in Positive Matrix Factorisation (PMF) analyses to quantitatively determine source fingerprints and their contributions to the total measured fine mass. Wind speed and direction back trajectory data from the global HYSPLIT codes were then linked to these PMF fingerprints to quantitatively identify the location of the sources.

  1. The IBA Rhodotron: an industrial high-voltage high-powered electron beam accelerator for polymers radiation processing

    Science.gov (United States)

    Van Lancker, Marc; Herer, Arnold; Cleland, Marshall R.; Jongen, Yves; Abs, Michel

    1999-05-01

    The Rhodotron is a high-voltage, high-power electron beam accelerator based on a design concept first proposed in 1989 by J. Pottier of the French Atomic Agency, Commissariat à l'Energie Atomique (CEA). In December 1991, the Belgian particle accelerator manufacturer, Ion Beam Applications s.a. (IBA) entered into an exclusive agreement with the CEA to develop and industrialize the Rhodotron. Electron beams have long been used as the preferential method to cross-link a variety of polymers, either in their bulk state or in their final form. Used extensively in the wire and cable industry to toughen insulating jackets, electron beam-treated plastics can demonstrate improved tensile and impact strength, greater abrasion resistance, increased temperature resistance and dramatically improved fire retardation. Electron beams are used to selectively cross-link or degrade a wide range of polymers in resin pellets form. Electron beams are also used for rapid curing of advanced composites, for cross-linking of floor-heating and sanitary pipes and for cross-linking of formed plastic parts. Other applications include: in-house and contract medical device sterilization, food irradiation in both electron and X-ray modes, pulp processing, electron beam doping of semi-conductors, gemstone coloration and general irradiation research. IBA currently markets three models of the Rhodotron, all capable of 10 MeV and alternate beam energies from 3 MeV upwards. The Rhodotron models TT100, TT200 and TT300 are typically specified with guaranteed beam powers of 35, 80 and 150 kW, respectively. Founded in 1986, IBA, a spin-off of the Cyclotron Research Center at the University of Louvain (UCL) in Belgium, is a pioneer in accelerator design for industrial-scale production.

  2. The IBA Rhodotron: an industrial high-voltage high-powered electron beam accelerator for polymers radiation processing

    International Nuclear Information System (INIS)

    Lancker, Marc van; Herer, Arnold; Cleland, Marshall R.; Jongen, Yves; Abs, Michel

    1999-01-01

    The Rhodotron is a high-voltage, high-power electron beam accelerator based on a design concept first proposed in 1989 by J. Pottier of the French Atomic Agency, Commissariat a l'Energie Atomique (CEA). In December 1991, the Belgian particle accelerator manufacturer, Ion Beam Applications s.a. (IBA) entered into an exclusive agreement with the CEA to develop and industrialize the Rhodotron. Electron beams have long been used as the preferential method to cross-link a variety of polymers, either in their bulk state or in their final form. Used extensively in the wire and cable industry to toughen insulating jackets, electron beam-treated plastics can demonstrate improved tensile and impact strength, greater abrasion resistance, increased temperature resistance and dramatically improved fire retardation. Electron beams are used to selectively cross-link or degrade a wide range of polymers in resin pellets form. Electron beams are also used for rapid curing of advanced composites, for cross-linking of floor-heating and sanitary pipes and for cross-linking of formed plastic parts. Other applications include: in-house and contract medical device sterilization, food irradiation in both electron and X-ray modes, pulp processing, electron beam doping of semi-conductors, gemstone coloration and general irradiation research. IBA currently markets three models of the Rhodotron, all capable of 10 MeV and alternate beam energies from 3 MeV upwards. The Rhodotron models TT100, TT200 and TT300 are typically specified with guaranteed beam powers of 35, 80 and 150 kW, respectively. Founded in 1986, IBA, a spin-off of the Cyclotron Research Center at the University of Louvain (UCL) in Belgium, is a pioneer in accelerator design for industrial-scale production

  3. Quality of skin as a barrier to ultra-fine particles. Contribution of the IBA group to the NANODERM EU-5 project in 2003-2004

    International Nuclear Information System (INIS)

    Kertesz, Zs.; Szikszai, Z.; Kiss, A.Z.

    2004-01-01

    experience in this field, take part in the sample preparation work of WP2 at the Department of Dermatology, Univ. Debrecen. In order to provide quantitative elemental concentrations and distributions a new measurement setup and data evaluation system has been developed at the Debrecen nuclear microprobe facility [2]. All the participating laboratories took part in an intercomparison study in order to demonstrate, that the results obtained using different facilities and different analytical techniques are consistent and reliable. The result of the analysis of two gelatin 'standard' samples showed a fairly good agreement between the six groups (17% and 20% SD from the mean value). The penetration studies using different formulations were started on domestic pig skin, which resembles human skin closest. As a next step, human skin xenografts transplanted into SCID mice were applied. This murine model was developed in the Department of Dermatology of the University of Debrecen because of the difficulties to obtain human skin biopsies from healthy volunteers. Experiments on healthy human skin provided by the Lisbon group started at the end of 2004. In 2004 22 pig skin, 11 transplanted human skin and 13 human skin samples were investigated in Debrecen. The results obtained by ion microscopy or electron microscopy shows that in the case of healthy skin the nanoparticles penetrate into the deepest corneocyte layer of the skin, but never reach the vital layers. Further experiments are planned with repeated exposure and on atopic skin. On the bases of the results obtained by electron microscopy and ion microscopy, cell physiological investigations have been already started. (author)

  4. PIXE and ion beam analysis in forensics

    International Nuclear Information System (INIS)

    Bailey, Melanie; Warmenhoven, John; Chrislopher, Matt; Kirkby, Karen; Palitsin, Vladimir; Grime, Geoff; Jeynes, Chris; Jones, Brian; Wenn, Roger

    2013-01-01

    Full text: University of Surrey has, for the past four years, collaborated with police institutions from across Europe and the rest of the world lo scope potential applications of ion beam analysis (IBA) in forensic science. In doing this we have consulted practitioners across a range of forensic disciplines, and critically compared IBA with conventional characterisation techniques to investigate the areas in which IBA can add evidential value. In this talk, the results of this feasibility study will be presented, showing the types of sample for which IBA shows considerable promise. We will show how a combination of PIXE with other IBA techniques (EBS, PIGE, MeV-SIMS) can be used to give unprecedented characterisation of forensic samples and comment on the significance of these results for forensic casework. We will also show cases where IBA not appear to add any significant improvement over conventional techniques. (author)

  5. The Factors Influencing Consumer Purchase Decision in Choosing Tablet Products of Iba Students

    OpenAIRE

    Tumewu, Ferdinand J.; Saerang, David Paul Elia; Korompis, Caecilia Eva Martina

    2014-01-01

    Youth in this modern era, related with their intention to get information access quickly. Nowadays, there is a popular gadget that used by many people which called tablet. Tablet is a combination of cell phones and laptop. The students of IBA program as the youth who are studying, they need to have gadget which not only can be used to access the internet or social media, but also can help them in college activity. The objective of this research is to know what factors that influencing consume...

  6. Regional energy facility siting analysis

    International Nuclear Information System (INIS)

    Eberhart, R.C.; Eagles, T.W.

    1976-01-01

    Results of the energy facility siting analysis portion of a regional pilot study performed for the anticipated National Energy Siting and Facility Report are presented. The question of cell analysis versus site-specific analysis is explored, including an evaluation of the difference in depth between the two approaches. A discussion of the possible accomplishments of regional analysis is presented. It is concluded that regional sitting analysis could be of use in a national siting study, if its inherent limits are recognized

  7. IBA and synchrotron methods for sub-micron fine particle characterisation

    International Nuclear Information System (INIS)

    Cohen, D.D.; Siegele, R. Stampfl. A.; Cai, Z.; Ilinski, P.; Rodrigues, W.; Legnini, D.G.; Yun, W.; Lai, B.

    1999-01-01

    Fine air-borne particles, whose average diameters are 2.5 μm and less (PM2.5), are known to play significant roles in a number of human and environmental issues. They may penetrate deep into the human lung system and are believed, due to their small size or due to toxins adsorbed onto their surfaces, to be responsible for up to 60,000 and 10,000 deaths in the U.S. and U.K. respectively. Health studies within NSW, Australia carried out by the NSW EPA, have shown increased hospital admissions and excess deaths related to high fine particle pollution episodes. A number of environmental issues are affected by the amount and type of fine-particles in the air. The white and brown hazes that occur in populated cities causing poor visibility are due to light scattering from fine particles. These same particles are easily transported large distances in the lower atmosphere playing a key role in global pollution and climate forcing. Current knowledge of fine-particle concentrations and constituents is very limited. Sources of fine particles are both natural and man-made. Over the past few years considerable work on the characterisation of these particles has been going on at ANSTO using accelerator based ion beam analysis (IBA) methods. X-ray fluorescence using ion beams from accelerators and synchrotron fluorescence are complementary techniques. This is well demonstrated by the plot. PIXE has higher cross sections for low Z elements, but for high Z elements closer to the excitation energy (16keV) synchrotron radiation cross sections are larger. Both techniques are multi-elemental analysis techniques

  8. Data analysis facility at LAMPF

    International Nuclear Information System (INIS)

    Perry, D.G.; Amann, J.F.; Butler, H.S.; Hoffman, C.J.; Mischke, R.E.; Shera, E.B.; Thiessen, H.A.

    1977-11-01

    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

  9. Three-dimensional verification of prostate cancer patients treated with VMAT by Matrixx detector and COMPASS software IBA; Verificacion tridimensional de pacientes con cancer de prostata tratados con VMAT mediante el detector Matrixx y software COMPASS de IBA

    Energy Technology Data Exchange (ETDEWEB)

    Mateos, J. C.; Luis, F. J.; Cabrera, P.; Carrasco, M.; Sanchez, G.; Herrador, M.

    2011-07-01

    Described in this paper the verification of prostate cancer patients treated with VMAT planned in our hospital, with a prescribed dose of 76 Gy. The ability to simultaneously analyze the patient by any plane COMPASS software (IBA, Germany), together with the detector array Matrixx-Evolution, this system gives a particularly interesting feature. The aim of this paper is to describe the operation of this equipment and validated for patient dosimetry in IMRT and VMAT treatments.

  10. Analysis of facility-monitoring data

    Energy Technology Data Exchange (ETDEWEB)

    Howell, J.A.

    1996-09-01

    This paper discusses techniques for analysis of data collected from nuclear-safeguards facility-monitoring systems. These methods can process information gathered from sensors and make interpretations that are in the best interests of the facility or agency, thereby enhancing safeguards while shortening inspection time.

  11. A simple Bragg detector design for AMS and IBA applications

    Energy Technology Data Exchange (ETDEWEB)

    Müller, Arnold Milenko; Döbeli, Max; Seiler, Martin; Synal, Hans-Arno

    2015-08-01

    A new compact Bragg type gas ionization chamber (GIC) has been built for use as particle counter in AMS and IBA applications. The detector stands out due to its simple concept, which does not include a Frisch grid. Test experiments have been performed with ions in the mass range from He to Th and energies ranging from 30 keV to 2.5 MeV, in order to find optimal measurement conditions and to characterize the detector performance. For projectiles heavier than Al at energies below 2.5 MeV the obtained energy resolution is comparable with that of a state-of-the-art GIC with Frisch grid and clearly outperforms solid state detectors. Additionally the operation of this simplified Bragg GIC in the electron multiplication mode was investigated for the first time, which allows the detection of radiocarbon ions at energies below 50 keV with an energy resolution of the order of 10 keV.

  12. Geospatial Data Analysis Facility

    Data.gov (United States)

    Federal Laboratory Consortium — Geospatial application development, location-based services, spatial modeling, and spatial analysis are examples of the many research applications that this facility...

  13. The IBA rhodotron TT1000: a very high power E-beam accelerator

    International Nuclear Information System (INIS)

    Abs, M.; Jongen, Y.; Poncelet, E.; Bol, J.-L.

    2004-01-01

    Due to the relatively low conversion efficiency of electrons into X-rays, the use of X-rays on an industrial basis requires high-power high-energy electron accelerators. Based on its experience acquired in the development of the Rhodotron (Nucl. Instrum. Methods B 40/41 (1989) 943; Nucl. Instrum. Methods B 79 (1993) 865), IBA has launched a few years ago a vigorous R and D program to develop such high-power electron accelerator devoted to X-ray industrial applications. This research program resulted in the TT1000 Rhodotron aimed at delivering 5 and 7 MeV electron beams with a current intensity of 100 mA. This project is now reaching its final phase with the qualification tests of the first prototype of this new machine

  14. Chemical durability of alkali-borosilicate glasses studied by analytical SEM, IBA, isotopic-tracing and SIMS

    Science.gov (United States)

    Trocellier, P.; Djanarthany, S.; Chêne, J.; Haddi, A.; Brass, A. M.; Poissonnet, S.; Farges, F.

    2005-10-01

    Simple and complex alkali-borosilicate glasses were submitted to aqueous corrosion at room temperature, 60 and 90 °C in solutions with pH ranging between 0 and 12. Analytical scanning electron microscopy (SEM), ion beam analysis (IBA) techniques, isotopic tracing and secondary ion mass-depth profiling (SIMS) have been used to investigate the variations of the surface composition of glass. In acidic medium, the glass surface is generally covered by a thick hydrated silica layer, mobile elements like Li, Na and B and transition elements (Fe, Zr, Mo, etc.) are strongly depleted. Near pH 7, relative enrichments of aluminium, iron and rare earths are shown together with strong Li, Na and B depletions. In basic medium, the glass surface exhibits relative enrichments of the major part of transition metals (from Cr to U) whereas mobile elements seem to be kept close to their nominal concentration level at the glass surface and Si is severely impoverished. Hydrogen incorporated at the glass surface after leaching is much more immobile in neutral and basic media than in acid medium.

  15. Chemical durability of alkali-borosilicate glasses studied by analytical SEM, IBA, isotopic-tracing and SIMS

    International Nuclear Information System (INIS)

    Trocellier, P.; Djanarthany, S.; Chene, J.; Haddi, A.; Brass, A.M.; Poissonnet, S.; Farges, F.

    2005-01-01

    Simple and complex alkali-borosilicate glasses were submitted to aqueous corrosion at room temperature, 60 and 90 deg. C in solutions with pH ranging between 0 and 12. Analytical scanning electron microscopy (SEM), ion beam analysis (IBA) techniques, isotopic tracing and secondary ion mass-depth profiling (SIMS) have been used to investigate the variations of the surface composition of glass. In acidic medium, the glass surface is generally covered by a thick hydrated silica layer, mobile elements like Li, Na and B and transition elements (Fe, Zr, Mo, etc.) are strongly depleted. Near pH 7, relative enrichments of aluminium, iron and rare earths are shown together with strong Li, Na and B depletions. In basic medium, the glass surface exhibits relative enrichments of the major part of transition metals (from Cr to U) whereas mobile elements seem to be kept close to their nominal concentration level at the glass surface and Si is severely impoverished. Hydrogen incorporated at the glass surface after leaching is much more immobile in neutral and basic media than in acid medium

  16. High-capacity neutron activation analysis facility

    International Nuclear Information System (INIS)

    Hochel, R.C.

    1979-01-01

    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 trace elements in hydrogeochemical samples collected in the National Uranium Resource Evaluation program. 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

  17. Facility/equipment performance evaluation using microcomputer simulation analysis

    International Nuclear Information System (INIS)

    Chockie, A.D.; Hostick, C.J.

    1985-08-01

    A computer simulation analysis model was developed at the Pacific Northwest Laboratory to assist in assuring the adequacy of the Monitored Retrievable Storage facility design to meet the specified spent nuclear fuel throughput requirements. The microcomputer-based model was applied to the analysis of material flow, equipment capability and facility layout. The simulation analysis evaluated uncertainties concerning both facility throughput requirements and process duration times as part of the development of a comprehensive estimate of facility performance. The evaluations provided feedback into the design review task to identify areas where design modifications should be considered

  18. Bidimensional verification of prostate cancer patients treated with VMAT by Matrixx detector and software IBA OP'IMRT; Verificacion bidimensional de pacientes con cancer de prostata tratados con VMAT mediante el detector Matrixx y software OP'IMRT de IBA

    Energy Technology Data Exchange (ETDEWEB)

    Mateos, J. C.; Perucha, M.; Cabrera, P.; Luis, F. J.; Sanchez, G.; Herrador, M.

    2011-07-01

    Described in this paper the verification of prostate cancer patients treated with VMAT planned in our hospital, with a prescribed dose of 76 Gy. Was used for this, nn-Evolution Matrixx IBA detector comprising a matrix ionization chamber 1020 with diameter of 4.5 Mm nn a height of 5 mm. The distance between the centers is 7,619 mm. The data were compared with film dosimetry and ionization chamber.

  19. 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.

  20. Cold Vacuum Drying Facility hazard analysis report

    International Nuclear Information System (INIS)

    Krahn, D.E.

    1998-01-01

    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

  1. 340 Waste handling Facility Hazard Categorization and Safety Analysis

    International Nuclear Information System (INIS)

    Rodovsky, T.J.

    2010-01-01

    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

  2. Operating procedures: Fusion Experiments Analysis Facility

    Energy Technology Data Exchange (ETDEWEB)

    Lerche, R.A.; Carey, R.W.

    1984-03-20

    The Fusion Experiments Analysis Facility (FEAF) is a computer facility based on a DEC VAX 11/780 computer. It became operational in late 1982. At that time two manuals were written to aid users and staff in their interactions with the facility. This manual is designed as a reference to assist the FEAF staff in carrying out their responsibilities. It is meant to supplement equipment and software manuals supplied by the vendors. Also this manual provides the FEAF staff with a set of consistent, written guidelines for the daily operation of the facility.

  3. Operating procedures: Fusion Experiments Analysis Facility

    International Nuclear Information System (INIS)

    Lerche, R.A.; Carey, R.W.

    1984-01-01

    The Fusion Experiments Analysis Facility (FEAF) is a computer facility based on a DEC VAX 11/780 computer. It became operational in late 1982. At that time two manuals were written to aid users and staff in their interactions with the facility. This manual is designed as a reference to assist the FEAF staff in carrying out their responsibilities. It is meant to supplement equipment and software manuals supplied by the vendors. Also this manual provides the FEAF staff with a set of consistent, written guidelines for the daily operation of the facility

  4. Kakaibang Halimuyak: Iba't Ibang Imahe ng Pangangapital sa Balintawak

    Directory of Open Access Journals (Sweden)

    Mariah Amour C. Miranda

    2015-06-01

    Full Text Available Ginagalugad ng sanaysay na ito ang isang pangunahing lugar na nadaraanan mula Norte patungong Maynila—ang Balintawak. Nagsisilbing manibela ng pagsusuri ang kontemporaneong pananaw sa lunan bilang pugad ng mga anyong may magkakasalungat na kahulugan. Binibigyang-pansin ng sanaysay ang iba't ibang imahe ng pagbebenta na matatagpuan sa Balintawak: ang billboard ng kumpanyang Bench na siyang pinakamalaki, ang mismong palengke, at ang mga lakong paninda sa tabing-kalsada. Sa pamamagitan nito, maipapakita ng sanaysay kung paano madadalumat ang Balintawak bilang isang panlipunang texto na sumasalamin sa mga magkakaibang pangangapital sa naturang lunan. This essay explores the space of Balintawak—a focal point of urban travel from northern Luzon to Manila. Using the contemporary view on space as a site of structures with contradictory meanings, the study seeks to understand how various images of market activities in Balintawak create meaningful representations. These images include the gigantic billboard of Bench, the central market itself, and flea markets in the area. The essay shows how Balintawak as a social text serves as a trading center of different forms of capital.

  5. High-capacity neutron activation analysis facility

    International Nuclear Information System (INIS)

    Hochel, R.C.; Bowman, W.W.; Zeh, C.W.

    1980-01-01

    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

  6. Digital pulse processor for ion beam microprobe imaging

    International Nuclear Information System (INIS)

    Bogovac, M.; Jaksic, M.; Wegrzynek, D.; Markowicz, A.

    2009-01-01

    Capabilities of spectroscopic ion beam analysis (IBA) techniques that are available in ion microprobe facilities can be greatly improved by the use of digital pulse processing. We report here development of a digital multi parameter data acquisition system suitable for IBA imaging applications. Input signals from charge sensitive preamplifier are conditioned by using a simple circuit and digitized with fast ADCs. The digitally converted signals are processed in real time using FPGA. Implementation of several components of the system is presented.

  7. UTJECAJ KONCENTRACIJE IBA NA KVALITETU OŽILJAVANJA REZNICA ODABRANIH AUTOHTONIH SORATA MASLINA DUBROVAČKOG PODRUČJA

    OpenAIRE

    Barnjak Vukas, Marina; Marić, Mara; Marinović-Peričević, Marija

    2016-01-01

    U radu su prikazani rezultati jednogodišnjeg proučavanja utjecaja različitih koncentracija fitohormona IBA (2 000, 3 000, 4 000 i 5 000 ppm) na ožiljavanje reznica dubrovačkih sorta maslina: Velika sitnjaka, Sitnica, Kalamata i Uljarica. Sva su istraživanja obavljena u stakleniku Zavoda za mediteranske kulture Sveučilišta u Dubrovniku, i dio su projekta ''Identifikacija i gospodarenje gen-fondom masline na području Dubrovačko-neretvanske županije'', za koje je planirano trajanje od tri godine...

  8. Characterization of the proton beam from an IBA Cyclone 18/9 with radiochromic film EBT2

    Energy Technology Data Exchange (ETDEWEB)

    Sansaloni, F.; Lagares, J. I.; Arce, P.; Llop, J.; Perez, J. M. [Medical Applications Unit, Technology Department, CIEMAT, Madrid (Spain); Radiochemistry Department, Molecular Imaging unit, CIC-biomaGUNE, San Sebastian (Spain); Technology Department, CIEMAT (Spain)

    2012-12-19

    The use of radiochromic films is widespread in different areas of medical physics like radiotherapy and hadrontherapy; however, radiochromic films have been scarcely used in the characterization of proton or deuteron beams generated in biomedical cyclotrons. In this paper the radiochromic film EBT2 was used to study the beam size and the proton beam energy of an IBA Cyclone 18/9 cyclotron. The results indicate that the beam size can be easily measured at a very low expense; however, an accurate determination of the beam energy might require the implementation of certain experimental improvements.

  9. 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.

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

    International Nuclear Information System (INIS)

    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

  11. 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

  12. Checking collagen preservation in archaeological bone by non-destructive studies (Micro-CT and IBA)

    Science.gov (United States)

    Beck, L.; Cuif, J.-P.; Pichon, L.; Vaubaillon, S.; Dambricourt Malassé, A.; Abel, R. L.

    2012-02-01

    The material to be studied is a piece of human skull discovered (1999) in Pleistocene sediments from the Orsang river (Gujarat state, India). From anatomical view point, this skull is highly composite: modern Homo sapiens characters are associated to undoubtedly more ancient features. Absolute dating by 14C is critical to understand this discovery. Prior to dating measurements, non-destructive studies have been carried out. Micro-CT reconstruction (X-ray microtomography) and Ion Beam Analysis (IBA) have been undertaken to check the structural preservation of the fossil and the collagen preservation. PIXE elemental map was used to select well-preserved bone area. RBS/EBS and NRA were used for light element quantification, in particular C, N and O contents. We also demonstrate that the PIXE-RBS/EBS combination is a effective tool for the whole characterization of archaeological and recent bones by analysing in one experiment both mineral and organic fractions. We have shown that the archaeological bone, a fragment of the potentially oldest modern Indian, is enough preserved for radiocarbon dating. We propose that Elastic Backscattering Spectrometry (EBS) using 3 MeV protons could be a good non destructive alternative to conventional CHN method using Carbon-Hydrogen-Nitrogen analyzer for measuring C and N before 14C dating.

  13. Checking collagen preservation in archaeological bone by non-destructive studies (Micro-CT and IBA)

    International Nuclear Information System (INIS)

    Beck, L.; Cuif, J.-P.; Pichon, L.; Vaubaillon, S.; Dambricourt Malassé, A.; Abel, R.L.

    2012-01-01

    The material to be studied is a piece of human skull discovered (1999) in Pleistocene sediments from the Orsang river (Gujarat state, India). From anatomical view point, this skull is highly composite: modern Homo sapiens characters are associated to undoubtedly more ancient features. Absolute dating by 14 C is critical to understand this discovery. Prior to dating measurements, non-destructive studies have been carried out. Micro-CT reconstruction (X-ray microtomography) and Ion Beam Analysis (IBA) have been undertaken to check the structural preservation of the fossil and the collagen preservation. PIXE elemental map was used to select well-preserved bone area. RBS/EBS and NRA were used for light element quantification, in particular C, N and O contents. We also demonstrate that the PIXE-RBS/EBS combination is a effective tool for the whole characterization of archaeological and recent bones by analysing in one experiment both mineral and organic fractions. We have shown that the archaeological bone, a fragment of the potentially oldest modern Indian, is enough preserved for radiocarbon dating. We propose that Elastic Backscattering Spectrometry (EBS) using 3 MeV protons could be a good non destructive alternative to conventional CHN method using Carbon–Hydrogen–Nitrogen analyzer for measuring C and N before 14 C dating.

  14. Checking collagen preservation in archaeological bone by non-destructive studies (Micro-CT and IBA)

    Energy Technology Data Exchange (ETDEWEB)

    Beck, L., E-mail: lucile.beck@cea.fr [C2RMF - UMR171 CNRS, Centre de Recherche et de Restauration des Musees de France, Palais du Louvre, Porte des Lions, 14 quai Francois Mitterrand, 75001 Paris (France); CEA, DEN, Service de Recherches de Metallurgie Physique, Laboratoire JANNUS, 91191 Gif-sur-Yvette (France); Cuif, J.-P. [UMR IDES 8148, Universite Paris XI-Orsay, 91405 Orsay cedex (France); Pichon, L. [C2RMF - UMR171 CNRS, Centre de Recherche et de Restauration des Musees de France, Palais du Louvre, Porte des Lions, 14 quai Francois Mitterrand, 75001 Paris (France); Vaubaillon, S. [CEA, INSTN, Laboratoire JANNUS, 91191 Gif-sur-Yvette (France); Dambricourt Malasse, A. [Departement de Prehistoire, Museum national d' Histoire naturelle, UMR 7194 - CNRS, Institut de Paleontologie Humaine, 1, rue Rene Panhard, 75013 Paris (France); Abel, R.L. [The Natural History Museum, London (United Kingdom)

    2012-02-15

    The material to be studied is a piece of human skull discovered (1999) in Pleistocene sediments from the Orsang river (Gujarat state, India). From anatomical view point, this skull is highly composite: modern Homo sapiens characters are associated to undoubtedly more ancient features. Absolute dating by {sup 14}C is critical to understand this discovery. Prior to dating measurements, non-destructive studies have been carried out. Micro-CT reconstruction (X-ray microtomography) and Ion Beam Analysis (IBA) have been undertaken to check the structural preservation of the fossil and the collagen preservation. PIXE elemental map was used to select well-preserved bone area. RBS/EBS and NRA were used for light element quantification, in particular C, N and O contents. We also demonstrate that the PIXE-RBS/EBS combination is a effective tool for the whole characterization of archaeological and recent bones by analysing in one experiment both mineral and organic fractions. We have shown that the archaeological bone, a fragment of the potentially oldest modern Indian, is enough preserved for radiocarbon dating. We propose that Elastic Backscattering Spectrometry (EBS) using 3 MeV protons could be a good non destructive alternative to conventional CHN method using Carbon-Hydrogen-Nitrogen analyzer for measuring C and N before {sup 14}C dating.

  15. External events analysis for experimental fusion facilities

    International Nuclear Information System (INIS)

    Cadwallader, L.C.

    1990-01-01

    External events are those off-normal events that threaten facilities either from outside or inside the building. These events, such as floods, fires, and earthquakes, are among the leading risk contributors for fission power plants, and the nature of fusion facilities indicates that they may also lead fusion risk. This paper gives overviews of analysis methods, references good analysis guidance documents, and gives design tips for mitigating the effects of floods and fires, seismic events, and aircraft impacts. Implications for future fusion facility siting are also discussed. Sites similar to fission plant sites are recommended. 46 refs

  16. Combination of the auxins NAA, IBA, and IAA with GA3 improves the commercial seed-tuber production of potato (Solanum tuberosum L.) under in vitro conditions.

    Science.gov (United States)

    Kumlay, Ahmet Metin

    2014-01-01

    The study compared the effects of 1.0 × MS medium containing various concentrations of α-naphthaleneacetic acid (NAA), indole-3-acetic acid (IAA), and indole-3-butyric acid (IBA), alone or in combination with gibberellic acid (GA3) in micropropagation of three potato (Solanum tuberosum L.) cultivars Pasinler, Granola, and Caspar using binodal stem cuttings. The results testified improved regeneration on 1.0 × MS medium containing variants of NAA, IAA, and IBA plus GA3 on all cultivars. The minimum days to shoot induction on three cultivars ranged 4.25-5 d on 1.0 × MS medium containing 0.25 mg L(-1) GA3 + 1 mg L(-1) NAA. The longest shoots (11.8 cm), maximum number of nodes (13.50), and maximum number of leaves (11.00) were recorded on cv. Caspar on 1.0 × MS medium containing 1 mg L(-1) NAA + 0.25 mg L(-1) GA3. The minimum time to root induction (12.25 d) was noted on cv. Pasinler on the same medium. All of the regenerated shoots could be easily rooted. The results showed that the combined effect of various concentrations of NAA, IAA, and IBA plus GA3 was more pronounced compared to the auxins used alone. The results of this research are of significant importance for potato breeders.

  17. Effects of IAA and IBA on the in vitro rooting of stem cuttings of Sechium edule (Jacq. Sw

    Directory of Open Access Journals (Sweden)

    José García García

    2015-01-01

    Full Text Available This investigation was carried out with the objective of evaluating the response of shoots of chayote [S. edule (Jacq. Sw.] to the application of indole-3-butyric acid (IBA and indole-3-acetic acid (IAA on the in vitro rooting phase. The effect of three culture media, modified from the proposed of Murashige and Skoog (MS was studied: 1- 65% MS salt base, 2- 65% MS salt base + 0.05 mg l-1 of indolebutyric acid (AIB and 3- 65% MS salt base + 3.0 mg l-1-3-indole acetic acid (IAA. The variables evaluated were: number of roots, length and number of shoots per in vitro seedling. The best result were obtained when using 65% MS salt base with 3.0 mg l-1 of IAA. Significant differences (P<0.05 among treatments containing growth regulators was obtained for the variables number of roots and length of in vitro plantlets. In the UNA-730 accession root induction was obtained in a 65% MS salt base culture medium without growth regulators; however, when IAA and IBA was added the induction was 100%. The differences identified in this work with regards to the root induction were probably the combined result of genotype and specific culture conditions. Key words: auxins, chayote, growth regulators, in vitro culture

  18. Stored energy analysis in the scaled-down test facilities

    International Nuclear Information System (INIS)

    Deng, Chengcheng; Chang, Huajian; Qin, Benke; Wu, Qiao

    2016-01-01

    Highlights: • Three methods are developed to evaluate stored energy in the scaled-down test facilities. • The mechanism behind stored energy distortion in the test facilities is revealed. • The application of stored energy analysis is demonstrated for the ACME facility of China. - Abstract: In the scaled-down test facilities that simulate the accident transient process of the prototype nuclear power plant, the stored energy release in the metal structures has an important influence on the accuracy and effectiveness of the experimental data. Three methods of stored energy analysis are developed, and the mechanism behind stored energy distortion in the test facilities is revealed. Moreover, the application of stored energy analysis is demonstrated for the ACME test facility newly built in China. The results show that the similarity requirements of three methods analyzing the stored energy release decrease gradually. The physical mechanism of stored energy release process can be characterized by the dimensionless numbers including Stanton number, Fourier number and Biot number. Under the premise of satisfying the overall similarity of natural circulation, the stored energy release process in the scale-down test facilities cannot maintain exact similarity. The results of the application of stored energy analysis illustrate that both the transient release process and integral total stored energy of the reactor pressure vessel wall of CAP1400 power plant can be well reproduced in the ACME test facility.

  19. The CMS CERN Analysis Facility (CAF)

    Energy Technology Data Exchange (ETDEWEB)

    Buchmueller, O [Imperial College (United Kingdom); Bonacorsi, D [Universita and INFN, Bologna (Italy); Fanzago, F [Universita and INFN, Padova (Italy); Gowdy, S; Malgeri, L; Panzer-Steindel, B; Schwickerath, U; Spiga, D; Toebbicke, Rainer [Conseil Europeen Recherche Nucl. (CERN) Switzerland (Switzerland); Kreuzer, P [Rheinisch-Westfaelische Tech. Hoch. (RWTH) (Germany); Mankel, R [Deutsches Elektronen-Synchrotron (DESY) (Germany); Metson, S [University of Bristol (United Kingdom); Sanches, J Afonso; Teodoro, D, E-mail: Peter.Kreuzer@cern.c [Universidade do Estado do Rio De Janeiro (UERJ) (Brazil)

    2010-04-01

    The CMS CERN Analysis Facility (CAF) was primarily designed to host a large variety of latency-critical workflows. These break down into alignment and calibration, detector commissioning and diagnosis, and high-interest physics analysis requiring fast-turnaround. In addition to the low latency requirement on the batch farm, another mandatory condition is the efficient access to the RAW detector data stored at the CERN Tier-0 facility. The CMS CAF also foresees resources for interactive login by a large number of CMS collaborators located at CERN, as an entry point for their day-by-day analysis. These resources will run on a separate partition in order to protect the high-priority use-cases described above. While the CMS CAF represents only a modest fraction of the overall CMS resources on the WLCG GRID, an appropriately sized user-support service needs to be provided. We will describe the building, commissioning and operation of the CMS CAF during the year 2008. The facility was heavily and routinely used by almost 250 users during multiple commissioning and data challenge periods. It reached a CPU capacity of 1.4MSI2K and a disk capacity at the Peta byte scale. In particular, we will focus on the performances in terms of networking, disk access and job efficiency and extrapolate prospects for the upcoming LHC first year data taking. We will also present the experience gained and the limitations observed in operating such a large facility, in which well controlled workflows are combined with more chaotic type analysis by a large number of physicists.

  20. The CMS CERN Analysis Facility (CAF)

    International Nuclear Information System (INIS)

    Buchmueller, O; Bonacorsi, D; Fanzago, F; Gowdy, S; Malgeri, L; Panzer-Steindel, B; Schwickerath, U; Spiga, D; Toebbicke, Rainer; Kreuzer, P; Mankel, R; Metson, S; Sanches, J Afonso; Teodoro, D

    2010-01-01

    The CMS CERN Analysis Facility (CAF) was primarily designed to host a large variety of latency-critical workflows. These break down into alignment and calibration, detector commissioning and diagnosis, and high-interest physics analysis requiring fast-turnaround. In addition to the low latency requirement on the batch farm, another mandatory condition is the efficient access to the RAW detector data stored at the CERN Tier-0 facility. The CMS CAF also foresees resources for interactive login by a large number of CMS collaborators located at CERN, as an entry point for their day-by-day analysis. These resources will run on a separate partition in order to protect the high-priority use-cases described above. While the CMS CAF represents only a modest fraction of the overall CMS resources on the WLCG GRID, an appropriately sized user-support service needs to be provided. We will describe the building, commissioning and operation of the CMS CAF during the year 2008. The facility was heavily and routinely used by almost 250 users during multiple commissioning and data challenge periods. It reached a CPU capacity of 1.4MSI2K and a disk capacity at the Peta byte scale. In particular, we will focus on the performances in terms of networking, disk access and job efficiency and extrapolate prospects for the upcoming LHC first year data taking. We will also present the experience gained and the limitations observed in operating such a large facility, in which well controlled workflows are combined with more chaotic type analysis by a large number of physicists.

  1. 300 Area fuel supply facilities deactivation mission analysis report

    International Nuclear Information System (INIS)

    Lund, D.P.

    1995-01-01

    This report presents the results of the 300 Area fuel supply facilities (formerly call ''N reactor fuel fabrication facilities'') Deactivation Project mission analysis. Hanford systems engineering (SE) procedures call for a mission analysis. The mission analysis is an important first step in the SE process

  2. Flow analysis of HANARO flow simulated test facility

    International Nuclear Information System (INIS)

    Park, Yong-Chul; Cho, Yeong-Garp; Wu, Jong-Sub; Jun, Byung-Jin

    2002-01-01

    The HANARO, a multi-purpose research reactor of 30 MWth open-tank-in-pool type, has been under normal operation since its initial critical in February, 1995. Many experiments should be safely performed to activate the utilization of the NANARO. A flow simulated test facility is being developed for the endurance test of reactivity control units for extended life times and the verification of structural integrity of those experimental facilities prior to loading in the HANARO. This test facility is composed of three major parts; a half-core structure assembly, flow circulation system and support system. The half-core structure assembly is composed of plenum, grid plate, core channel with flow tubes, chimney and dummy pool. The flow channels are to be filled with flow orifices to simulate core channels. This test facility must simulate similar flow characteristics to the HANARO. This paper, therefore, describes an analytical analysis to study the flow behavior of the test facility. The computational flow analysis has been performed for the verification of flow structure and similarity of this test facility assuming that flow rates and pressure differences of the core channel are constant. The shapes of flow orifices were determined by the trial and error method based on the design requirements of core channel. The computer analysis program with standard k - ε turbulence model was applied to three-dimensional analysis. The results of flow simulation showed a similar flow characteristic with that of the HANARO and satisfied the design requirements of this test facility. The shape of flow orifices used in this numerical simulation can be adapted for manufacturing requirements. The flow rate and the pressure difference through core channel proved by this simulation can be used as the design requirements of the flow system. The analysis results will be verified with the results of the flow test after construction of the flow system. (author)

  3. A new ion-beam laboratory for materials research at the Slovak University of Technology

    Science.gov (United States)

    Noga, Pavol; Dobrovodský, Jozef; Vaňa, Dušan; Beňo, Matúš; Závacká, Anna; Muška, Martin; Halgaš, Radoslav; Minárik, Stanislav; Riedlmajer, Róbert

    2017-10-01

    An ion beam laboratory (IBL) for materials research has been commissioned recently at the Slovak University of Technology within the University Science Park CAMBO located in Trnava. The facility will support research in the field of materials science, physical engineering and nanotechnology. Ion-beam materials modification (IBMM) as well as ion-beam analysis (IBA) are covered and deliverable ion energies are in the range from tens of keV up to tens of MeV. Two systems have been put into operation. First, a high current version of the HVEE 6 MV Tandetron electrostatic tandem accelerator with duoplasmatron and cesium sputtering ion sources, equipped with two end-stations: a high-energy ion implantation and IBA end-station which includes RBS, PIXE and ERDA analytical systems. Second, a 500 kV implanter equipped with a Bernas type ion source and two experimental wafer processing end-stations. The facility itself, operational experience and first IBMM and IBA experiments are presented together with near-future plans and ongoing development of the IBL.

  4. Efeito do AIB sobre o enraizamento e desenvolvimento de estacas de quivi (Actinidia deliciosa Effect of IBA on the rooting and development of kiwi cuttings (Actinidia deliciosa

    Directory of Open Access Journals (Sweden)

    Vitor Manfroi

    1997-03-01

    Full Text Available O objetivo do trabalho foi estudar o efeito do ácido 3-indoibiitirico (A/B no enraizamento e desenvolvimento de estacas semi-lenhosas de quivi, cv. Monte. O experimento foi conduzido na Estação Experimental Agronômica da UFRGS, em Eldorado do Sul, RS, e constou de cinco tratamentos, com cinco repetições, em blocos casualizados. Usou-se 19 sacos/parcela, com duas estacas/saco plástico, plantadas em uma mistura argila: areia.-esterco (1: 1: 1: e tratadas com AIB nas concentrações de: 2000ppm, 4000ppm, 6000ppm e 8000ppm, além da testemunha (sem AIB. O AIB não influenciou na porcentagem de enraizamento das estacas, mas resultou no aumento linear do peso seco médio das raízes. Houve, da mesma forma, incrementos lineares no comprimento e no peso seco dos brotos, à medida que se elevou a concentração de AIB.The objective of this experiment was to study the effect of the 3-indolbutiric acid (IBA on the rooting and development of semi-hardwood cuttings of kiwi, cv. Monty. The experiment was carried out at the Staccatos Experimental Agronomical/UFRGS in Eldorado do Soul. RS, Brazil with five treatments and five repetitions, in completely randomized blocks design. There were 19 bags per pilot with two cuttings per plastic bag grow in a catty: sane manure mixture (1:1:1 and treated by /BA at the concentrations of 2000ppm, 4000ppm, 6000ppm and 8000ppm. In addition to the contrail. IBA did not affect the rooting percentage but resulted in a linear increase of the mean root dry weight. Shoot development was not affected by the IBA. Buy there was a tendency for a linear increase of shoot length and dry weight in response to IBA concentrations above 2000 ppm.

  5. Combination of the Auxins NAA, IBA, and IAA with GA3 Improves the Commercial Seed-Tuber Production of Potato (Solanum tuberosum L.) under In Vitro Conditions

    Science.gov (United States)

    Kumlay, Ahmet Metin

    2014-01-01

    The study compared the effects of 1.0 × MS medium containing various concentrations of α-naphthaleneacetic acid (NAA), indole-3-acetic acid (IAA), and indole-3-butyric acid (IBA), alone or in combination with gibberellic acid (GA3) in micropropagation of three potato (Solanum tuberosum L.) cultivars Pasinler, Granola, and Caspar using binodal stem cuttings. The results testified improved regeneration on 1.0 × MS medium containing variants of NAA, IAA, and IBA plus GA3 on all cultivars. The minimum days to shoot induction on three cultivars ranged 4.25–5 d on 1.0 × MS medium containing 0.25 mg L−1  GA3 + 1 mg L−1 NAA. The longest shoots (11.8 cm), maximum number of nodes (13.50), and maximum number of leaves (11.00) were recorded on cv. Caspar on 1.0 × MS medium containing 1 mg L−1  NAA + 0.25 mg L−1 GA3. The minimum time to root induction (12.25 d) was noted on cv. Pasinler on the same medium. All of the regenerated shoots could be easily rooted. The results showed that the combined effect of various concentrations of NAA, IAA, and IBA plus GA3 was more pronounced compared to the auxins used alone. The results of this research are of significant importance for potato breeders. PMID:25028654

  6. The impact on materials science of ion beam analysis with electrostatic accelerators

    International Nuclear Information System (INIS)

    Amsel, G.; Battistig, G.

    2005-01-01

    The specific aspects of IBA for near surface and thin film analysis are discussed. In a number of cases IBA is the only analytical tool that may provide the information sought, in other cases it provides the most accessible or practical technique to be applied. While IBA is insensitive to the chemical state of the atoms analysed, it is unique in particular for determining with high accuracy and sensitivity absolute atomic quantities or concentrations, for studying with channeling techniques the atomic structure of crystalline thin films or materials near the surface, for isotopic tracing experiments with stable isotopes using nuclear reactions or resonances. Its advantages and drawbacks with respect to SIMS will be especially outlined. Due to these unique characteristics IBA has a long history of application, in combination with other characterisation methods, to a number of problems encountered in materials science, solid state and surface physics, solid state electrochemistry, thin film deposition or growth studies, trace and contamination determinations, etc. Representative applications will be presented that could not be obtained without IBA

  7. Usage of an interactive image analysis system for studying various parameters of etched tracks in CR-39 and Makrofol E

    International Nuclear Information System (INIS)

    Abu-Jarad, F.; Islam, M.A.; Que, A.

    1991-01-01

    An Automated Interactive Built Analysis System (IBAS) is being used to analyze the alpha and fission fragment tracks in CR-39 and Makrofol E detectors. It primarily consists of a control computer (IBAS1) and an image processor (IBAS2). The system is used for counting the nuclear tracks, measuring their areas, diameters, statistics and displaying the frequency distribution of their sizes. All information can be printed out or stored on floppy disks. (author)

  8. 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...

  9. 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.

  10. Hot Cell Facility (HCF) Safety Analysis Report

    International Nuclear Information System (INIS)

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

    2000-01-01

    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

  11. Impact of accelerator-based analytical techniques on the knowledge and conservation of cultural heritage

    International Nuclear Information System (INIS)

    Dran, Jean Claude

    2001-01-01

    A large set of modern analytical techniques is currently applied to get a better insight on art and archaeological objects as well as to contribute to their conservation and restoration. Because of the precious and sometimes unique character of the works, non-destructive techniques and even those requiring no (or only minute) sampling, are preferred. From this standpoint, ion beam analysis (IBA) constitutes one of the best choices, since it combines quite good analytical performance and non-destructiveness. For over 10 years, an IBA facility has been installed in the Research Laboratory of the Museums of France. Until now it is the only facility of this kind entirely devoted to the study of cultural heritage. A special set-up, namely an external beam line, has been developed which permits the in-air analysis of large or fragile works of art without sampling. This facility is used for both short investigations at the request of museum curators and extensive research works in art history and archaeology. Numerous examples will be given to highlight the impact of this tool on cultural heritage. (author)

  12. Understanding of CO{sub 2} interaction with thermally grown SiO{sub 2} on Si using IBA depth profiling techniques

    Energy Technology Data Exchange (ETDEWEB)

    Deokar, Geetanjali; D’Angelo, Marie; Briand, Emrick [INSP, UPMC, CNRS UMR 7588, 4 Place Jussieu, Paris F-75005 (France); Deville Cavellin, Catherine, E-mail: deville@univ-paris12.fr [INSP, UPMC, CNRS UMR 7588, 4 Place Jussieu, Paris F-75005 (France); Faculté des Sciences et Technologie UPEC, 61 Av., De Gaulle, Créteil F-94010 (France)

    2013-06-01

    Interactions between CO{sub 2} and SiO{sub 2} films thermally grown on Si have been studied using {sup 18}O and {sup 13}C as isotopic tracers associated with ion beam analysis (IBA) depth profiling techniques. From secondary ion mass spectrometry (SIMS) measurements no carbon from CO{sub 2} is detected in the silica while it is found in Si. These results suggest that CO{sub 2} diffuses through the silica. Exchanges of oxygen between CO{sub 2} and silica can be observed from {sup 18}O to {sup 16}O SIMS signals variation. The oxygen concentration depth profiles were determined quantitatively using the narrow resonance near 151 keV in the {sup 18}O(p,α){sup 15}N nuclear reaction (Narrow Resonance Profiling, NRP). We demonstrate that two distinct oxygen exchanges processes co-exist and we determine the diffusion coefficient of the CO{sub 2} molecule in the silica at 1100 °C.

  13. High-intensity cyclotrons for radioisotope production and accelerator driven systems

    Energy Technology Data Exchange (ETDEWEB)

    Jongen, Y.; Vandeplassche, D.; Kleeven, W.; Beeckman, W.; Zaremba, S.; Lannoye, G.; Stichelbaut, F

    2002-04-22

    IBA recently proposed a new method to extract high-intensity positive ion beams from a cyclotron based on the concept of auto-extraction. We review the design of a 14 MeV, multi-milliampere cyclotron using this new technology. IBA is also involved in the design of the accelerator system foreseen to drive the MYRRHA facility, a multipurpose neutron source developed jointly by SCK-CEN and IBA.

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

    International Nuclear Information System (INIS)

    1982-01-01

    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

  15. The NAF: National analysis facility at DESY

    International Nuclear Information System (INIS)

    Haupt, Andreas; Kemp, Yves

    2010-01-01

    Within the framework of a broad collaboration among German particle physicists, the strategic Helmholtz Alliance P hysics a the Terascale , an analysis facility has been set up at DESY. The facility is intended to provide the best possible analysis infrastructure for researches of the ATLAS, CMS, LHCb and ILC experiments and also for theory researchers. In a first part of the contribution, we will present the concept of the NAF and its place in the existing distributed grid landscape of the experiments. In a second part, the building blocks of the NAF will be detailed with an emphasis on technical implementations of some parts: - Usage of VOMS for separating grid resources between collaboration-wide and NAF-specific resources. - interactive and batch cluster and integration with PROOF. - usage of grid proxies to access work group servers and AFS. - the usage and operation of Lustre for fast data access. A special focus is the seamless integration of the facility into the two geographically separated DESY sites and its implications. In a third part, the experience of running the facility for one year will be reported.

  16. Ion beam analysis in cultural heritage studies: Milestones and perspectives

    International Nuclear Information System (INIS)

    Dran, Jean-Claude; Calligaro, Thomas

    2013-01-01

    For three decades, ion beam analysis (IBA) in external mode was considered as the best choice for the characterisation of cultural heritage materials, as it combines excellent analytical performance and non-invasive character. However, in recent years, other analytical techniques arose as serious competitors, such as those based on synchrotron radiation (X-ray absorption, fluorescence or diffraction) or those using portable instruments (XRF, micro-Raman). It is shown that nevertheless IBA remains unmatched thanks to two unique features, namely the analysis of light elements and the high-resolution 3D chemical imaging

  17. Systems reliability analysis for the national ignition facility

    International Nuclear Information System (INIS)

    Majumdar, K.C.; Annese, C.E.; MacIntyre, A.T.; Sicherman, A.

    1996-01-01

    A Reliability, Availability and Maintainability (RAM) analysis was initiated for the National Ignition Facility (NIF). The NIF is an inertial confinement fusion research facility designed to achieve controlled thermonuclear reaction; the preferred site for the NIF is the Lawrence Livermore National Laboratory (LLNL). The NIF RAM analysis has three purposes: (1) to allocate top level reliability and availability goals for the systems, (2) to develop an operability model for optimum maintainability, and (3) to determine the achievability of the allocated goals of the RAM parameters for the NIF systems and the facility operation as a whole. An allocation model assigns the reliability and availability goals for front line and support systems by a top-down approach; reliability analysis uses a bottom-up approach to determine the system reliability and availability from component level to system level

  18. Safety analysis of the existing 850 Firing Facility

    International Nuclear Information System (INIS)

    Odell, B.N.

    1986-01-01

    A safety analysis was performed to determine if normal operations and/or potential accidents at the 850 Firing Facility at Site 300 could present undue hazards to the general public, personnel at Site 300, or have an adverse effect on the environment. The normal operations and credible accidents that might have an effect on these facilities or have off-site consequences were considered. It was determined by this analysis that all but one of the hazards were either low or of the type or magnitude routinely encountered and/or accepted by the public. The exception was explosives, which was classified as a moderate hazard per the requirements given in DOE Order 5481.1A. This safety analysis concluded that the operation at this facility will present no undue risk to the health and safety of LLNL employees or the public

  19. Safety analysis of the existing 851 Firing Facility

    International Nuclear Information System (INIS)

    Odell, B.N.

    1986-01-01

    A safety analysis was performed to determine if normal operations and/or potential accidents at the 851 Firing Facility at Site 300 could present undue hazards to the general public, personnel at Site 300, or have an adverse effect on the environment. The normal operations and credible accidents that might have an effect on these facilities or have off-site consequences were considered. It was determined by this analysis that all but two of the hazards were either low or of the type or magnitude routinely encountered and/or accepted by the public. The exceptions were the linear accelerator and explosives, which were classified as moderate hazards per the requirements given in DOE Order 5481.1A. This safety analysis concluded that the operation at this facility will present no undue risk to the health and safety of LLNL employees or the public

  20. Scaling analysis for the OSU AP600 test facility (APEX)

    International Nuclear Information System (INIS)

    Reyes, J.N.

    1998-01-01

    In this paper, the authors summarize the key aspects of a state-of-the-art scaling analysis (Reyes et al. (1995)) performed to establish the facility design and test conditions for the advanced plant experiment (APEX) at Oregon State University (OSU). This scaling analysis represents the first, and most comprehensive, application of the hierarchical two-tiered scaling (H2TS) methodology (Zuber (1991)) in the design of an integral system test facility. The APEX test facility, designed and constructed on the basis of this scaling analysis, is the most accurate geometric representation of a Westinghouse AP600 nuclear steam supply system. The OSU APEX test facility has served to develop an essential component of the integral system database used to assess the AP600 thermal hydraulic safety analysis computer codes. (orig.)

  1. 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.

  2. Integration of facility modeling capabilities for nuclear nonproliferation analysis

    International Nuclear Information System (INIS)

    Garcia, Humberto; Burr, Tom; Coles, Garill A.; Edmunds, Thomas A.; Garrett, Alfred; Gorensek, Maximilian; Hamm, Luther; Krebs, John; Kress, Reid L.; Lamberti, Vincent; Schoenwald, David; Tzanos, Constantine P.; Ward, Richard C.

    2012-01-01

    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.

  3. Integration Of Facility Modeling Capabilities For Nuclear Nonproliferation Analysis

    International Nuclear Information System (INIS)

    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.

    2011-01-01

    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.

  4. Report of the consultant's meeting on applications of accelerator based analysis

    International Nuclear Information System (INIS)

    1998-07-01

    At the present meeting, applications of accelerator based analytical methods, often referred as ion beam analysis (IBA) methods, to the following areas have been discussed: materials (including thin films), Earth sciences (including environmental studies), biology and medicine, art and archaeology (cultural heritage), and other applications (including forensic applications). This report gives brief overview of IBA applications in these areas, with short background about accelerators needed and corresponding analytical techniques

  5. Analysis of Elektrogorsk 108 test facility experimental data

    International Nuclear Information System (INIS)

    Urbonas, R.

    2001-01-01

    In the paper an evaluation of experimental data obtained at Russian Elektrogorsk 108 (E-108) test facility is presented. E-108 facility is a scaled model of Russian RBMK design reactor. An attempt to validate state-of-the-art thermal hydraulic codes on the basis of E-108 test facility was made. Originally these codes were developed and validated for BWRs and PWRs. Since state-of-art thermal hydraulic codes are widely used for simulation of RBMK reactors further codes' implementation and validation is required. The facility was modelled by employing RELAP5 (INEEL, USA) thermal hydraulic system analysis best estimate code. The results show dependence from number of nodes used in the heated channels, frictional and form losses employed. The obtained oscillatory behaviour is resulted by density wave and critical heat flux. It is shown that codes are able to predict thermal hydraulic instability and sudden heat structure temperature excursion, when critical heat flux is approached, well. In addition, an uncertainty analysis of one of the experiments was performed by employing GRS developed System for Uncertainty and Sensitivity Analysis (SUSA). It was one of the first attempts to use this statistic-based methodology in Lithuania.(author)

  6. Mechanistic facility safety and source term analysis

    International Nuclear Information System (INIS)

    PLYS, M.G.

    1999-01-01

    A PC-based computer program was created for facility safety and source term analysis at Hanford The program has been successfully applied to mechanistic prediction of source terms from chemical reactions in underground storage tanks, hydrogen combustion in double contained receiver tanks, and proccss evaluation including the potential for runaway reactions in spent nuclear fuel processing. Model features include user-defined facility room, flow path geometry, and heat conductors, user-defined non-ideal vapor and aerosol species, pressure- and density-driven gas flows, aerosol transport and deposition, and structure to accommodate facility-specific source terms. Example applications are presented here

  7. Ion beam analysis of Cu(In,Ga)Se{sub 2} thin film solar cells

    Energy Technology Data Exchange (ETDEWEB)

    Karydas, A.G. [International Atomic Energy Agency (IAEA), IAEA Laboratories, Nuclear Science and Instrumentation Laboratory, A-2444 Seibersdorf (Austria); Institute of Nuclear and Particle Physics, NCSR “Demokritos”, 153 10 Aghia Paraskevi, Athens Greece (Greece); Streeck, C. [Physikalisch-Technische Bundesanstalt (PTB), Abbestr. 2-12, 10587 Berlin (Germany); Radovic, I. Bogdanovic [Ruđer Bošković Institute (RBI), Zagreb (Croatia); Kaufmann, C.; Rissom, T. [Helmholtz-Zentrum Berlin für Materialien und Energie GmbH (HZB), Hahn-Meitner-Platz 1, 14109 Berlin (Germany); Beckhoff, B. [Physikalisch-Technische Bundesanstalt (PTB), Abbestr. 2-12, 10587 Berlin (Germany); Jaksic, M. [Ruđer Bošković Institute (RBI), Zagreb (Croatia); Barradas, N.P. [Centro de Ciências e Tecnologias Nucleares, Instituto Superior Técnico, Universidade de Lisboa, E. N. 10, Apartado 21, 2686-953 Sacavém (Portugal)

    2015-11-30

    Graphical abstract: - Highlights: • Elemental depth profiles for various CIGS thin films were quantitatively determined. • Pure absorbers, complete cell and bilayer solar cells were prepared and analyzed. • Synergistic PIXE and RBS analysis of thin solar cells using alpha beam particles. • High energy alpha beam resolved completely the Indium depth profile. • Synchrotron based Reference Free GIXRF quantitative analysis validated IBA results. - Abstract: The present work investigates the potential of ion beam analysis (IBA) techniques such as the Rutherford backscattering spectrometry (RBS) and particle induced X-ray emission (PIXE) using helium ions to provide quantitative in-depth elemental analysis of various types of Cu(In,Ga)Se{sub 2} thin films. These films with a thickness of about 2 μm are used as absorber layers in photovoltaic devices with continuously increasing the performance of this technology. The preparation process generally aims to obtain an in-depth gradient of In and Ga concentrations that optimizes the optoelectronic and electrical properties of the solar cell. The measurements were performed at directly accessible single or double layered CIGS absorbers and at buried absorbers in completed thin film solar cells. The IBA data were analyzed simultaneously in order to derive best fitted profiles that match all experimental RBS and PIXE spectra. For some samples elemental profiles deduced form synchrotron based, reference free grazing incidence X-ray fluorescence analysis were compared with the IBA results and an overall good agreement was observed within quoted uncertainties.

  8. Cold Vacuum Drying facility design basis accident analysis documentation

    International Nuclear Information System (INIS)

    CROWE, R.D.

    2000-01-01

    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

  9. 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.

  10. Capsule safety analysis of PRTF irradiation facility

    International Nuclear Information System (INIS)

    Suwarto

    2013-01-01

    Power Ramp Test Facility (PRTF) is an irradiation facility used for fuel testing of power reactor. PRTF has a capsule which is a test fuel rod container. During operation, pressurized water of 160 bars flows through in the capsule. Due to the high pressure it should be analyzed the impact of the capsule on reactor core safety. This analysis has purpose to calculate the ability of capsule pressure capacity. The analysis was carried out by calculating pressure capacity. From the calculating results it can be concluded that the capsule with pressure capacity of 438 bars will be safe to prevent the operation pressure of PRTF. (author)

  11. Nuclear fuel cycle facility accident analysis handbook

    International Nuclear Information System (INIS)

    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

  12. Hazard analysis in uranium hexafluoride production facility

    International Nuclear Information System (INIS)

    Marin, Maristhela Passoni de Araujo

    1999-01-01

    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)

  13. DRY TRANSFER FACILITY SEISMIC ANALYSIS

    International Nuclear Information System (INIS)

    EARNEST, S.; KO, H.; DOCKERY, W.; PERNISI, R.

    2004-01-01

    The purpose of this calculation is to perform a dynamic and static analysis on the Dry Transfer Facility, and to determine the response spectra seismic forces for the design basis ground motions. The resulting seismic forces and accelerations will be used in a subsequent calculation to complete preliminary design of the concrete shear walls, diaphragms, and basemat

  14. 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.

  15. Development of an auditable safety analysis in support of a radiological facility classification

    International Nuclear Information System (INIS)

    Kinney, M.D.; Young, B.

    1995-01-01

    In recent years, U.S. Department of Energy (DOE) facilities commonly have been classified as reactor, non-reactor nuclear, or nuclear facilities. Safety analysis documentation was prepared for these facilities, with few exceptions, using the requirements in either DOE Order 5481.1B, Safety Analysis and Review System; or DOE Order 5480.23, Nuclear Safety Analysis Reports. Traditionally, this has been accomplished by development of an extensive Safety Analysis Report (SAR), which identifies hazards, assesses risks of facility operation, describes and analyzes adequacy of measures taken to control hazards, and evaluates potential accidents and their associated risks. This process is complicated by analysis of secondary hazards and adequacy of backup (redundant) systems. The traditional SAR process is advantageous for DOE facilities with appreciable hazards or operational risks. SAR preparation for a low-risk facility or process can be cost-prohibitive and quite challenging because conventional safety analysis protocols may not readily be applied to a low-risk facility. The DOE Office of Environmental Restoration and Waste Management recognized this potential disadvantage and issued an EM limited technical standard, No. 5502-94, Hazard Baseline Documentation. This standard can be used for developing documentation for a facility classified as radiological, including preparation of an auditable (defensible) safety analysis. In support of the radiological facility classification process, the Uranium Mill Tailings Remedial Action (UMTRA) Project has developed an auditable safety analysis document based upon the postulation criteria and hazards analysis techniques defined in DOE Order 5480.23

  16. Data analysis for neutron monitoring in an enrichment facility

    International Nuclear Information System (INIS)

    Markin, J.T.; Stewart, J.E.; Goldman, A.S.

    1982-01-01

    Area monitoring of neutron radiation to detect high-enriched uranium production is a potential strategy for inspector verification of operations in the cascade area of a centrifuge enrichment facility. This paper discusses the application of statistical filtering and hypothesis testing procedures to experimental data taken in an enrichment facility. The results demonstrate that these data analysis methods can enhance detection of facility misoperation by neutron monitoring

  17. Reproductive biology in monoecious and gynoecious cucumber cultivars as a result of IBA application Biologia reprodutiva de cultivares monóicas e ginóicas de pepino em função do uso de AIB

    Directory of Open Access Journals (Sweden)

    Valdir Diola

    2008-03-01

    Full Text Available The understanding of both the reproductive biology and the regulation of the sexual expression of cucumber flowers (Cucumis sativus makes crop management easier and can improve fruit yield and quality. The objective of this study was to evaluate the physiological answer of cucumber floral verticils to the application of IBA. The experiment was carried out in a greenhouse, in completely randomized blocks, with four replications of 4-plant plots, and treatments applied to a 5 x 2 factorial (0, 50, 100, 200, and 500 µmol of IBA, and two cultivars: Wisconsin MR28, gynoecious, and Caipira, monoecious. Cultivar Wisconsin MR28 produced in average 7,636 pollen grains (PG per flower, with a positive linear response to the increase in IBA concentration. Instead, in cultivar Caipira (5,160 PG all IBA concentrations reduced PG production. Cultivars did not differ from each other in relation to PG viability (average in vitrogermination of 75.4 and 79.9% to cultivars Wisconsin MR28 and Caipira, respectively and in both PG viability increased linearly with the increase in AIB concentration. Cultivars Wisconsin MR28 and Caipira presented in average 71.6 and 70.6 seeds per fruit respectively, and responded with an increase in seed number and improvement in fruit general aspect to the rise in IBA concentration. The ratio male:female flowers was significantly different between cultivars (4.2:1 and 3.5:1, respectively to cultivars Wisconsin MR28 and Caipira and responded in a distinct way to IBA concentrations. While in cultivar Caipira, IBA concentrations near to 100 µmol increased the number of male flowers; in cultivar Wisconsin MR28 the same IBA concentration reduced it. The two cultivars had a similar number of female flowers. However, whereas it remained relatively stable in cultivar Caipira in spite of the increase in IBA concentration, there was an increase in the number of female flowers in cultivar Wisconsin MR28, as a result of the rise in IBA

  18. Waste analysis plan for the 200 area effluent treatment facility and liquid effluent retention facility

    International Nuclear Information System (INIS)

    Ballantyne, N.A.

    1995-01-01

    This waste analysis plan (WAP) has been prepared for startup of the 200 Area Effluent Treatment Facility (ETF) and operation of the Liquid Effluent Retention Facility (LERF), which are located on the Hanford Facility, Richland, Washington. This WAP documents the methods used to obtain and analyze representative samples of dangerous waste managed in these units, and of the nondangerous treated effluent that is discharged to the State-Approved Land Disposal System (SALDS). Groundwater Monitoring at the SALDS will be addressed in a separate plan

  19. International Atomic Energy Agency intercomparison of ion beam analysis software

    Energy Technology Data Exchange (ETDEWEB)

    Barradas, N.P. [Instituto Tecnologico e Nuclear, Estrada Nacional No. 10, Apartado 21, 2686-953 Sacavem (Portugal); Centro de Fisica Nuclear da Universidade de Lisboa, Avenida do Professor Gama Pinto 2, 1649-003 Lisboa (Portugal)], E-mail: nunoni@itn.pt; Arstila, K. [K.U. Leuven, Instituut voor Kern-en Stralingsfysica, Celestijnenlaan 200D, B-3001 Leuven (Belgium); Battistig, G. [MFA Research Institute for Technical Physics and Materials Science, P.O. Box 49, H-1525 Budapest (Hungary); Bianconi, M. [CNR-IMM-Sezione di Bologna, Via P. Gobetti, 101, I-40129 Bologna (Italy); Dytlewski, N. [International Atomic Energy Agency, Wagramer Strasse 5, P.O. Box 100, A-1400 Vienna (Austria); Jeynes, C. [Surrey Ion Beam Centre, University of Surrey, Guildford, Surrey GU2 7XH (United Kingdom); Kotai, E. [KFKI Research Institute for Particle and Nuclear Physics, P.O. Box 49, H-1525 Budapest (Hungary); Lulli, G. [CNR-IMM-Sezione di Bologna, Via P. Gobetti, 101, I-40129 Bologna (Italy); Mayer, M. [Max-Planck-Institut fuer Plasmaphysik, EURATOM Association, Boltzmannstrasse 2, D-85748 Garching (Germany); Rauhala, E. [Accelerator Laboratory, Department of Physics, University of Helsinki, P.O. Box 43, FIN-00014 Helsinki (Finland); Szilagyi, E. [KFKI Research Institute for Particle and Nuclear Physics, P.O. Box 49, H-1525 Budapest (Hungary); Thompson, M. [Department of MS and E/Bard Hall 328, Cornell University, Ithaca, NY 14853 (United States)

    2007-09-15

    Ion beam analysis (IBA) includes a group of techniques for the determination of elemental concentration depth profiles of thin film materials. Often the final results rely on simulations, fits and calculations, made by dedicated codes written for specific techniques. Here we evaluate numerical codes dedicated to the analysis of Rutherford backscattering spectrometry, non-Rutherford elastic backscattering spectrometry, elastic recoil detection analysis and non-resonant nuclear reaction analysis data. Several software packages have been presented and made available to the community. New codes regularly appear, and old codes continue to be used and occasionally updated and expanded. However, those codes have to date not been validated, or even compared to each other. Consequently, IBA practitioners use codes whose validity, correctness and accuracy have never been validated beyond the authors' efforts. In this work, we present the results of an IBA software intercomparison exercise, where seven different packages participated. These were DEPTH, GISA, DataFurnace (NDF), RBX, RUMP, SIMNRA (all analytical codes) and MCERD (a Monte Carlo code). In a first step, a series of simulations were defined, testing different capabilities of the codes, for fixed conditions. In a second step, a set of real experimental data were analysed. The main conclusion is that the codes perform well within the limits of their design, and that the largest differences in the results obtained are due to differences in the fundamental databases used (stopping power and scattering cross section). In particular, spectra can be calculated including Rutherford cross sections with screening, energy resolution convolutions including energy straggling, and pileup effects, with agreement between the codes available at the 0.1% level. This same agreement is also available for the non-RBS techniques. This agreement is not limited to calculation of spectra from particular structures with predetermined

  20. Detailed analysis of the KAERI nTOF facility

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Jong Woon; Lee, Young Ouk [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2016-06-15

    A project for building a neutron time-of-flight (nTOF) facility is progressing. We expect that the construction will start in early 2016. Before that, a detailed simulation based on the current architectural drawings was performed to optimize the performance of our facility. Currently, several parts had been modified or changed from the original design to reflect requirements such as the layout of the electron beam line, shape of the vacuum chamber producing a neutron beam, and the underground layout of the nTOF facility. Detailed analysis for these modifications has been done with MCNP simulation. An overview of our photo-neutron source and KAERI nTOF facility were introduced. The numerical simulations for heat deposition, source term, and radiation shielding of KAERI nTOF facility were performed and the results are discussed. We are expecting that the construction of the KAERI nTOF facility will start in early 2016, and these results will be used as basic data.

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

    Energy Technology Data Exchange (ETDEWEB)

    SINGH, G.

    2000-09-06

    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 cited, as applicable. This FHA comprehensively assesses the risk of fire at the CVDF to ascertain whether the specific objectives of DOE 5480.7A are met. These specific fire protection objectives are: (1) Minimize the potential for the occurrence of a fire. (2) Ensure that fire does not cause an onsite or offsite release of radiological and other hazardous material that will threaten the public health and safety or the environment. (3) Establish requirements that will provide an acceptable degree of life safety to DOE and contractor personnel and ensure that there are no undue hazards to the public from fire and its effects in DOE facilities. (4) Ensure that vital DOE programs will not suffer unacceptable delays as a result of fire and related perils. (5) Ensure that property damage from fire and related perils does not exceed an acceptable level. (6) Ensure that process control and safety systems are not damaged by fire or related perils. This FHA is based on the

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

    International Nuclear Information System (INIS)

    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 cited, as applicable. This FHA comprehensively assesses the risk of fire at the CVDF to ascertain whether the specific objectives of DOE 5480.7A are met. These specific fire protection objectives are: (1) Minimize the potential for the occurrence of a fire. (2) Ensure that fire does not cause an onsite or offsite release of radiological and other hazardous material that will threaten the public health and safety or the environment. (3) Establish requirements that will provide an acceptable degree of life safety to DOE and contractor personnel and ensure that there are no undue hazards to the public from fire and its effects in DOE facilities. (4) Ensure that vital DOE programs will not suffer unacceptable delays as a result of fire and related perils. (5) Ensure that property damage from fire and related perils does not exceed an acceptable level. (6) Ensure that process control and safety systems are not damaged by fire or related perils. This FHA is based on the

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

    International Nuclear Information System (INIS)

    Rugg, J.E.

    1998-02-01

    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

  4. Activation analysis for the IFF system in RAON facility

    International Nuclear Information System (INIS)

    LEE, Cheol Woo; LEE, Young-Ouk; KIM, Jong Won; KIM, Mijung

    2014-01-01

    A heavy-ion accelerator facility is under a development in Korea to use in the basic science research and various application areas. In this facility, the In-Flight Fragment (IFF) target and isotope separator has been designed to produce various isotopes and transport the interesting isotopes into the experimental rooms. In this work, activation analysis for the pre-separator was performed in the IFF target room. In this work, activation analysis for the pre-separator was performed for the IFF target system in RAON heavy-ion accelerator facility. At first, radiation source terms were evaluated with the primary beams and target conditions. Using the evaluated source terms, induced activities in all component of pre-separator were calculated. The decay gamma-rays produced after a shutdown was estimated based on the activation analysis and gamma-ray dose rate according to the cooling time was evaluated

  5. 105-DR Large Sodium Fire Facility decontamination, sampling, and analysis plan

    International Nuclear Information System (INIS)

    Knaus, Z.C.

    1995-01-01

    This is the decontamination, sampling, and analysis plan for the closure activities at the 105-DR Large Sodium Fire Facility at Hanford Reservation. This document supports the 105-DR Large Sodium Fire Facility Closure Plan, DOE-RL-90-25. The 105-DR LSFF, which operated from about 1972 to 1986, was a research laboratory that occupied the former ventilation supply room on the southwest side of the 105-DR Reactor facility in the 100-D Area of the Hanford Site. The LSFF was established to investigate fire fighting and safety associated with alkali metal fires in the liquid metal fast breeder reactor facilities. The decontamination, sampling, and analysis plan identifies the decontamination procedures, sampling locations, any special handling requirements, quality control samples, required chemical analysis, and data validation needed to meet the requirements of the 105-DR Large Sodium Fire Facility Closure Plan in compliance with the Resource Conservation and Recovery Act

  6. 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).

  7. Addendum to the Composite Analysis for the E-Area Vaults and Saltstone Disposal Facilities

    International Nuclear Information System (INIS)

    Cook, J.R.

    2002-01-01

    Revision 1 of the Composite Analysis (CA) Addendum has been prepared to respond to the U.S. Department of Energy (DOE) Low-Level Waste Disposal Facilities Federal Review Group review of the CA. This addendum to the composite analysis responds to the conditions of approval. The composite analysis was 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. 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 the Savannah River Site and contains all of the waste disposal facilities, the chemical separation facilities and associated high-level waste storage facilities, as well as numerous other sources of radioactive material

  8. Spacing Sensitivity Analysis of HLW Intermediate Storage Facility

    International Nuclear Information System (INIS)

    Youn, Bum Soo; Lee, Kwang Ho

    2010-01-01

    Currently, South Korea's spent fuels are stored in its temporary storage within the plant. But the temporary storage is expected to be reaching saturation soon. For the effective management of spent fuel wastes, the need for intermediate storage facility is a desperate position. However, the research for the intermediate storage facility for waste has not made active so far. In addition, in case of foreign countries it is mostly treated confidentially and the information isn't easy to collect. Therefore, the purpose of this study is creating the basic thermal analysis data for the waste storage facility that will be valuable in the future

  9. Investigation of Growth and Survival of Transplanted Plane and Pine Trees According to IBA Application, Tree Age, Transplanting Time and Method

    Directory of Open Access Journals (Sweden)

    N. Etemadi

    2015-03-01

    Full Text Available The major problems in transplanting the landscape trees are high level of mortality and low establishment rate of transplanted trees, especially in the first year. In order to achieve the best condition for successful transplanting of pine and plane trees in Isfahan landscape, the present study was carried out based on a completely randomized block design with four replicates and three treatments including transplanting method (balled and burlapped and bare root, tree age (immature and mature and IBA application (0 and 150 mg/L. Trees were transplanted during 2009 and 2010 in three times (dormant season, early and late growing season. Survival rate and Relative Growth Rate index based on tree height (RGRH and trunk diameter (RGRD were measured during the first and second years. Trees transplanted early in the growing season showed the most survival percentage during the two years, as compared to other transplanting dates. Survival of Balled and burlapped and immature transplanted trees was significantly greater than bare root or mature trees. The significant effect of age treatment was continued in the second year. IBA treatment had no effect on survival rate of the studied species. Balled and burlapped and immature transplanted pine trees also had higher RGRH and RGRD compared to bare root or mature trees. According to the results of this study, early growing season is the best time for transplanting pine and plane trees. Also, transplanting of immature trees using balled and burlapped method is recommended to increase the survival and establishment rate.

  10. Storage fee analysis for a retrievable surface storage facility

    International Nuclear Information System (INIS)

    Field, B.B.; Rosnick, C.K.

    1973-12-01

    Conceptual design studies are in progress for a Water Basin Concept (WBC) and an alternative Sealed Storage Cask Concept (SSCC) of a Retrievable Surface Storage Facility (RSSF) intended as a Federal government facility for storing high-level radioactive wastes until a permanent disposal method is established. The RSSF will be a man-made facility with a design life of at least 100 y, and will have capacity to store all of the high-level waste from the reprocessing of nuclear power plant spent fuels generated by the industry through the year 2000. This report is a basic version of ARH-2746, ''Retrievable Surface Storage Facility, Water Basin Concept, User Charge Analysis.'' It is concerned with the issue of establishing a fee to cover the cost of storing nuclear wastes both in the RSSF and at the subsequent disposal facility. (U.S.)

  11. CMT scaling analysis and distortion evaluation in passive integral test facility

    International Nuclear Information System (INIS)

    Deng Chengcheng; Qin Benke; Wang Han; Chang Huajian

    2013-01-01

    Core makeup tank (CMT) is the crucial device of AP1000 passive core cooling system, and reasonable scaling analysis of CMT plays a key role in the design of passive integral test facilities. H2TS method was used to perform scaling analysis for both circulating mode and draining mode of CMT. And then, the similarity criteria for CMT important processes were applied in the CMT scaling design of the ACME (advanced core-cooling mechanism experiment) facility now being built in China. Furthermore, the scaling distortion results of CMT characteristic Ⅱ groups of ACME were calculated. At last, the reason of scaling distortion was analyzed and the distortion evaluation was conducted for ACME facility. The dominant processes of CMT circulating mode can be adequately simulated in the ACME facility, but the steam condensation process during CMT draining is not well preserved because the excessive CMT mass leads to more energy to be absorbed by cold metal. However, comprehensive analysis indicates that the ACME facility with high-pressure simulation scheme is able to properly represent CMT's important phenomena and processes of prototype nuclear plant. (authors)

  12. Severe accident analysis and management in nuclear fuel cycle facilities

    International Nuclear Information System (INIS)

    Golshan, Mina

    2013-01-01

    Within the UK regulatory regime, assessment of risks arising from licensee's activities are expected to cover both normal operations and fault conditions. In order to establish the safety case for fault conditions, fault analysis is expected to cover three forms of analysis: design basis analysis (DBA), probabilistic safety assessment (PSA) and severe accident analysis (SAA). DBA should provide a robust demonstration of the fault tolerance of the engineering design and the effectiveness of the safety measures on a conservative basis. PSA looks at a wider range of fault sequences (on a best estimate basis) including those excluded from the DBA. SAA considers significant but unlikely accidents and provides information on their progression and consequences, within the facility, on the site and off site. The assessment of severe accidents is not limited to nuclear power plants and is expected to be carried out for all plant states where the identified dose targets could be exceeded. This paper sets out the UK nuclear regulatory expectation on what constitutes a severe accident, irrespective of the type of facility, and describes characteristics of severe accidents focusing on nuclear fuel cycle facilities. Key rules in assessment of severe accidents as well as the relationship to other fault analysis techniques are discussed. The role of SAA in informing accident management strategies and offsite emergency plans is covered. The paper also presents generic examples of scenarios that could lead to severe accidents in a range of nuclear fuel cycle facilities. (authors)

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

    International Nuclear Information System (INIS)

    Warner, C.L.

    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

  14. 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.

  15. Cold Vacuum Drying Facility Design Basis Accident Analysis Documentation

    International Nuclear Information System (INIS)

    PIEPHO, M.G.

    1999-01-01

    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

  16. Contribution to the study of the Ciconiiformes (Aves’ presence in the IBA Carja - Mata - Radeanu ponds (Romania

    Directory of Open Access Journals (Sweden)

    IGNAT Alina Elena

    2006-09-01

    Full Text Available The IBA „Cârja-Maţa-Rădeanu ponds” (code 010 is situated along the point of the confluence of Elan River with the Prut River, on the border of Vaslui and Galaţi counties. The avifauna list including 123 birds species recorded in 1995 – 2005 period; between these, we recorded 12 species belonged to Ciconiiformes Order. From these, one species is present only during the migration time – the Black Stork (Ciconia nigra, all the others being breeding species in this area. We followed their dynamic during migration and the breeding population’s trend. We notice the presence of the Spoonbill (Platalea leucorodia like breeding species beginning with the 2003’s summer – it is the second breeding site identified out of the Danube Delta in Romania but also in the Prut River Basin.

  17. 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.

  18. Fire hazards analysis for the uranium oxide (UO3) facility

    International Nuclear Information System (INIS)

    Wyatt, D.M.

    1994-01-01

    The Fire Hazards Analysis (FHA) documents the deactivation end-point status of the UO 3 complex fire hazards, fire protection and life safety systems. This FHA has been prepared for the Uranium Oxide Facility by Westinghouse Hanford Company in accordance with the criteria established in DOE 5480.7A, Fire Protection and RLID 5480.7, Fire Protection. The purpose of the Fire Hazards Analysis is to comprehensively and quantitatively assess the risk from a fire within individual fire areas in a Department of Energy facility so as to ascertain whether the objectives stated in DOE Order 5480.7, paragraph 4 are met. Particular attention has been paid to RLID 5480.7, Section 8.3, which specifies the criteria for deactivating fire protection in decommission and demolition facilities

  19. Facility Safeguardability Analysis in Support of Safeguards by Design

    International Nuclear Information System (INIS)

    Wonder, E.F.

    2010-01-01

    The idea of 'Safeguards-by-Design' (SBD) means designing and incorporating safeguards features into new civil nuclear facilities at the earliest stages in the design process to ensure that the constructed facility is 'safeguardable,' i.e. will meet national and international nuclear safeguards requirements. Earlier consideration of safeguards features has the potential to reduce the need for costly retrofits of the facility and can result in a more efficient and effective safeguards design. A 'Facility Safeguardability Analysis' (FSA) would be a key step in Safeguards-by-Design that would link the safeguards requirements with the 'best practices', 'lessons learned', and design of the safeguards measures for implementing those requirements. The facility designer's nuclear safeguards experts would work closely with other elements of the project design team in performing FSA. The resultant analysis would support discussions and interactions with the national nuclear regulator (i.e. State System of Accounting for and Control of Nuclear Material - SSAC) and the IAEA for development and approval of the proposed safeguards system. FSA would also support the implementation of international safeguards by the IAEA, by providing them with a means to analyse and evaluate the safeguardability of facilities being designed and constructed - i.e. by independently reviewing and validating the FSA as performed by the design team. Development of an FSA methodology is part of a broader U.S. National Nuclear Security Administration program to develop international safeguards-by-design tools and guidance documents for use by facility designers. The NNSA NGSI -sponsored project team is looking, as one element of its work, at how elements of the methodology developed by the Generation IV International Forum's Working Group on Proliferation Resistance and Physical Protection can be adapted to supporting FSA. (author)

  20. Seismic design and analysis of nuclear fuel cycle facilities in France

    International Nuclear Information System (INIS)

    Sollogoub, P.

    2001-01-01

    Methodology for seismic design of nuclear fuel facilities and power plants in France is described. After the description of regulatory and normative texts for seismic design, different elements are examined: definition of ground motion, analysis methods, new trends, reevaluation and specificity of Fuel Cycle Facilities. R/D developments are explicated in each part. Their final objective are to better quantify the margins of each step which, in relation with safety analysis,lead to balanced design, analysis and retrofit rules. (author)

  1. Analysis on working pressure selection of ACME integral test facility

    International Nuclear Information System (INIS)

    Chen Lian; Chang Huajian; Li Yuquan; Ye Zishen; Qin Benke

    2011-01-01

    An integral effects test facility, advanced core cooling mechanism experiment facility (ACME) was designed to verify the performance of the passive safety system and validate its safety analysis codes of a pressurized water reactor power plant. Three test facilities for AP1000 design were introduced and review was given. The problems resulted from the different working pressures of its test facilities were analyzed. Then a detailed description was presented on the working pressure selection of ACME facility as well as its characteristics. And the approach of establishing desired testing initial condition was discussed. The selected 9.3 MPa working pressure covered almost all important passive safety system enables the ACME to simulate the LOCAs with the same pressure and property similitude as the prototype. It's expected that the ACME design would be an advanced core cooling integral test facility design. (authors)

  2. The Effects of IBA and NAA, and Rooting Media on Propagation of Miniature Rose Cuttings (Rosa hybrida

    Directory of Open Access Journals (Sweden)

    azam ranjbar

    2017-09-01

    miniature rose stem cutting, this research was carried out as a factorial on the basis of randomized complete design (RCD with three replications. Plant growth regulators including IBA at concentrations of 0, 1000, 2000 and 3000 mgl-1, concentrations of NAA at 0, 500, 1000, 1500 and 2000 mgl-1 were applied together with two types of rooting media. Media including mixing volume of perlite, tea waste compost and sand in a ratio of 1: 2: 2, and perlite, peat and sand in a ratio of 1:2:2 were mixed and applied in this experiment. Using SAS software, data was analyzed based on a generalized linear model (GLM analysis and tested by least significant difference (LSD at (P-value< 0.05. Results and Discussion: Results showed that the highest rooting percentage of cuttings was obtained with 2000 mgl-1 of IBA, while no significant effect of NAA treatment and different rooting media on percentage of rooting was revealed. The two-fold and three-fold interaction of treatments on other measured traits such as primary and secondary root number and root diameter were significant. The two-fold interaction of NAA treatments and rooting media on the trait of primary root number were no significant. The highest root number and root diameter measured in medium containing perlite, tea waste compost and sand in a ratio of 1:2:2 for cutting received combined plant growth regulators. Conclusions: Compost, the final product of organic residues degradation, improves soil physical characteristics such as soil aggregate formation and stability, water penetration, porosity, compressing resistance and nutrients availability. As well, it improves soil biological characteristics and in result, integration of compost with soil can increase growth, yield and quality of crop. There are also some evidences that in contrast of peat, compost contains plant growth regulators improved plant growth and development. Totally, considering our obtained results, in order to accelerate rooting formation in miniature rose

  3. Seismic analysis for shroud facility in-pile tube and saturated temperature capsules

    International Nuclear Information System (INIS)

    Iimura, Koichi; Yamaura, Takayuki; Ogawa, Mitsuhiro

    2009-07-01

    At Oarai Research and Development Center, Japan Atomic Energy Agency (JAEA), the plan of repairing and refurbishing Japan Materials Testing Reactor (JMTR) has progressed in order to restart JMTR operation in the fiscal 2011. As a part of effective use of JMTR, the neutron irradiation tests of LWR fuels and materials has been planned in order to study their soundness. By using Oarai Shroud Facility (OSF-1) and Fuel Irradiation Facility with the He-3 gas control system for power lamping test using Boiling Water Capsules (BOCA Irradiation Facility), the irradiation tests with power ramping will be carried out to study the soundness of fuel under LWR Transient condition. OSF-1 is the irradiation facility of shroud type that can insert and eject the capsule under reactor operation, and is composed of 'In-pile Tube', 'Cooling system' and 'Capsule exchange system'. BOCA Irradiation Facility is the facility which simulates irradiation environment of LWR, and is composed of 'Boiling water Capsule', 'Capsule control system' and 'Power control system by He-3'. By using Saturated temperature Capsules and the water environment control system, the material irradiation tests under the water chemistry condition of LWR will be carried out to clarify the mechanism of IASCC. In JMTR, these facilities are in service at the present. However, the detailed design for renewal or remodeling was carried out based on the new design condition in order to be correspondent to the irradiation test plan after restart JMTR operation. In this seismic analysis of the detailed design, each equipment classification and operating state were arranged with 'Japanese technical standards of the structure on nuclear facility for test research' and 'Technical guidelines for seismic design of nuclear power plants on current, and then, stress calculation and evaluation were carried out by FEM piping analysis code 'SAP' and structure analysis code 'ABAQUS'. About the stress of the seismic force, it was proven

  4. Safety analysis of the existing 804 and 845 firing facilities

    International Nuclear Information System (INIS)

    Odell, B.N.

    1986-01-01

    A safety analysis was performed to determine if normal operations and/or potential accidents at the 804 and 845 Firing Facilities at Site 300 could present undue hazards to the general public, peronnel at Site 300, or have an adverse effect on the environment. The normal operation and credible accident that might have an effect on these facilities or have off-site consequence were considered. It was determined by this analysis that all but one of the hazards were either low or of the type or magnitude routinely encountered and/or accepted by the public. The exception was explosives. Since this hazard has the potential for causing significant on-site and minimum off-site consequences, Bunkers 804 and 845 have been classified as moderate hazard facilties per DOE Order 5481.1A. This safety analysis concluded that the operation at these facilities will present no undue risk to the health and safety of LLNL employees or the public

  5. Pressure analysis in ventilation ducts at bituminization facility

    International Nuclear Information System (INIS)

    Kikuchi, Naoki; Iimura, Masato; Takahashi, Yuki; Omori, Eiichi; Yamanouchi, Takamichi

    1997-09-01

    Pressure analysis in cell ventilation ducts at bituminization facility where the fire and explosion accident occured was carried out. This report also describes the results of bench mark calculations for computer code EVENT84 which was used for the accident analysis. The bench mark calculations were performed by comparing the analytical results by EVENT84 code with the experimental data of safety demonstration tests of ventilation system which were carried out by JAERI. We confirmed the applicability of EVENT84 code with the conservative results. The pressure analysis in cell ventilation ducts at bituminization facility were performed by comparing the analytical results of duct pressure by EVENT84 code with the yield stress of destroyed ducts by explosion, in order to estimate the scale of explosion. As a result, we could not explain the damage of ducts quantitatively, but we found the local pressure peaks analytically in downstream ducts where the serious damages were observed. (author)

  6. Promoter Boundaries for the luxCDABE and betIBA-proXWV Operons in Vibrio harveyi Defined by the Method Rapid Arbitrary PCR Insertion Libraries (RAIL).

    Science.gov (United States)

    Hustmyer, Christine M; Simpson, Chelsea A; Olney, Stephen G; Rusch, Douglas B; Bochman, Matthew L; van Kessel, Julia C

    2018-06-01

    Experimental studies of transcriptional regulation in bacteria require the ability to precisely measure changes in gene expression, often accomplished through the use of reporter genes. However, the boundaries of promoter sequences required for transcription are often unknown, thus complicating the construction of reporters and genetic analysis of transcriptional regulation. Here, we analyze reporter libraries to define the promoter boundaries of the luxCDABE bioluminescence operon and the betIBA-proXWV osmotic stress operon in Vibrio harveyi We describe a new method called r apid a rbitrary PCR i nsertion l ibraries (RAIL) that combines the power of arbitrary PCR and isothermal DNA assembly to rapidly clone promoter fragments of various lengths upstream of reporter genes to generate large libraries. To demonstrate the versatility and efficiency of RAIL, we analyzed the promoters driving expression of the luxCDABE and betIBA-proXWV operons and created libraries of DNA fragments from these loci fused to fluorescent reporters. Using flow cytometry sorting and deep sequencing, we identified the DNA regions necessary and sufficient for maximum gene expression for each promoter. These analyses uncovered previously unknown regulatory sequences and validated known transcription factor binding sites. We applied this high-throughput method to gfp , mCherry , and lacZ reporters and multiple promoters in V. harveyi We anticipate that the RAIL method will be easily applicable to other model systems for genetic, molecular, and cell biological applications. IMPORTANCE Gene reporter constructs have long been essential tools for studying gene regulation in bacteria, particularly following the recent advent of fluorescent gene reporters. We developed a new method that enables efficient construction of promoter fusions to reporter genes to study gene regulation. We demonstrate the versatility of this technique in the model bacterium Vibrio harveyi by constructing promoter libraries

  7. Waste Encapsulation and Storage Facility (WESF) Waste Analysis Plan

    International Nuclear Information System (INIS)

    SIMMONS, F.M.

    2000-01-01

    The purpose of this waste analysis plan (WAP) is to document waste analysis activities associated with the Waste Encapsulation and Storage Facility (WESF) to comply with Washington Administrative Code (WAC) 173-303-300(1), (2), (3), (4), (5), and (6). WESF is an interim status other storage-miscellaneous storage unit. WESF stores mixed waste consisting of radioactive cesium and strontium salts. WESF is located in the 200 East Area on the Hanford Facility. Because dangerous waste does not include source, special nuclear, and by-product material components of mixed waste, radionuclides are not within the scope of this documentation. The information on radionuclides is provided only for general knowledge

  8. Thermal stress analysis of the fuel storage facility

    International Nuclear Information System (INIS)

    Chen, W.W.

    1991-12-01

    This paper presents the results of a nonlinear finite-element analysis to determine the structural integrity of the walls of the nuclear fuel storage room in the Radio Isotope Power System Facility of the Fuels and Materials Examination Facility (FMEF) Project. The analysis was performed to assess the effects of thermal loading on the walls that would result from a loss-of-cooling accident. The results obtained from using the same three-dimensional finite-element model with different types of elements, the eight-node brick element and the nonlinear concrete element, and the calculated results using the analytical solutions, are compared. The concrete responses in terms of octahedral normal and shearing stresses are described. The crack and crush states of the concrete were determined on the basis of multiaxial failure criteria

  9. Composition and stratigraphy of the paint layers: investigation on the Madonna dei Fusi by ion beam analysis techniques

    Science.gov (United States)

    Grassi, N.

    2005-06-01

    In the framework of the extensive study on the wood painting "Madonna dei fusi" attributed to Leonardo da Vinci, Ion Beam Analysis (IBA) techniques were used at the Florence accelerator laboratory to get information about the elemental composition of the paint layers. After a brief description of the basic principle and the general features of IBA techniques, we will illustrate in detail how the analysis allowed us to characterise the pigments of original and restored areas and the substrate composition, and to obtain information about the stratigraphy of the painting, also providing an estimate of the paint layer thickness.

  10. Safety analysis and risk assessment of the National Ignition Facility

    International Nuclear Information System (INIS)

    Brereton, S.; McLouth, L.; Odell, B.

    1996-01-01

    The National Ignition Facility (NIF) is a proposed U.S. Department of Energy inertial confinement laser fusion facility. The candidate sites for locating the NIF are: Los Alamos National Laboratory, Sandia National Laboratory, the Nevada Test Site, and Lawrence Livermore National Laboratory (LLNL), the preferred site. The NIF will operate by focusing 192 laser beams onto a tiny deuterium-tritium target located at the center of a spherical target chamber. The NIF mission is to achieve inertial confinement fusion (ICF) ignition, access physical conditions in matter of interest to nuclear weapons physics, provide an above ground simulation capability for nuclear weapons effects testing, and contribute to the development of inertial fusion for electrical power production. The NIF has been classified as a radiological, low hazard facility on the basis of a preliminary hazards analysis and according to the DOE methodology for facility classification. This requires that a safety analysis be prepared under DOE Order 5481.1B, Safety Analysis and Review System. A draft Preliminary Safety Analysis Report (PSAR) has been written, and this will be finalized later in 1996. This paper summarizes the safety issues associated with the operation of the NIF and the methodology used to study them. It provides a summary of the methodology, an overview of the hazards, estimates maximum routine and accidental exposures for the preferred site of LLNL, and concludes that the risks from NIF operations are low

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

    International Nuclear Information System (INIS)

    Mitsutake, Naohiro; Oku, Shinya; Fujii, Ryo; Furui, Yuji; Yasunaga, Hideo

    2008-01-01

    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)

  12. The dynamic analysis facility at the Chalk River Nuclear Laboratories

    International Nuclear Information System (INIS)

    Argue, D.S.; Howatt, W.T.

    1979-10-01

    The Dynamic Analysis Facility at the Chalk River Nuclear Laboratories (CRNL) of Atomic Energy of Canada Limited (AECL) comprises a Hybrid Computer, consisting of two Applied Dynamic International AD/FIVE analog computers and a Digital Equipment Corporation (DEC) PDP-11/55 digital computer, and a Program Development System based on a DEC PDP-11/45 digital computer. This report describes the functions of the various hardware components of the Dynamic Analysis Facility and the interactions between them. A brief description of the software available to the user is also given. (auth)

  13. 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.

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

    International Nuclear Information System (INIS)

    Cook, J.R.

    2000-01-01

    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

  15. A systems analysis approach to nuclear facility siting

    International Nuclear Information System (INIS)

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

    1975-01-01

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

  16. AOX1-Subfamily Gene Members in Olea europaea cv. "Galega Vulgar"-Gene Characterization and Expression of Transcripts during IBA-Induced in Vitro Adventitious Rooting.

    Science.gov (United States)

    Velada, Isabel; Grzebelus, Dariusz; Lousa, Diana; M Soares, Cláudio; Santos Macedo, Elisete; Peixe, Augusto; Arnholdt-Schmitt, Birgit; G Cardoso, Hélia

    2018-02-17

    Propagation of some Olea europaea L. cultivars is strongly limited due to recalcitrant behavior in adventitious root formation by semi-hardwood cuttings. One example is the cultivar "Galega vulgar". The formation of adventitious roots is considered a morphological response to stress. Alternative oxidase (AOX) is the terminal oxidase of the alternative pathway of the plant mitochondrial electron transport chain. This enzyme is well known to be induced in response to several biotic and abiotic stress situations. This work aimed to characterize the alternative oxidase 1 (AOX1)-subfamily in olive and to analyze the expression of transcripts during the indole-3-butyric acid (IBA)-induced in vitro adventitious rooting (AR) process. OeAOX1a (acc. no. MF410318) and OeAOX1d (acc. no. MF410319) were identified, as well as different transcript variants for both genes which resulted from alternative polyadenylation events. A correlation between transcript accumulation of both OeAOX1a and OeAOX1d transcripts and the three distinct phases (induction, initiation, and expression) of the AR process in olive was observed. Olive AOX1 genes seem to be associated with the induction and development of adventitious roots in IBA-treated explants. A better understanding of the molecular mechanisms underlying the stimulus needed for the induction of adventitious roots may help to develop more targeted and effective rooting induction protocols in order to improve the rooting ability of difficult-to-root cultivars.

  17. Vulnerability Analysis of Physical Protection System at Hypothetical Facility

    International Nuclear Information System (INIS)

    Jung, Won Moog; Lee, Ho Jin; Yu, Dong Han; Min, Gyung Sik

    2006-01-01

    Since the 9/11 event in the U.S.A, International terror possibilities has been increasing for nuclear facilities including nuclear power plants(NPPs). It is necessary to evaluate the performance of an existing physical protection system(PPS) at nuclear facilities based on such malevolent acts. A PPS is a complex configuration of detection, delay, and response elements. Detection, delay, and response elements are all important to the analysis and evaluation of a PPS and its effectiveness. Methods are available to analyze a PPS and evaluate its effectiveness. Sandia National Laboratory(SNL) in the U.S.A was developed a System Analysis of Vulnerability to Intrusion (SAVI) computer code for evaluating the effectiveness of PPS against outsider threats. This study presents the vulnerability analysis of the PPS at hypothetical facility using SAVI code that the basic input parameters are from PPS of Hanaro Research Reactor at Korea Atomic Energy Research Institution. It is understand that PPS of research reactor and critical assemblies are deficient that that of NPP and nuclear materials of RRCAS are compact to transport For analysis, first, the site-specific Adversary Sequence Diagrams(ASDs) of the PPS is constructed. It helps to understand the functions of the existing PPS composed of physical areas and Protection Elements(PEs). Then, the most vulnerable path of an ASD as a measure of effectiveness is determined. The results in the analysis can used to suggest the possible PPS upgrades to the most vulnerable paths for the system like research reactor

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

    International Nuclear Information System (INIS)

    Park, Hyun Soo; Kim, Byung Tae; Park, Seong Won; Cho, Soo Haeng; Lee, Yong Rae; Lee, Kyung Ku; Park, Seung Hyub; Hwang, Jeong Ki; Kim, Jeong Mook; Oh, Haeng Yoeb

    1988-12-01

    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)

  19. Waste Sampling and Characterization Facility (WSCF) Complex Safety Analysis

    International Nuclear Information System (INIS)

    MELOY, R.T.

    2003-01-01

    The Waste Sampling and Characterization Facility (WSCF) is an analytical laboratory complex on the Hanford Site that was constructed to perform chemical and low-level radiological analyses on a variety of sample media in support of Hanford Site customer needs. The complex is located in the 600 area of the Hanford Site, east of the 200 West Area. Customers include effluent treatment facilities, waste disposal and storage facilities, and remediation projects. Customers primarily need analysis results for process control and to comply with federal, Washington State, and US. Department of Energy (DOE) environmental or industrial hygiene requirements. This document was prepared to analyze the facility for safety consequences and includes the following steps: Determine radionuclide and highly hazardous chemical inventories; Compare these inventories to the appropriate regulatory limits; Document the compliance status with respect to these limits; and Identify the administrative controls necessary to maintain this status

  20. Aluminium incorporation in AlxGa1-xN/GaN heterostructures: A comparative study by ion beam analysis and X-ray diffraction

    International Nuclear Information System (INIS)

    Redondo-Cubero, A.; Gago, R.; Gonzalez-Posada, F.; Kreissig, U.; Di Forte Poisson, M.-A.; Brana, A.F.; Munoz, E.

    2008-01-01

    The Al content in Al x Ga 1-x N/GaN heterostructures has been determined by X-ray diffraction (XRD) and contrasted with absolute measurements from ion beam analysis (IBA) methods. For this purpose, samples with 0.1 0.2. The assessment of Al incorporation by XRD is quite reliable regarding the average value along the sample thickness. However, XRD analysis tends to overestimate the Al fraction at low contents, which is attributed to the presence of strain within the layer. For the highest Al incorporation, IBA detects a certain Al in-depth compositional profile that should be considered for better XRD data analysis

  1. Use of fire hazard analysis to cost effectively manage facility modifications

    Energy Technology Data Exchange (ETDEWEB)

    Krueger, K., E-mail: kkruger@plcfire.com [PLC Fire Safety Solutions, Fredericton, NB (Canada); Cronk, R., E-mail: rcronk@plcfire.com [PLC Fire Safety Solutions, Mississauga, ON (Canada)

    2014-07-01

    In Canada, licenced Nuclear power facilities, or facilities that process, handle or store nuclear material are required by the Canadian Nuclear Safety Commission to have a change control process in place. These processes are in place to avoid facility modifications that could result in an increase in fire hazards, or degradation of fire protection systems. Change control processes can have a significant impact on budgets associated with plant modifications. A Fire Hazard Analysis (FHA) is also a regulatory requirement for licenced facilities in Canada. An FHA is an extensive evaluation of a facility's construction, nuclear safety systems, fire hazards, and fire protection features. This paper is being presented to outline how computer based data management software can help organize facilities' fire safety information, manage this information, and reduce the costs associated with preparation of FHAs as well as facilities' change control processes. (author)

  2. A new approach to the combination of IBA techniques and wind back trajectory data to determine source contributions to long range transport of fine particle air pollution

    Energy Technology Data Exchange (ETDEWEB)

    Cohen, David D., E-mail: dcz@ansto.gov.au [Australian Nuclear Science and Technology Organisation, Locked Bag 2001, Kirrawee DC, NSW 2232 (Australia); Crawford, Jagoda; Stelcer, Eduard; Atanacio, Armand [Australian Nuclear Science and Technology Organisation, Locked Bag 2001, Kirrawee DC, NSW 2232 (Australia)

    2012-02-15

    A new approach to link HYSPLIT back trajectories to the source of fine particle pollution as characterised by standard IBA techniques is discussed. The example of the long range transport of desert dust from inland Australia across the eastern coast is used to show that over a 10-year period extreme soil events originated from major agricultural regions some 30% of the time and that dust from known deserts are not always the problem.

  3. Life cycle cost estimation and systems analysis of Waste Management Facilities

    International Nuclear Information System (INIS)

    Shropshire, D.; Feizollahi, F.

    1995-01-01

    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

  4. 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.

  5. 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).

  6. Evolution of Interactive Analysis Facilities: from NAF to NAF 2.0

    International Nuclear Information System (INIS)

    Haupt, Andreas; Kemp, Yves; Nowak, Friederike

    2014-01-01

    In 2007, the National Analysis Facility (NAF) was set up within the framework of the Helmholtz Alliance 'Physics at the Terascale', and is located at DESY. Its purpose was and is the provision of an analysis infrastructure for up-to-date research in Germany, complementing the Grid by offering a interactive access to the data. It has been well received within the physics community, and has proven to be a highly successful concept. We will review experiences with the original NAF, and discuss both the resulting motivation and constraints for the transition to an evolved model. We call this new facility the NAF 2.0. We will present a new setup including its building blocks and user handling, and give an overview of the current status. The integration of new communities has broadened the range of the analysis facility beyond its primary focus on LHC and ILC experiments. To finish, an outlook on further developments like the adoption of new technologies will be given.

  7. Shielding analysis of high level waste water storage facilities using MCNP code

    Energy Technology Data Exchange (ETDEWEB)

    Yabuta, Naohiro [Mitsubishi Research Inst., Inc., Tokyo (Japan)

    2001-01-01

    The neutron and gamma-ray transport analysis for the facility as a reprocessing facility with large buildings having thick shielding was made. Radiation shielding analysis consists of a deep transmission calculation for the concrete wall and a skyshine calculation for the space out of the buildings. An efficient analysis with a short running time and high accuracy needs a variance reduction technique suitable for all the calculation regions and structures. In this report, the shielding analysis using MCNP and a discrete ordinate transport code is explained and the idea and procedure of decision of variance reduction parameter is completed. (J.P.N.)

  8. A new facility for rapid neutron activation analysis

    International Nuclear Information System (INIS)

    Zeisler, R.; Makarewicz, M.; Grass, F.; Casta, J.

    1996-01-01

    Many research groups have undertaken efforts on the utilization of short-lived nuclides in a broad spectrum of neutron activation analysis (NAA) applications. The advantages of these approaches are obvious because the information on the sample can be extracted more rapidly. In addition to its other advantages, NAA can become extremely competitive in price and analysis time. Nevertheless, NAA with short-lived nuclides has not gained broad popularity, perhaps because of some difficulties in accuracy and the availability of suitable irradiation facilities. This report discusses the ASTRA reactor for neutron activation analysis capabilities

  9. Accident analysis for aircraft crash into hazardous facilities: DOE standard

    International Nuclear Information System (INIS)

    1996-10-01

    This standard provides the user with sufficient information to evaluate and assess the significance of aircraft crash risk on facility safety without expending excessive effort where it is not required. It establishes an approach for performing a conservative analysis of the risk posed by a release of hazardous radioactive or chemical material resulting from an aircraft crash into a facility containing significant quantities of such material. This can establish whether a facility has a significant potential for an aircraft impact and whether this has the potential for producing significant offsite or onsite consequences. General implementation guidance, screening and evaluation guidelines, and methodologies for the evaluations are included

  10. Preliminary safety analysis report for the Waste Characterization Facility

    International Nuclear Information System (INIS)

    1994-10-01

    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

  11. Social network analysis of duplicative prescriptions: One-month analysis of medical facilities in Japan.

    Science.gov (United States)

    Takahashi, Yoshimitsu; Ishizaki, Tatsuro; Nakayama, Takeo; Kawachi, Ichiro

    2016-03-01

    Duplicative prescriptions refer to situations in which patients receive medications for the same condition from two or more sources. Health officials in Japan have expressed concern about medical "waste" resulting from this practices. We sought to conduct descriptive analysis of duplicative prescriptions using social network analysis and to report their prevalence across ages. We analyzed a health insurance claims database including 1.24 million people from December 2012. Through social network analysis, we examined the duplicative prescription networks, representing each medical facility as nodes, and individual prescriptions for patients as edges. The prevalence of duplicative prescription for any drug class was strongly correlated with its frequency of prescription (r=0.90). Among patients aged 0-19, cough and colds drugs showed the highest prevalence of duplicative prescriptions (10.8%). Among people aged 65 and over, antihypertensive drugs had the highest frequency of prescriptions, but the prevalence of duplicative prescriptions was low (0.2-0.3%). Social network analysis revealed clusters of facilities connected via duplicative prescriptions, e.g., psychotropic drugs showed clustering due to a few patients receiving drugs from 10 or more facilities. Overall, the prevalence of duplicative prescriptions was quite low - less than 10% - although the extent of the problem varied by drug class and age group. Our approach illustrates the potential utility of using a social network approach to understand these practices. Copyright © 2016 Elsevier Ireland Ltd. All rights reserved.

  12. Integration of facility modeling capabilities for nuclear nonproliferation analysis

    International Nuclear Information System (INIS)

    Burr, Tom; Gorensek, M.B.; Krebs, John; Kress, Reid L.; Lamberti, Vincent; Schoenwald, David; Ward, Richard C.

    2012-01-01

    Developing automated methods for data collection and analysis that can facilitate nuclearnonproliferation assessment is an important research area with significant consequences for the effective global deployment of nuclear energy. Facilitymodeling 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 facilitymodeling 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 facilitymodelingcapabilities and illustrates how they could be integrated and utilized for nonproliferationanalysis. The inverse problem of inferring facility conditions based on collected observations is described, along with a proposed architecture and computer framework for utilizing facilitymodeling tools. After considering a representative sampling of key facilitymodelingcapabilities, the proposed integration framework is illustrated with several examples.

  13. Multicriteria analysis of thermal and energy systems for tourist facilities

    International Nuclear Information System (INIS)

    Raguzin, I.

    1999-01-01

    The introductory part of the paper briefly presents the technological, economic and environmental optimisation procedure of thermal and energy systems for tourist facilities with the multicriteria ranging method when choosing an optimum solution. The procedure described includes a systematic analysis of the system's structure, energy-mass balance, balance of costs, environmental impact analysis and the choice of an optimum solution. Special attention was paid to criteria quantification for the choice of solution and the most appropriate ranging method.The procedure's application has been illustrated on an example of a potential tourist facility on the Island of Loinj, i.e. the locality with a potential highest category tourist development. This example includes (a) consumers (heating of rooms, preparation of hot water, heating of swimming pool water and cooling of rooms), and (b) producers (boiler room, cooling engine-rooms, a cogeneration plant and heat pumps). The data have been supplied from the project documentation for the reconstruction of the existing facilities mainly preliminary designs. The multicriteria ranging was conducted based on an appropriate computer programme for problem solution. (author)

  14. PROMPT DOSE ANALYSIS FOR THE NATIONAL IGNITION FACILITY

    International Nuclear Information System (INIS)

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

    2008-01-01

    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 (∼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

  15. Radiochemical analysis of military nuclear facilities

    International Nuclear Information System (INIS)

    Bayramov, A.A.; Bayramova, S.M.

    2012-01-01

    Full text : Radiochemical Analysis is a branch of analytical chemistry comprising an aggregate of methods for qualitatively determining the composition and content of radioisotopes in the products of transformations. Safety and minimization of radiation impact on human and environment are important demand of operation of Military Nuclear Facilities (MNF). In accordance of recommendations of International Commission on Radiological Protection there are next objects of radiochemical analysis: 1) potential sources of radiochemical pollution; 2) environment (objects of environment, human environment including buildings, agricultural production, water, air et al.); 3) human himself (determination of dose from external and internal radiation, chemical poisoning). The chemical analysis can be carried out using, for example, the Gas Chromatography instrument whish separates chemical mixtures and identifies the components at a molecular level. It is one of the most accurate tools for analyzing environmental samples. The Gas Chromatography works on the principle that a mixture will separate into individual substances when heated. The heated gases are carried through a column with an inert gas (such as helium). As the separated substances emerge from the column opening, they flow into the Mass Spectrometry. Mass spectrometry identifies compounds by the mass of the analyte molecule. Newly developed portable Gas Chromatography and Mass Spectrometry are techniques that can be used to separate volatile organic compounds and pesticides. Other uses of Gas Chromatography, combined with other separation and analytical techniques, have been developed for radionuclides, explosive compounds such as royal demolition explosive and trinitrotoluene, and metals. So, based on the many years experience of operation of dangerous MNF, in concordance with norms of radiation and chemical safety it was considered that the tasks of the radiochemical analysis of Military Nuclear Facilities include

  16. AOX1-Subfamily Gene Members in Olea europaea cv. “Galega Vulgar”—Gene Characterization and Expression of Transcripts during IBA-Induced in Vitro Adventitious Rooting

    Science.gov (United States)

    Lousa, Diana; M. Soares, Cláudio; Santos Macedo, Elisete; Arnholdt-Schmitt, Birgit

    2018-01-01

    Propagation of some Olea europaea L. cultivars is strongly limited due to recalcitrant behavior in adventitious root formation by semi-hardwood cuttings. One example is the cultivar ”Galega vulgar”. The formation of adventitious roots is considered a morphological response to stress. Alternative oxidase (AOX) is the terminal oxidase of the alternative pathway of the plant mitochondrial electron transport chain. This enzyme is well known to be induced in response to several biotic and abiotic stress situations. This work aimed to characterize the alternative oxidase 1 (AOX1)-subfamily in olive and to analyze the expression of transcripts during the indole-3-butyric acid (IBA)-induced in vitro adventitious rooting (AR) process. OeAOX1a (acc. no. MF410318) and OeAOX1d (acc. no. MF410319) were identified, as well as different transcript variants for both genes which resulted from alternative polyadenylation events. A correlation between transcript accumulation of both OeAOX1a and OeAOX1d transcripts and the three distinct phases (induction, initiation, and expression) of the AR process in olive was observed. Olive AOX1 genes seem to be associated with the induction and development of adventitious roots in IBA-treated explants. A better understanding of the molecular mechanisms underlying the stimulus needed for the induction of adventitious roots may help to develop more targeted and effective rooting induction protocols in order to improve the rooting ability of difficult-to-root cultivars. PMID:29462998

  17. Depth profile analysis of thin TiOxNy films using standard ion beam analysis techniques and HERDA

    International Nuclear Information System (INIS)

    Markwitz, A.; Dytlewski, N.; Cohen, D.

    1999-01-01

    Ion beam assisted deposition is used to fabricate thin titanium oxynitride films (TiO x N y ) at Industrial Research (typical film thickness 100nm). At the Institute of Geological and Nuclear Sciences, the thin films are analysed using non-destructive standard ion beam analysis (IBA) techniques. High-resolution titanium depth profiles are measured with RBS using 1.5MeV 4 He + ions. Non-resonant nuclear reaction analysis (NRA) is performed for investigating the amounts of O and N in the deposited films using the reactions 16 O(d,p) 17 O at 920 keV and 14 N(d,α) 12 C at 1.4 MeV. Using a combination of these nuclear techniques, the stoichiometry as well as the thickness of the layers is revealed. However, when oxygen and nitrogen depth profiles are required for investigating stoichiometric changes in the films, additional nuclear analysis techniques such as heavy ion elastic recoil detection (HERDA) have to be applied. With HERDA, depth profiles of N, O, and Ti are measured simultaneously. In this paper comparative IBA measurement s of TiO x N y films with different compositions are presented and discussed

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

    International Nuclear Information System (INIS)

    Chilian, C.; Kennedy, G.

    2010-01-01

    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)

  19. Neutronics analysis of International Fusion Material Irradiation Facility (IFMIF). Japanese contributions

    International Nuclear Information System (INIS)

    Oyama, Yukio; Noda, Kenji; Kosako, Kazuaki.

    1997-10-01

    In fusion reactor development for demonstration reactor, i.e., DEMO, materials tolerable for D-T neutron irradiation are absolutely required for both mechanical and safety point of views. For this requirement, several kinds of low activation materials were proposed. However, experimental data by actual D-T fusion neutron irradiation have not existed so far because of lack of fusion neutron irradiation facility, except fundamental radiation damage studies at very low neutron fluence. Therefore such a facility has been strongly requested. According to agreement of need for such a facility among the international parties, a conceptual design activity (CDA) of International Fusion Material Irradiation Facility (IFMIF) has been carried out under the frame work of the IEA-Implementing Agreement. In the activity, a neutronics analysis on irradiation field optimization in the IFMIF test cell was performed in three parties, Japan, US and EU. As the Japanese contribution, the present paper describes a neutron source term as well as incident deuteron beam angle optimization of two beam geometry, beam shape (foot print) optimization, and dpa, gas production and heating estimation inside various material loading Module, including a sensitivity analysis of source term uncertainty to the estimated irradiation parameters. (author)

  20. Safeguards systems analysis research and development and the practice of safeguards at DOE facilities

    International Nuclear Information System (INIS)

    Zack, N.R.; Thomas, K.E.; Markin, J.T.; Tape, J.W.

    1991-01-01

    Los Alamos Safeguards Systems Group personnel interact with Department of Energy (DOE) nuclear materials processing facilities in a number of ways. Among them are training courses, formal technical assistance such as developing information management or data analysis software, and informal ad hoc assistance especially in reviewing and commenting on existing facility safeguards technology and procedures. These activities are supported by the DOE Office of Safeguards and Security, DOE Operations Offices, and contractor organizations. Because of the relationships with the Operations Office and facility personnel, the Safeguards Systems Group research and development (R and D) staff have developed an understanding of the needs of the entire complex. Improved safeguards are needed in areas such as materials control activities, accountability procedures and techniques, systems analysis and evaluation methods, and material handling procedures. This paper surveys the generic needs for efficient and cost effective enhancements in safeguards technologies and procedures at DOE facilities, identifies areas where existing safeguards R and D products are being applied or could be applied, and sets a direction for future systems analysis R and D to address practical facility safeguards needs

  1. Ion beam analysis techniques applied to large scale pollution studies

    Energy Technology Data Exchange (ETDEWEB)

    Cohen, D D; Bailey, G; Martin, J; Garton, D; Noorman, H; Stelcer, E; Johnson, P [Australian Nuclear Science and Technology Organisation, Lucas Heights, NSW (Australia)

    1994-12-31

    Ion Beam Analysis (IBA) techniques are ideally suited to analyse the thousands of filter papers a year that may originate from a large scale aerosol sampling network. They are fast multi-elemental and, for the most part, non-destructive so other analytical methods such as neutron activation and ion chromatography can be performed afterwards. ANSTO in collaboration with the NSW EPA, Pacific Power and the Universities of NSW and Macquarie has established a large area fine aerosol sampling network covering nearly 80,000 square kilometres of NSW with 25 fine particle samplers. This network known as ASP was funded by the Energy Research and Development Corporation (ERDC) and commenced sampling on 1 July 1991. The cyclone sampler at each site has a 2.5 {mu}m particle diameter cut off and runs for 24 hours every Sunday and Wednesday using one Gillman 25mm diameter stretched Teflon filter for each day. These filters are ideal targets for ion beam analysis work. Currently ANSTO receives 300 filters per month from this network for analysis using its accelerator based ion beam techniques on the 3 MV Van de Graaff accelerator. One week a month of accelerator time is dedicated to this analysis. Four simultaneous accelerator based IBA techniques are used at ANSTO, to analyse for the following 24 elements: H, C, N, O, F, Na, Al, Si, P, S, Cl, K, Ca, Ti, V, Cr, Mn, Fe, Cu, Ni, Co, Zn, Br and Pb. The IBA techniques were proved invaluable in identifying sources of fine particles and their spatial and seasonal variations accross the large area sampled by the ASP network. 3 figs.

  2. Ion beam analysis techniques applied to large scale pollution studies

    Energy Technology Data Exchange (ETDEWEB)

    Cohen, D.D.; Bailey, G.; Martin, J.; Garton, D.; Noorman, H.; Stelcer, E.; Johnson, P. [Australian Nuclear Science and Technology Organisation, Lucas Heights, NSW (Australia)

    1993-12-31

    Ion Beam Analysis (IBA) techniques are ideally suited to analyse the thousands of filter papers a year that may originate from a large scale aerosol sampling network. They are fast multi-elemental and, for the most part, non-destructive so other analytical methods such as neutron activation and ion chromatography can be performed afterwards. ANSTO in collaboration with the NSW EPA, Pacific Power and the Universities of NSW and Macquarie has established a large area fine aerosol sampling network covering nearly 80,000 square kilometres of NSW with 25 fine particle samplers. This network known as ASP was funded by the Energy Research and Development Corporation (ERDC) and commenced sampling on 1 July 1991. The cyclone sampler at each site has a 2.5 {mu}m particle diameter cut off and runs for 24 hours every Sunday and Wednesday using one Gillman 25mm diameter stretched Teflon filter for each day. These filters are ideal targets for ion beam analysis work. Currently ANSTO receives 300 filters per month from this network for analysis using its accelerator based ion beam techniques on the 3 MV Van de Graaff accelerator. One week a month of accelerator time is dedicated to this analysis. Four simultaneous accelerator based IBA techniques are used at ANSTO, to analyse for the following 24 elements: H, C, N, O, F, Na, Al, Si, P, S, Cl, K, Ca, Ti, V, Cr, Mn, Fe, Cu, Ni, Co, Zn, Br and Pb. The IBA techniques were proved invaluable in identifying sources of fine particles and their spatial and seasonal variations accross the large area sampled by the ASP network. 3 figs.

  3. A study on safety analysis methodology in spent fuel dry storage facility

    Energy Technology Data Exchange (ETDEWEB)

    Che, M. S.; Ryu, J. H.; Kang, K. M.; Cho, N. C.; Kim, M. S. [Hanyang Univ., Seoul (Korea, Republic of)

    2004-02-15

    Collection and review of the domestic and foreign technology related to spent fuel dry storage facility. Analysis of a reference system. Establishment of a framework for criticality safety analysis. Review of accident analysis methodology. Establishment of accident scenarios. Establishment of scenario analysis methodology.

  4. 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.

  5. 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.

  6. Data Analysis Facility (DAF)

    Science.gov (United States)

    1991-01-01

    NASA-Dryden's Data Analysis Facility (DAF) provides a variety of support services to the entire Dryden community. It provides state-of-the-art hardware and software systems, available to any Dryden engineer for pre- and post-flight data processing and analysis, plus supporting all archival and general computer use. The Flight Data Access System (FDAS) is one of the advanced computer systems in the DAF, providing for fast engineering unit conversion and archival processing of flight data delivered from the Western Aeronautical Test Range. Engineering unit conversion and archival formatting of flight data is performed by the DRACO program on a Sun 690MP and an E-5000 computer. Time history files produced by DRACO are then moved to a permanent magneto-optical archive, where they are network-accessible 24 hours a day, 7 days a week. Pertinent information about the individual flights is maintained in a relational (Sybase) database. The DAF also houses all general computer services, including; the Compute Server 1 and 2 (CS1 and CS2), the server for the World Wide Web, overall computer operations support, courier service, a CD-ROM Writer system, a Technical Support Center, the NASA Dryden Phone System (NDPS), and Hardware Maintenance.

  7. 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.

  8. The German National Analysis Facility as a tool for ATLAS analyses

    International Nuclear Information System (INIS)

    Ehrenfeld, W; Leffhalm, K; Mehlhase, S

    2011-01-01

    In 2008 the German National Analysis Facility (NAF) at DESY was established. It is attached to and builds on top of DESY Grid infrastructure. The facility is designed to provide the best possible analysis infrastructure for high energy particle physics of the ATLAS, CMS, LHCb and ILC experiments. The Grid and local infrastructure of the NAF is reviewed with a focus on the ATLAS part. Both parts include large scale storage and a batch system. Emphasis is put on ATLAS specific customisation and utilisation of the NAF. This refers not only to the NAF components but also to the different components of the ATLAS analysis framework. Experience from operating and supporting ATLAS users on the NAF is presented in this paper. The ATLAS usage of the different components are shown including some typical use cases of user analysis. Finally, the question is addressed, if the design of the NAF meets the ATLAS expectations for efficient data analysis in the era of LHC data taking.

  9. The Prompt Gamma Neutron Activation Analysis Facility at ICN-Pitesti

    International Nuclear Information System (INIS)

    Barbos, D.; Paunoiu, C.; Mladin, M.; Cosma, C.

    2008-01-01

    PGNAA is a very widely applicable technique for determining the presence and amount of many elements simultaneously in samples ranging in size from micrograms to many grams. PGNAA is characterized by its capability for nondestructive multi-elemental analysis and its ability to analyse elements that cannot be determined by INAA. By means of this PGNAA method we are able to increase the performance of INAA method. A facility has been developed at Institute for Nuclear Research-Pitesti so that the unique features of prompt gamma-ray neutron activation analysis can be used to measure trace and major elements in samples. The facility is linked at the radial neutron beam tube at ACPR-TRIGA reactor. During the PGNAA-facility is in use the ACPR reactor will be operated in steady-state mode at 250 KW maximum power. The facility consists of a radial beam-port, external sample position with shielding, and induced prompt gamma-ray counting system.Thermal neutron flux with energy lower than cadmium cut-off at the sample position was measured using thin gold foil is: φ scd = 1.10 6 n/cm 2 /s with a cadmium ratio of:80.The gamma-ray detection system consist of an HpGe detector of 16% efficiency (detector model GC1518) with 1.85 keV resolution capability. The HpGe is mounted with its axis at 90 deg. with respect to the incident neutron beam at distance about 200mm from the sample position. To establish the performance capabilities of the facility, irradiation of pure element or sample compound standards were performed to identify the gama-ray energies from each element and their count rates

  10. 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.

  11. Time-domain soil-structure interaction analysis of nuclear facilities

    International Nuclear Information System (INIS)

    Coleman, Justin L.; Bolisetti, Chandrakanth; Whittaker, Andrew S.

    2016-01-01

    The Nuclear Regulatory Commission (NRC) regulation 10 CFR Part 50 Appendix S requires consideration of soil-structure interaction (SSI) in nuclear power plant (NPP) analysis and design. Soil-structure interaction analysis for NPPs is routinely carried out using guidance provided in the ASCE Standard 4-98 titled “Seismic Analysis of Safety-Related Nuclear Structures and Commentary”. This Standard, which is currently under revision, provides guidance on linear seismic soil-structure-interaction (SSI) analysis of nuclear facilities using deterministic and probabilistic methods. A new appendix has been added to the forthcoming edition of ASCE Standard 4 to provide guidance for time-domain, nonlinear SSI (NLSSI) analysis. Nonlinear SSI analysis will be needed to simulate material nonlinearity in soil and/or structure, static and dynamic soil pressure effects on deeply embedded structures, local soil failure at the foundation-soil interface, nonlinear coupling of soil and pore fluid, uplift or sliding of the foundation, nonlinear effects of gaps between the surrounding soil and the embedded structure and seismic isolation systems, none of which can be addressed explicitly at present. Appendix B of ASCE Standard 4 provides general guidance for NLSSI analysis but will not provide a methodology for performing the analysis. This paper provides a description of an NLSSI methodology developed for application to nuclear facilities, including NPPs. This methodology is described as series of sequential steps to produce reasonable results using any time-domain numerical code. These steps require some numerical capabilities, such as nonlinear soil constitutive models, which are also described in the paper.

  12. Ion beam analysis fundamentals and applications

    CERN Document Server

    Nastasi, Michael; Wang, Yongqiang

    2015-01-01

    Ion Beam Analysis: Fundamentals and Applications explains the basic characteristics of ion beams as applied to the analysis of materials, as well as ion beam analysis (IBA) of art/archaeological objects. It focuses on the fundamentals and applications of ion beam methods of materials characterization.The book explains how ions interact with solids and describes what information can be gained. It starts by covering the fundamentals of ion beam analysis, including kinematics, ion stopping, Rutherford backscattering, channeling, elastic recoil detection, particle induced x-ray emission, and nucle

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

    International Nuclear Information System (INIS)

    BISHOP, G.E.

    2000-01-01

    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

  14. 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)

    Mitsutake, Naohiro; Fujii, Ryo; Oku, Shinya; Furui, Yuji; Yasunaga, Hideo

    2007-01-01

    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)

  15. Domestic round robin exercise on analysis of uranium for nuclear material handling facilities in Japan

    International Nuclear Information System (INIS)

    Kato, Yoshiyasu; Nagai, Kohta; Handa, Takamitsu; Inoue, Shin-ichi; Sato, Yoshihiro

    2016-01-01

    Interlaboratory comparison programme as well as internal quality control system is an effective tool for an analytical laboratory responsible to nuclear material accountancy of a nuclear facility to maintain and enhance its capability for analysis. However, it is a burden on nuclear material handling facilities in Japan to attend interlaboratory comparison programme run by overseas institutions because of high costs and complicated procedure for importing nuclear materials, and therefore facilities which can participate in such international programme would be limited. Nuclear Material Control Center has hence started and organised an annual domestic round robin exercise on analysis of uranium standard materials, funded by the Japan Safeguards Office of the Nuclear Regulation Authority, since 2008 to enhance analytical capability of Japanese Facilities. The outline of the round robin exercise will be given and the results of uranium isotopic and concentration analysis reported by participant facilities from 2008 to 2015 will be summarised in the presentation. (author)

  16. BUSTED BUTTE TEST FACILITY GROUND SUPPORT CONFIRMATION ANALYSIS

    International Nuclear Information System (INIS)

    Bonabian, S.

    1998-01-01

    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

  17. Utilization and facility of neutron activation analysis in HANARO research reactor

    International Nuclear Information System (INIS)

    Chung, Y.S.; Chung, Y.J.; Moon, J.H.

    1998-01-01

    The facilities of neutron activation analysis within a multi-purpose research reactor (HANARO) are described and the main applications of Neutron activation analysis (NAA) in Korea are reviewed. The sample irradiation tube, automatic and manual pneumatic transfer system, are installed at three irradiation holes. One irradiation hole is lined with a cadmium tube for epithermal-nal NAA. The performance of the NAA facility was examined to identify the characteristics of tube transfer system, irradiation sites and polyethylene irradiation capsule. The available thermal neutron flux with each irradiation site are in the range of 3.9x10 13 -1.6x10 14 n/cm 2 ·s and cadmium ratios are 15-250. Neutron activation analysis has been applied in the trace component analysis of nuclear, geological, biological, environmental and high purity materials and various polymers for research and development. Analytical services and the latest analytical results are summarized. (author)

  18. Phase 1 sampling and analysis plan for the 304 Concretion Facility closure activities

    International Nuclear Information System (INIS)

    Adler, J.G.

    1994-01-01

    This document provides guidance for the initial (Phase 1) sampling and analysis activities associated with the proposed Resource Conservation and Recovery Act of 1976 (RCRA) clean closure of the 304 Concretion Facility. Over its service life, the 304 Concretion Facility housed the pilot plants associated with cladding uranium cores, was used to store engineering equipment and product chemicals, was used to treat low-level radioactive mixed waste, recyclable scrap uranium generated during nuclear fuel fabrication, and uranium-titanium alloy chips, and was used for the repackaging of spent halogenated solvents from the nuclear fuels manufacturing process. The strategy for clean closure of the 304 Concretion Facility is to decontaminate, sample (Phase 1 sampling), and evaluate results. If the evaluation indicates that a limited area requires additional decontamination for clean closure, the limited area will be decontaminated, resampled (Phase 2 sampling), and the result evaluated. If the evaluation indicates that the constituents of concern are below action levels, the facility will be clean closed. Or, if the evaluation indicates that the constituents of concern are present above action levels, the condition of the facility will be evaluated and appropriate action taken. There are a total of 37 sampling locations comprising 12 concrete core, 1 concrete chip, 9 soil, 11 wipe, and 4 asphalt core sampling locations. Analysis for inorganics and volatile organics will be performed on the concrete core and soil samples. Separate concrete core samples will be required for the inorganic and volatile organic analysis (VOA). Analysis for inorganics only will be performed on the concrete chip, wipe, and asphalt samples

  19. A safety decision analysis for Saudi Arabian nuclear research facility

    International Nuclear Information System (INIS)

    Abulfaraj, W.H.; Abdul-Fattah, A.F.

    1985-01-01

    Establishment of a nuclear research facility should be the first step in planning for introducing the nuclear energy to Saudi Arabia. The fuzzy set decision theory is selected among different decision theories to be applied for this analysis. Four research reactors from USA are selected for the present study. The IFDA computer code, based on the fuzzy set theory is applied. Results reveal that the FNR reactor is the best alternative for the case of Saudi Arabian nuclear research facility, and MITR is the second best. 17 refs

  20. Analysis of a shield design for a DT neutron generator test facility.

    Science.gov (United States)

    Chichester, D L; Pierce, G D

    2007-10-01

    Independent numerical simulations have been performed using the MCNP5 and SCALE5 radiation transport codes to evaluate the effectiveness of a concrete facility designed to shield personnel from neutron radiation emitted from DT neutron generators. The analysis considered radiation source terms of 14.1 MeV monoenergetic neutrons located at three discrete locations within the two test vaults in the facility, calculating neutron and photon dose rates at 44 locations around the facility using both codes. In addition, dose rate contours were established throughout the facility using the MCNP5 mesh tally feature. Neutron dose rates calculated outside of the facility are predicted to be below 0.01 mrem/h at all locations when all neutron generator source terms are operating within the facility. Similarly, the neutron dose rate in one empty test vault when the adjacent test vault is being utilized is also less then 0.01 mrem/h. For most calculation locations outside the facility the photon dose rates were less then the neutron dose rates by a factor of 10 or more.

  1. Implementation of ionoluminescence in the AGLAE scanning external microprobe

    International Nuclear Information System (INIS)

    Pichon, L.; Calligaro, T.; Gonzalez, V.; Lemasson, Q.; Moignard, B.; Pacheco, C.

    2015-01-01

    The scope of this work is to present the implementation of an IBIL imaging system in the scanning external microprobe of the AGLAE facility so as to correlate luminescence and composition maps provided by PIXE, RBS and PIGE. The challenging integration of the optical spectrometer, due to incompatibility of acquisition timings and data formats with the other IBA channels has motivated the development of a specific acquisition system. This article details the IBIL setup and explains the technical solutions retained for the coupling of IBIL with IBA techniques in order to produce fast and large IBIL-IBA maps. The IBIL maps stored in the same format as the PIXE, RBS and PIGE ones can be visualised and compared using the dedicated AGLAEmap program or the PyMCA processing package. An example of such a coupled mapping on Mesoamerican jade is presented to emphasise the interest of performing simultaneously IBA and IBIL large mappings

  2. Utilization and facility of neutron activation analysis in HANARO research reactor

    Energy Technology Data Exchange (ETDEWEB)

    Chung, Y S; Chung, Y J; Moon, J H [Korea Atomic Energy Research Institute, P.O.Box 105 Yusong, 305-600, Taejon (Korea, Republic of)

    1998-07-01

    The facilities of neutron activation analysis within a multi-purpose research reactor (HANARO) are described and the main applications of Neutron activation analysis (NAA) in Korea are reviewed. The sample irradiation tube, automatic and manual pneumatic transfer system, are installed at three irradiation holes. One irradiation hole is lined with a cadmium tube for epithermal-nal NAA. The performance of the NAA facility was examined to identify the characteristics of tube transfer system, irradiation sites and polyethylene irradiation capsule. The available thermal neutron flux with each irradiation site are in the range of 3.9x10{sup 13}-1.6x10{sup 14} n/cm{sup 2}{center_dot}s and cadmium ratios are 15-250. Neutron activation analysis has been applied in the trace component analysis of nuclear, geological, biological, environmental and high purity materials and various polymers for research and development. Analytical services and the latest analytical results are summarized. (author)

  3. Safety analysis report upgrade program at the Plutonium Facility, Los Alamos National Laboratory

    International Nuclear Information System (INIS)

    Pan, P.Y.

    1993-01-01

    Plutonium research and development activities have resided at the Los Alamos National Laboratory (LANL) since 1943. The function of the Plutonium Facility (PF-4) has been to perform basic special nuclear materials research and development and to support national defense and energy programs. The original Final Safety Analysis Report (FSAR) for PF-4 was approved by DOE in 1978. This FSAR analyzed design-basis and bounding accidents. In 1986, DOE/AL published DOE/AL Order 5481.1B, ''Safety Analysis and Review System'', as a requirement for preparation and review of safety analyses. To meet the new DOE requirements, the Facilities Management Group of the Nuclear Material Technology Division submitted a draft FSAR to DOE for approval in April 1991. This draft FSAR analyzed the new configurations and used a limited-scope probabilistic risk analysis for accident analysis. During the DOE review of the draft FSAR, DOE Order 5480.23 ''Nuclear Safety Analysis Reports'', was promulgated and was later officially released in April 1992. The new order significantly expands the scope, preparation, and maintenance efforts beyond those required in DOE/AL Order 5481.1B by requiring: description of institutional and human-factor safety programs; clear definitions of all facility-specific safety commitments; more comprehensive and detailed hazard assessment; use of new safety analysis methods; and annual updates of FSARs. This paper describes the safety analysis report (SAR) upgrade program at the Plutonium Facility in LANL. The SAR upgrade program is established to meet the requirements in DOE Order 5480.23. Described in this paper are the SAR background, authorization basis for operations, hazard classification, and technical program elements

  4. Engineering evaluation/cost analysis for the 105-DR and 105-F Reactor facilities and ancillary facilities

    International Nuclear Information System (INIS)

    Coenenberg, E.T.

    1998-01-01

    This document presents the results of an engineering evaluation/cost analysis (EE/CA) that was conducted to evaluate alternatives to address final disposition of the 105-DR and 105-F Reactor Buildings (subsequently referred to as facilities), including the fuel storage basins (FSB) and below-grade portions of the reactors, excluding the reactor blocks. The reactor blocks will remain in a safe storage mode for up to 75 years as identified in the Record the Decision (ROD) (58 FR 48509) for the Environmental Impact Statement (EIS), Decommissioning of Eight Surplus Production Reactors at the Hanford Site, Richland, Washington (DOE 1992a). This EE/CA also addresses final disposition of four ancillary facilities: 116-D and 116-DR Exhaust Air Stacks, 117-DR Exhaust Filter Building, and 119-DR Exhaust Air Sample Building. The 105-DR and 105-F facilities are located in the 100-D and 100-F Areas of the Hanford Site. In November 1989, the 100 Area of the Hanford Site was placed on the U.S. Environmental Protection Agency's (EPA) National Priorities List (NPL) under the Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA). The 100 Area NPL includes the 100-D Area (which includes the 100-DR site) and the 100-F Area, which are in various stages of the remediation process. It has been determined by DOE that hazardous substances in the 105-DR, 105-F, and the four ancillary facilities may present a potential threat to human health or the environment, and that a non-time critical removal action at these facilities is warranted. To help determine the most appropriate action, DOE, in cooperation with the Washington State Department of Ecology (Ecology) and the EPA, has prepared this EE/CA. The scope of the evaluation includes the 105-DR and 105-F facilities and the four ancillary facilities. The 116-DR and 117-DR facilities are located within the boundaries of the 105-DR Large Sodium Fire Facility Treatment, Storage, and Disposal (TSD) unit, which is

  5. The upgrading of the cyclic neutron activation analysis facility at the Dalat research reactor

    International Nuclear Information System (INIS)

    Van Doanh Ho; Manh Dung Ho; Quang Thien Tran; Dong Vu Cao; Thanh Viet Ha

    2018-01-01

    The cyclic neutron activation analysis (CNAA) facility based on a pneumatic transfer system for short irradiation and rapid counting has recently been upgraded at the Dalat research reactor. The original facility was only designed for single irradiation. Therefore, this work has aimed to upgrade both hardware and software for the cyclic irradiation. In this paper, the upgrading of the facility for CNAA was described. Irradiation time of the facility were calibrated, thereby reducing irradiation time to seconds with precision. The accuracy and sensitivity of CNAA based-on the upgraded facility were assessed by determination of some short-lived nuclides. (author)

  6. Analysis of Atorvastatin in Commercial Solid Drugs using the TT-PIGE Technique

    International Nuclear Information System (INIS)

    Younes, G; Zahraman, K; Nsouli, B; Bejjani, A; Mahmoud, R; El-Yazbi, F

    2008-01-01

    The quantification of the active ingredient (Al) in drugs is a crucial and important step in the drug quality control process. This is usually performed by using wet chemical techniques like LC-MS, UV spectrophotometry and other appropriate organic analytical methods. In the case of an active ingredient contains specific heteroatoms (F, S, Cl), elemental IBA techniques can be explored for molecular quantification. IBA techniques permit the analysis of the sample under solid form, without any laborious sample preparations. This is an advantage when the number of sample is relatively large. In this work, we demonstrate the ability of the Thick Target PIGE technique for rapid and accurate quantification of low concentration AtorvastatinTM in three commercial anti-hyperlipidemic drugs (Lipitor, Liponorm and Storvas). (author)

  7. Analysis of Atorvastatin in Commercial Solid Drugs using the TT-PIGE Technique

    Energy Technology Data Exchange (ETDEWEB)

    Younes, G [Beirut Arab University, Faculty of Science, Chemistry Department Beirut (Lebanon); Zahraman, K; Nsouli, B; Bejjani, A [Lebanese Atomic Energy Commission, National Council for Scientific Research, Beirut (Lebanon); Mahmoud, R; El-Yazbi, F [Beirut Arab University, Faculty of Pharmacy, Department of Pharmaceutical and Analytical Chemistry, Beirut (Lebanon)

    2008-07-01

    The quantification of the active ingredient (Al) in drugs is a crucial and important step in the drug quality control process. This is usually performed by using wet chemical techniques like LC-MS, UV spectrophotometry and other appropriate organic analytical methods. In the case of an active ingredient contains specific heteroatoms (F, S, Cl), elemental IBA techniques can be explored for molecular quantification. IBA techniques permit the analysis of the sample under solid form, without any laborious sample preparations. This is an advantage when the number of sample is relatively large. In this work, we demonstrate the ability of the Thick Target PIGE technique for rapid and accurate quantification of low concentration AtorvastatinTM in three commercial anti-hyperlipidemic drugs (Lipitor, Liponorm and Storvas). (author)

  8. Engineering evaluation/cost analysis for the 233-S Plutonium Concentration Facility

    International Nuclear Information System (INIS)

    Rugg, J.E.

    1996-08-01

    The 100, 200, 300 and 1100 Areas of the Hanford Site were placed on the U. S. Environmental Protection Agency's National Priorities List in November 1989 under the Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA). Located in the 200 Area is the deactivated 233-S Plutonium Concentration Facility (used in the REDOX process). The facility has undergone severe degradation due to exposure to extreme weather conditions. An expedited response is proposed to ensure protection of human health and the environment. The Department of Energy, Richland Operations Office (RL) in cooperation with the Washington State Department of Ecology, has prepared this Engineering Evaluation/Cost Analysis pursuant to CERCLA. Based on the evaluation, RL has determined that hazardous substances in the 233-S Facility may present a potential threat to human health or the environment, and that an expedited removal action is warranted for decommissioning of the facility

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

    International Nuclear Information System (INIS)

    Weidert, J.R.

    1997-01-01

    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

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

    International Nuclear Information System (INIS)

    Mihalic, M.A.

    1998-02-01

    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

  11. Analysis of occupational doses in radioactive and nuclear facilities

    International Nuclear Information System (INIS)

    Curti, A.; Gomez P, I.; Pardo, G.; Thomasz, E.

    1996-01-01

    Occupational doses were analyzed in the most important nuclear and radioactive facilities in Argentina, on the period 1988-1994. The areas associated with uranium mining and milling, and medical uses of radiation facilities were excluded from this analysis. The ICRP publication 60 recommendations, adopted in 1990, and enforced in Argentine in 1994, keep the basic criteria of dose limitation system and recommend a substantial reduction in the dose limits. The reduction of the dose limits will affect the individual dose distributions, principally in those installations with occupational doses close to 50 mSv. It were analyzed Occupational doses, principally in the following facilities: Atucha-I and Embalse Nuclear Power Plants, radioisotope production plants, research reactors and radioactive waste management plants. The highest doses were identified in each facility, as well as the task associated with them. Trends in the individual dose distribution and collective and average doses were analyzed. It is concluded, that no relevant difficulties should appear in accomplishing with the basic standards for radiological safety, except for the Atucha-I Nuclear Power Plant. In this NPP a significant effort for the optimization of radiological safety procedures in order to diminish the occupational doses, and a change of the fuel channels by new ones free of cobalt are being carried out. (authors). 4 refs., 3 figs., 3 tabs

  12. A decision analysis of an exploratory studies facility

    International Nuclear Information System (INIS)

    Merkhofer, M.W.; Gnirk, P.

    1991-01-01

    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

  13. An analysis of decommissioning costs for the AFRRI TRIGA reactor facility

    International Nuclear Information System (INIS)

    Forsbacka, Matt

    1990-01-01

    A decommissioning cost analysis for the AFRRI TRIGA Reactor Facility was made. AFRRI is not at this time suggesting that the AFRRI TRIGA Reactor Facility be decommissioned. This report was prepared to be in compliance with paragraph 50.33 of Title 10, Code of Federal Regulations which requires the assurance of availability of future decommissioning funding. The planned method of decommissioning is the immediate decontamination of the AFRRI TRIGA Reactor site to allow for restoration of the site to full public access - this is called DECON. The cost of DECON for the AFRRI TRIGA Reactor Facility in 1990 dollars is estimated to be $3,200,000. The anticipated ancillary costs of facility site demobilization and spent fuel shipment is an additional $600,000. Thus the total cost of terminating reactor operations at AFRRI will be about $3,800,000. The primary basis for this cost estimate is a study of the decommissioning costs of a similar reactor facility that was performed by Battelle Pacific Northwest Laboratory (PNL) as provided in USNRC publication NUREG/CR-1756. The data in this study were adapted to reflect the decommissioning requirements of the AFRRI TRIGA. (author)

  14. Environmental analysis of the operation of the ERDA facilities in Oak Ridge

    International Nuclear Information System (INIS)

    McWherter, J.R.

    1975-01-01

    An analysis of the environmental effects of current ERDA operations in Oak Ridge is being conducted to establish a baseline for the consideration of the environmental effects of additional facilities or modified operations in the future. An extensive ecological survey has been conducted for about one year; social and economic data were obtained; and an archaeological survey of the area was made. The facilities were described and the effluents associated with operations were quantified to the extent practical. The effects of effluent releases to the environment are being analyzed. The social effects of the ERDA facilities in Oak Ridge are also being studied. (auth)

  15. 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...

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

    Energy Technology Data Exchange (ETDEWEB)

    JOHNSON, B.H.

    1999-08-19

    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.

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

    International Nuclear Information System (INIS)

    JOHNSON, B.H.

    1999-01-01

    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

  18. Surface Fire Hazards Analysis Technical Report-Constructor Facilities

    International Nuclear Information System (INIS)

    Flye, R.E.

    2000-01-01

    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

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

    International Nuclear Information System (INIS)

    K.D. Draper

    2005-01-01

    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

  20. Natural phenomena risk analysis - an approach for the tritium facilities 5480.23 SAR natural phenomena hazards accident analysis

    International Nuclear Information System (INIS)

    Cappucci, A.J. Jr.; Joshi, J.R.; Long, T.A.; Taylor, R.P.

    1997-01-01

    A Tritium Facilities (TF) Safety Analysis Report (SAR) has been developed which is compliant with DOE Order 5480.23. The 5480.23 SAR upgrades and integrates the safety documentation for the TF into a single SAR for all of the tritium processing buildings. As part of the TF SAR effort, natural phenomena hazards (NPH) were analyzed. A cost effective strategy was developed using a team approach to take advantage of limited resources and budgets. During development of the Hazard and Accident Analysis for the 5480.23 SAR, a strategy was required to allow maximum use of existing analysis and to develop a cost effective graded approach for any new analysis in identifying and analyzing the bounding accidents for the TF. This approach was used to effectively identify and analyze NPH for the TF. The first part of the strategy consisted of evaluating the current SAR for the RTF to determine what NPH analysis could be used in the new combined 5480.23 SAR. The second part was to develop a method for identifying and analyzing NPH events for the older facilities which took advantage of engineering judgment, was cost effective, and followed a graded approach. The second part was especially challenging because of the lack of documented existing analysis considered adequate for the 5480.23 SAR and a limited budget for SAR development and preparation. This paper addresses the strategy for the older facilities

  1. Atmospheric Pathway Screening Analysis for Saltstone Disposal Facility Vault 4

    International Nuclear Information System (INIS)

    COOK, JAMES

    2004-01-01

    A sequential screening process using a methodology developed by the National Council on Radiation Protection and Measurements, professional judgment and process knowledge has been used to produce a list of radionuclides requiring detailed analysis to derive disposal limits for the Saltstone Disposal Facility based on the atmospheric pathway

  2. Engineering evaluation/cost analysis for the 233-S Plutonium Concentration Facility

    International Nuclear Information System (INIS)

    1997-01-01

    The deactivated 233-S Plutonium Concentration Facility (233-S Facility) is located in the 200 Area. The facility has undergone severe degradation due to exposure to extreme weather conditions. A rapid freeze and thaw cycle occurred at the Hanford Site during February 1996, which caused cracking to occur on portions of the building's roof. This has resulted in significantly infiltration of water into the facility, which provides a pathway for potential release of radioactive material into the environment (air and/or ground). The weather caused several existing cracks in the concrete portions of the structure to lengthen, increasing the potential for failed confinement of the radioactive material in the building. Differential settlement has also occurred, causing portions of the facility to separate from the main building structure thus creating a potential for release of radioactive material t the environment. An expedited removal action is proposed to ensure that a release from the 233-S Facility does not occur. The US Department of Energy (DOE), Richland Operations Office (RL), in cooperation with the EPA, has prepared this Engineering Evaluation/Cost Analysis (EE/CA) pursuant to CERCLA. Based on the evaluation, RL has determined that hazardous substances in the 233-S Facility may present a potential threat to human health and/or the environment, and that an expedited removal action is warranted. The purpose of the EE/CA is to provide the framework for the evaluation and selection of a technology from a viable set of alternatives for a removal action

  3. Functional analysis of the exploratory studies facility

    International Nuclear Information System (INIS)

    Duffy, M.A.; Mozhi, T.A.; Kumar, P.N.; Senderling, M.S.; Lemeshewsky, W.A.

    1993-01-01

    The 'Physical System Requirements - Exploratory Studies Facility' (PSR-ESF) was developed as part of an improved management structure and procedure initiative by the OCRWM for managing the disposal of spent nuclear fuel and high-level radioactive wastes. This paper discusses the development of the PSR-EF document. Based on a functional analysis approach, this document includes results in the form of boundary diagrams, function hierarchy trees, function description tables containing a compilation of requirements, architecture tree and tables, and functional flow diagrams. The approach used ensures the flowdown and traceability of relevant requirements for the ESF design process

  4. Inventory of activation analysis facilities available in the European Community to Industrial users

    International Nuclear Information System (INIS)

    Pauwels, J.

    1975-01-01

    This inventory includes lists of activation equipment produced in the European Community, facilities available for industrial users and activation laboratories existing in the European companies. The aim of this inventory is to provide all information that may be useful, to companies interested in activation analysis, as well as to give an idea on existing routine applications and on the European market in facilities

  5. A decision analysis of an exploratory studies facility

    International Nuclear Information System (INIS)

    Merkhofer, M.W.; Gnirk, P.

    1992-01-01

    This paper reports that an Exploratory Studied 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 characterization decision because the ESF design may affect the accuracy of characterization testing an constrains subsequent repository design. To assist the design process, a comparative evaluation was conducted to rank 34 alternative ESF-repository designs. The evaluation relied on techniques from formal decision analysis, including decision trees and multiattribute utility analysis (MUA). The results helped to identify favorable design features and enabled the Department of Energy to adopt an improved ESF design

  6. Eficiência das auxinas (AIB e ANA no enraizamento de miniestacas de clones de Eucalyptus cloeziana F. Muell Auxin (IBA and NAA effects on minicuttings rooting of Eucalyptus cloeziana F. Muell. clones

    Directory of Open Access Journals (Sweden)

    Fernanda Daniele de Almeida

    2007-01-01

    Full Text Available Este trabalho teve como objetivo avaliar a eficiência das auxinas AIB (ácido indolbutírico e ANA (ácido naftalenoacético no enraizamento adventício de miniestacas de clones de Eucalyptus cloeziana. Foram utilizadas miniestacas provenientes de sete clones de Eucalyptus cloeziana, estabelecidos em minijardim clonal, sendo avaliados os efeitos de AIB (0, 1.500, 3.000 e 6.000 mg L-1 na forma líquida e em pó e ANA (0, 3.000 e 6.000 mg L-1 na forma líquida. Os resultados apontaram ser a miniestaquia técnica viável na propagação vegetativa dos clones de Eucalyptus cloeziana estudados, apresentando, de modo geral, alto índice de enraizamento das miniestacas. Os clones com maior potencial de enraizamento adventício responderam mais positivamente às menores dosagens de AIB, enquanto nos clones com capacidade de enraizamento reduzida houve tendência de as maiores dosagens de AIB serem mais eficientes no enraizamento, independentemente da forma de aplicação do fitorregulador (líquido ou pó. O ANA, de modo geral, não influenciou significativamente o enraizamento das miniestacas da maioria dos clones estudados.The present work aimed to evaluate the efficiency of the auxins IBA (indolbutyric acid and NAA (naphtaleneacetic acid on the adventitious rooting of Eucalyptus cloeziana clones. Minicuttings originated from seven Eucalyptus cloeziana clones established in mini-clonal hedge, were evaluated for the effects of IBA (0, 1500, 3000 and 6000 mg L-1 in the liquid and powder forms and NAA (0, 3000 and 6000 mg L-1 in the liquid form. The results showed that minicutting is a viable technique for vegetative propagation of the studied Eucalyptus cloeziana clones, with overall high rooting rates. Clones with higher adventitious rooting potential gave better response to lower IBA doses, while clones with reduced rooting potential were more efficient with higher doses, independently of the form of the applied phytoregulator (powder or liquid. NAA

  7. Computerized radionuclidic analysis in production facilities

    International Nuclear Information System (INIS)

    Gibbs, A.

    1978-03-01

    The Savannah River Plant Laboratories Department has been using a dual computer system to control all radionuclidic pulse height analyses since 1971. This computerized system analyzes 7000 to 8000 samples per month and has allowed the counting room staff to be reduced from three persons to one person. More reliable process information is being returned to the production facilities and for environmental evaluations and being returned faster, even though the sample load has more than tripled. This information is now more easily retrievable for other evaluations. The computer is also used for mass spectrometer data reduction and for quality control data analysis. The basic system is being expanded by interfacing microcomputers which provide data input from all of the laboratory modules for quality assurance programs

  8. Metodologias de aplicação de AIB no enraizamento de estacas semilenhosas de Sapium glandulatum (vell. pax Methodologies of IBA application in the rooting of Sapium glandulatum (vell. pax semi-hardwood cuttings

    Directory of Open Access Journals (Sweden)

    B.G.A. Ferreira

    2009-01-01

    , não sendo um método recomendável para o aumento da indução radicial de Sapium glandulatum. Pelo exposto, pode-se considerar que estacas de brotações do ano desta espécie não são indicadas para sua propagação vegetativa, de acordo com os tratamentos realizados.The species Sapium glandulatum, commonly known as "leiteiro", is one of the Brazilian native species potentially recommended for the recovery of degraded areas, mainly due to its pioneering character and probable medicinal properties since its family, Euphorbiaceae, is rich in phenolic compounds. In April/2000 and December/2001, experiments were carried out in a greenhouse to investigate the effects of different indolebutyric acid (IBA levels in concentrated solution (10 seconds immersion, diluted solution (16 hours immersion and as talc, associated or not with boric acid, on the rooting of Sapium glandulatum semi-hardwood cuttings. The latter were produced from sproutings of the year collected from stock plants located in Bocaiúva do Sul, Paraná State, Brazil. The length of each cutting was about 10 cm, with 2 half apical leaves. The following treatments were evaluated: 0, 4000, 6000 and 8000 mg L-1 IBA, alone and with 150 mg L-1 boric acid (concentrated solution; 0, 200 and 400 mg L-1 IBA, alone and with 150 mg L-1 boric acid (diluted solution; and 0, 4000, 6000 and 8000 mg L-1 IBA as talc. After 70 days in greenhouse, the best period for cutting collection was December/2000 (summer, and 8000 mg L-1 IBA in concentrated solution led to the highest rooting percentage (14%, although not significantly different from the remaining treatments. The diluted solution did not show promising results for root system induction due to the high mortality of cuttings. The results for IBA as talc were not higher than those for the best treatments in concentrated solution, which indicates this method is not recommended to increase Sapium glandulatum rooting induction. Thus, sprouting cuttings of the year from

  9. Hazards Analysis for the Spent Nuclear Fuel L-Experimental Facility

    International Nuclear Information System (INIS)

    Blanchard, A.

    1999-01-01

    The purpose of this Hazard Analysis (HA) is to identify and assess potential hazards associated with the operations of the Spent Nuclear Fuels (SNF) Treatment and Storage Facility LEF. Additionally, this HA will be used for identifying and assessing potential hazards and specifying functional attributes of SSCs for the LEF project

  10. A durability analysis of the Cascad facility based on feedback obtained after 10 years of operation

    International Nuclear Information System (INIS)

    Samoel, R.; Canas, D.; Henry, H.; Battesti, P.

    1999-01-01

    The CASCAD facility at the nuclear research centre in Cadarache is a dry storage facility for spent fuel that has been placed in a vault. Feedback on its design and performance after 10 years of operation was obtained in order to identify the factors limiting its life time. This assessment corresponds to a durability analysis based on a combination of dependability methods. This is a critical analysis identifying the risks involving failure of the components when they are subjected to internal and external disturbances (aging, technology obsolescence, etc.). The measures to be implemented to extend the life time of the facility are subsequently enumerated. A proposed synthesis or 'logic diagram' of the analysis is also presented. (authors)

  11. 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.

  12. SU-E-T-03: 3 Year Clinical Experience with the IBA Proton Eyeline

    Energy Technology Data Exchange (ETDEWEB)

    Kryck, E; Mamalui-Hunter, M; Li, Z; Slopsema, R [University of Florida/Radiation Oncology, Jacksonville, FL (United States)

    2015-06-15

    Purpose: Over the past 3 years, more than 50 patients with ocular disease have been treated with a prototype commercial eyeline developed by Ion Beam Applications (IBA). It is particularly crucial for the dosimetry of the machine to be accurate, precise, and reproducible because of the small treatment volumes and several surrounding critical structures. A quality assurance (QA) program has been developed in order to regularly check and record the machine’s dosimetry over time. In this study we have summarized and evaluated three years of patient and system QA data for the eyeline prototype. Methods: In order to accurately deliver the prescribed dose to the patient’s treatment site, an output model was created based on several machine parameters. This output model, along with the requested system parameters, are regularly checked and recorded by a QA program. 10 standard proton fields have been created which have regular QA performed monthly with a water tank and parallel-plate chamber, and recorded in a database. QA has additionally been performed for each patient-specific treatment field. This is to verify and evaluate the patient output model as well as the system parameters for range&modulation combinations different than the standard QA fields. Results: 140 beam measurements have been analyzed for range, modulation, and output. The range is typically within tolerance, although there are about 6 cases where the system did not perform as expected. The modulation appears to be very stable, always being within tolerance. Output for the standard QA fields are typically within 2.5% from the baseline value. The patient output measurements agree within 2.5% from the model. Conclusion: Overall the eyeline performs well within the tolerances set, and the patient output measurements agree within 2% of the model.

  13. LMFBR safety experiment facility planning and analysis

    International Nuclear Information System (INIS)

    Stevenson, M.G.; Scott, J.H.

    1976-01-01

    In the past two years considerable effort has been placed on the planning and design of new facilities for the resolution of LMFBR safety issues. The paper reviews the key issues, the experiments needed to resolve them, and the design aspects of proposed new facilities. In addition, it presents a decision theory approach to selecting an optimal combination of modified and new facilities

  14. Experimental Fuels Facility Re-categorization Based on Facility Segmentation

    Energy Technology Data Exchange (ETDEWEB)

    Reiss, Troy P.; Andrus, Jason

    2016-07-01

    The Experimental Fuels Facility (EFF) (MFC-794) at the Materials and Fuels Complex (MFC) located on the Idaho National Laboratory (INL) Site was originally constructed to provide controlled-access, indoor storage for radiological contaminated equipment. Use of the facility was expanded to provide a controlled environment for repairing contaminated equipment and characterizing, repackaging, and treating waste. The EFF facility is also used for research and development services, including fuel fabrication. EFF was originally categorized as a LTHC-3 radiological facility based on facility operations and facility radiological inventories. Newly planned program activities identified the need to receive quantities of fissionable materials in excess of the single parameter subcritical limit in ANSI/ANS-8.1, “Nuclear Criticality Safety in Operations with Fissionable Materials Outside Reactors” (identified as “criticality list” quantities in DOE-STD-1027-92, “Hazard Categorization and Accident Analysis Techniques for Compliance with DOE Order 5480.23, Nuclear Safety Analysis Reports,” Attachment 1, Table A.1). Since the proposed inventory of fissionable materials inside EFF may be greater than the single parameter sub-critical limit of 700 g of U-235 equivalent, the initial re-categorization is Hazard Category (HC) 2 based upon a potential criticality hazard. This paper details the facility hazard categorization performed for the EFF. The categorization was necessary to determine (a) the need for further safety analysis in accordance with LWP-10802, “INL Facility Categorization,” and (b) compliance with 10 Code of Federal Regulations (CFR) 830, Subpart B, “Safety Basis Requirements.” Based on the segmentation argument presented in this paper, the final hazard categorization for the facility is LTHC-3. Department of Energy Idaho (DOE-ID) approval of the final hazard categorization determined by this hazard assessment document (HAD) was required per the

  15. Vulnerability Analysis for Physical Protection System at Hypothetical Facility of a Different Type Reactor

    International Nuclear Information System (INIS)

    Jung, Won-Moog; Kim, Jung-Soo; Kim, Jae-Kwang; Yoo, Ho-Sik; Kwak, Sung-Ho; Jang, Sung-Soon

    2007-01-01

    Since the 9/11 event in the U.S.A, International terror possibilities has been increased for nuclear facilities including nuclear power plants(NPPs). It is necessary to evaluate the performance of an existing physical protection system(PPS) at nuclear facilities based on such malevolent acts. Detection, delay, and response elements are all important to PPS. They are used for the analysis and evaluation of a PPS and its effectiveness. Methods are available to analyze a PPS and evaluate its effectiveness. Sandia National Laboratory(SNL) in the U.S.A developed a System Analysis of Vulnerability to Intrusion (SAVI) computer code for evaluating the effectiveness of PPS against outsider threats. This study presents the vulnerability analysis of the PPS at hypothetical facility of a different type using SAVI code that the basic input parameters are from PPS of a different type. For analysis, first, the site-specific Adversary Sequence Diagrams(ASDs) of the PPS is designed. It helps to understand the functions of the existing PPS composed of physical areas and Protection Elements(PEs). Then, the most vulnerable path of an ASD as a measure of effectiveness is determined. The results in the analysis can compare with the most vulnerable paths at a different type

  16. 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.

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

    International Nuclear Information System (INIS)

    TOMASZEWSKI, T.A.

    2000-01-01

    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

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

    International Nuclear Information System (INIS)

    Ballard, J.D.

    2002-01-01

    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)

  19. Energy spread in ion beam analysis

    International Nuclear Information System (INIS)

    Szilagyi, E.

    2000-01-01

    In ion beam analysis (IBA) the depth profiles are extracted from the experimentally determined energy profiles. The spectra, however, are subject to finite energy resolution of both extrinsic and intrinsic origin. Calculation of those effects such as instrumental beam, geometry and detection-related energy and angular spreads as well as energy straggling, multiple scattering and Doppler effects in the sample itself is not trivial, especially since it involves treatment of non-independent random processes. A proper account for energy spread is vital in IBA not only for correct extraction of elemental and isotopic depth profiles from the measured spectra, but already prior to data acquisition, in optimising experimental conditions to reach the required depth resolution at a certain depth. After a short review of the literature on the different energy spread contributions experimental examples are given from resonance, RBS, elastic BS and ERDA practice in which an account for energy spread contributions is essential. Some further examples illustrate extraction of structural information (roughness, pore size, etc.) from elaborated depth resolution calculation for such layer structures

  20. Energy spread in ion beam analysis

    Energy Technology Data Exchange (ETDEWEB)

    Szilagyi, E. E-mail: szilagyi@rmki.kkfki.hu

    2000-03-01

    In ion beam analysis (IBA) the depth profiles are extracted from the experimentally determined energy profiles. The spectra, however, are subject to finite energy resolution of both extrinsic and intrinsic origin. Calculation of those effects such as instrumental beam, geometry and detection-related energy and angular spreads as well as energy straggling, multiple scattering and Doppler effects in the sample itself is not trivial, especially since it involves treatment of non-independent random processes. A proper account for energy spread is vital in IBA not only for correct extraction of elemental and isotopic depth profiles from the measured spectra, but already prior to data acquisition, in optimising experimental conditions to reach the required depth resolution at a certain depth. After a short review of the literature on the different energy spread contributions experimental examples are given from resonance, RBS, elastic BS and ERDA practice in which an account for energy spread contributions is essential. Some further examples illustrate extraction of structural information (roughness, pore size, etc.) from elaborated depth resolution calculation for such layer structures.

  1. Multi-dimensional Analysis for SLB Transient in ATLAS Facility as Activity of DSP (Domestic Standard Problem)

    International Nuclear Information System (INIS)

    Bae, B. U.; Park, Y. S.; Kim, J. R.; Kang, K. H.; Choi, K. Y.; Sung, H. J.; Hwang, M. J.; Kang, D. H.; Lim, S. G.; Jun, S. S.

    2015-01-01

    Participants of DSP-03 were divided in three groups and each group has focused on the specific subject related to the enhancement of the code analysis. The group A tried to investigate scaling capability of ATLAS test data by comparing to the code analysis for a prototype, and the group C studied to investigate effect of various models in the one-dimensional codes. This paper briefly summarizes the code analysis result from the group B participants in the DSP-03 of the ATLAS test facility. The code analysis by Group B focuses highly on investigating the multi-dimensional thermal hydraulic phenomena in the ATLAS facility during the SLB transient. Even though the one-dimensional system analysis code cannot simulate the whole system of the ATLAS facility with a nodalization of the CFD (Computational Fluid Dynamics) scale, a reactor pressure vessel can be considered with multi-dimensional components to reflect the thermal mixing phenomena inside a downcomer and a core. Also, the CFD could give useful information for understanding complex phenomena in specific components such as the reactor pressure vessel. From the analysis activity of Group B in ATLAS DSP-03, participants adopted a multi-dimensional approach to the code analysis for the SLB transient in the ATLAS test facility. The main purpose of the analysis was to investigate prediction capability of multi-dimensional analysis tools for the SLB experiment result. In particular, the asymmetric cooling and thermal mixing phenomena in the reactor pressure vessel could be significantly focused for modeling the multi-dimensional components

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

    International Nuclear Information System (INIS)

    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

  3. Seismic analysis of the mirror fusion test facility building

    International Nuclear Information System (INIS)

    Coats, D.W.

    1978-01-01

    This report describes a seismic analysis of the present Mirror Fusion Test Facility (MFTF) building at the Lawrence Livermore Laboratory. The analysis was conducted to evaluate how the structure would withstand the postulated design-basis earthquake (DBE). We discuss the methods of analysis used and results obtained. Also presented are a detailed description of the building, brief discussions of site geology, seismicity, and soil conditions, the approach used to postulate the DBE, and two methods for incorporating the effects of ductility. Floor spectra for the 2nd, 3rd, and 4th floors developed for preliminary equipment design are also included. The results of the analysis, based on best-estimate equipment loadings, indicate additional bracing and upgrading of connection details are required for the structure to survive the postulated design-basis earthquake. Specific recommendations are made

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

    International Nuclear Information System (INIS)

    1978-01-01

    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

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

    International Nuclear Information System (INIS)

    Oh, Yon Woo; Kim, Seon Duk; Nam, Ji Hee

    2000-11-01

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

    Energy Technology Data Exchange (ETDEWEB)

    Oh, Yon Woo; Kim, Seon Duk; Nam, Ji Hee

    2000-11-01

    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.

  7. Facility effluent monitoring plan for the 327 Facility

    International Nuclear Information System (INIS)

    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

  8. Inventory difference analysis at Los Alamos Plutonium Facility

    International Nuclear Information System (INIS)

    Zardecki, A.; Armstrong, J.M.; Longmire, V.; Strittmatter, R.B.

    1997-01-01

    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

  9. 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.

  10. Seismic risk analysis for the Westinghouse Electric facility, Cheswick, Pennsylvania

    International Nuclear Information System (INIS)

    1977-01-01

    This report presents the results of a detailed seismic risk analysis of the Westinghouse Electric plutonium fuel development facility at Cheswick, Pennsylvania. This report focuses on earthquakes. 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. Because of the aseismicity of the region around the site, an analysis different from the conventional closest approach in a tectonic province was adapted. Earthquakes as far from the site as 1,000 km were included, as were the possibility of earthquakes at the site. In addition, various uncertainties in the input were explicitly considered in the analysis. For example, allowance was made for both the uncertainty in predicting maximum possible earthquakes in the region and the effect of the dispersion of data about the best fit attenuation relation. The attenuation relationship is derived from two of the most recent, advanced studies relating earthquake intensity reports and acceleration. Results of the risk analysis, which include a Bayesian estimate of the uncertainties, are presented as return period accelerations. The best estimate curve indicates that the Westinghouse facility will experience 0.05 g every 220 years and 0.10 g every 1400 years. The accelerations are very insensitive to the details of the source region geometries or the historical earthquake statistics in each region and each of the source regions contributes almost equally to the cumulative risk at the site

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

    International Nuclear Information System (INIS)

    William S. Charlton

    1999-01-01

    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

  12. Economic analysis of including an MRS facility in the waste management system

    International Nuclear Information System (INIS)

    Williams, J.W.; Conner, C.; Leiter, A.J.; Ching, E.

    1992-01-01

    The MRS System Study Summary Report (System Study) in June 1989 concluded that an MRS facility would provide early spent fuel acceptance as well as flexibility for the waste management system. However, these advantages would be offset by an increase in the total system cost (i.e., total cost to the ratepayer) ranging from $1.3 billion to about $2.8 billion depending on the configuration of the waste management system. This paper discusses this new investigation which will show that, in addition to the advantages of an MRS facility described above, a basic (i.e., store-only) MRS facility may result in a cost savings to the total system, primarily due to the inclusion in the analysis of additional at-reactor operating costs for maintaining shutdown reactor sites

  13. SAS3A analysis of natural convection boiling behavior in the Sodium Boiling Test Facility

    International Nuclear Information System (INIS)

    Klein, G.A.

    1979-01-01

    An analysis of natural convection boiling behavior in the Sodium Boiling Test (SBT) Facility has been performed using the SAS3A computer code. The predictions from this analysis indicate that stable boiling can be achieved for extensive periods of time for channel powers less than 1.4 kW and indicate intermittent dryout at higher powers up to at least 1.7 kW. The results of this anaysis are in reasonable agreement with the SBT Facility test results

  14. Overview of seismic probabilistic risk assessment for structural analysis in nuclear facilities

    International Nuclear Information System (INIS)

    Reed, J.W.

    1989-01-01

    Probabilistic Risk Assessment (PRA) for seismic events is currently being performed for nuclear and DOE facilities. The background on seismic PRA is presented along with a basic description of the method. The seismic PRA technique is applicable to other critical facilities besides nuclear plants. The different approaches for obtained structure fragility curves are discussed and their applications to structures and equipment, in general, are addressed. It is concluded that seismic PRA is a useful technique for conducting probability analysis for a wide range of classes of structures and equipment

  15. 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.

  16. Mixed Waste Management Facility Preliminary Safety Analysis Report. Chapters 1 to 20

    International Nuclear Information System (INIS)

    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

  17. 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......The optimization of logistics in large building com- plexes with many resources, such as hospitals, require realistic facility management and planning. Current planning practices rely foremost on manual observations or coarse unverified as- sumptions and therefore do not properly scale or provide....... Spatio-temporal visualization tools built on top of these methods enable planners to inspect and explore extracted information to inform facility-planning activities. To evaluate the methods, we present results for a large hospital complex covering more than 10 hectares. The evaluation is based on Wi...

  18. Status of the ALICE CERN Analysis Facility

    International Nuclear Information System (INIS)

    Meoni, Marco; Grosse-Oetringhaus, Jan Fiete; Carminati, Federico

    2010-01-01

    The ALICE experiment at CERN LHC is using a PROOF-enabled cluster for fast physics analysis, detector calibration and reconstruction of small data samples. The current system (CAF - CERN Analysis Facility) consists of some 120 CPU cores and about 45 TB of disk space distributed across the CAF hosts. One of the most important aspects of the data analysis on the CAF is the speed with which it can be carried out. The system is particularly aimed at the prototyping phase of analyses that need a high number of iterations and thus require a short response time. Quasi-online quality assurance of data can be obtained. The paper describes the design principles of the PROOF framework and presents the current setup, performance tests and usage statistics. Subsets of selected data can be automatically staged in CAF from the Grid storage systems, therefore data distribution and staging techniques are described in depth. A fairshare algorithm to adjust the priorities of concurrently running sessions is also examined. Furthermore, the adaptation of PROOF to the AliEn/gLite Grid middleware is described. This approach enables a dynamic startup of PROOF nodes worldwide with the purpose to process much larger physics datasets.

  19. The data analysis facilities that astronomers want

    International Nuclear Information System (INIS)

    Disney, M.

    1985-01-01

    This paper discusses the need and importance of data analysis facilities and what astronomers ideally want. A brief survey is presented of what is available now and some of the main deficiencies and problems with today's systems are discussed. The main sources of astronomical data are presented incuding: optical photographic, optical TV/CCD, VLA, optical spectros, imaging x-ray satellite, and satellite planetary camera. Landmark discoveries are listed in a table, some of which include: our galaxy as an island, distance to stars, H-R diagram (stellar structure), size of our galaxy, and missing mass in clusters. The main problems at present are discussed including lack of coordinated effort and central planning, differences in hardware, and measuring performance

  20. 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.

  1. 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.

  2. 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.

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

    International Nuclear Information System (INIS)

    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

  4. Safety analysis of IFR fuel processing in the Argonne National Laboratory Fuel Cycle Facility

    International Nuclear Information System (INIS)

    Charak, I; Pedersen, D.R.; Forrester, R.J.; Phipps, R.D.

    1993-01-01

    The Integral Fast Reactor (IFR) concept developed by Argonne National Laboratory (ANL) includes on-site processing and recycling of discharged core and blanket fuel materials. The process is being demonstrated in the Fuel Cycle Facility (FCF) at ANL's Idaho site. This paper describes the safety analyses that were performed in support of the FCF program; the resulting safety analysis report was the vehicle used to secure authorization to operate the facility and carry out the program, which is now under way. This work also provided some insights into safety-related issues of a commercial IFR fuel processing facility. These are also discussed

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

    International Nuclear Information System (INIS)

    Khattab, M.; Mariy, Ahmed

    1999-01-01

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

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

    International Nuclear Information System (INIS)

    Blanchard, A.

    1999-01-01

    '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.'

  7. 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

  8. 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...

  9. Lead coolant test facility systems design, thermal hydraulic analysis and cost estimate

    Energy Technology Data Exchange (ETDEWEB)

    Khericha, Soli, E-mail: slk2@inel.gov [Battelle Energy Alliance, LLC, Idaho National Laboratory, Idaho Falls, ID 83415 (United States); Harvego, Edwin; Svoboda, John; Evans, Robert [Battelle Energy Alliance, LLC, Idaho National Laboratory, Idaho Falls, ID 83415 (United States); Dalling, Ryan [ExxonMobil Gas and Power Marketing, Houston, TX 77069 (United States)

    2012-01-15

    The Idaho National Laboratory prepared a preliminary technical and functional requirements (T and FR), thermal hydraulic design and cost estimate for a lead coolant test facility. The purpose of this small scale facility is to simulate lead coolant fast reactor (LFR) coolant flow in an open lattice geometry core using seven electrical rods and liquid lead or lead-bismuth eutectic coolant. Based on review of current world lead or lead-bismuth test facilities and research needs listed in the Generation IV Roadmap, five broad areas of requirements were identified as listed below: Bullet Develop and demonstrate feasibility of submerged heat exchanger. Bullet Develop and demonstrate open-lattice flow in electrically heated core. Bullet Develop and demonstrate chemistry control. Bullet Demonstrate safe operation. Bullet Provision for future testing. This paper discusses the preliminary design of systems, thermal hydraulic analysis, and simplified cost estimated. The facility thermal hydraulic design is based on the maximum simulated core power using seven electrical heater rods of 420 kW; average linear heat generation rate of 300 W/cm. The core inlet temperature for liquid lead or Pb/Bi eutectic is 4200 Degree-Sign C. The design includes approximately seventy-five data measurements such as pressure, temperature, and flow rates. The preliminary estimated cost of construction of the facility is $3.7M (in 2006 $). It is also estimated that the facility will require two years to be constructed and ready for operation.

  10. Waste Analysis Plan for the Waste Receiving and Processing (WRAP) Facility

    International Nuclear Information System (INIS)

    TRINER, G.C.

    1999-01-01

    The purpose of this waste analysis plan (WAP) is to document the waste acceptance process, sampling methodologies, analytical techniques, and overall processes that are undertaken for dangerous, mixed, and radioactive waste accepted for confirmation, nondestructive examination (NDE) and nondestructive assay (NDA), repackaging, certification, and/or storage at the Waste Receiving and Processing Facility (WRAP). Mixed and/or radioactive waste is treated at WRAP. WRAP is located in the 200 West Area of the Hanford Facility, Richland, Washington. Because dangerous waste does not include source, special nuclear, and by-product material components of mixed waste, radionuclides are not within the scope of this documentation. The information on radionuclides is provided only for general knowledge

  11. Leak-Path Factor Analysis for the Nuclear Materials Storage Facility

    International Nuclear Information System (INIS)

    Shaffer, C.; Leonard, M.

    1999-01-01

    Leak-path factors (LPFs) were calculated for the Nuclear Materials Storage Facility (NMSF) located in the Plutonium Facility, Building 41 at the Los Alamos National Laboratory Technical Area 55. In the unlikely event of an accidental fire powerful enough to fail a container holding actinides, the subsequent release of oxides, modeled as PuO 2 aerosols, from the facility and into the surrounding environment was predicted. A 1-h nondestructive assay (NDA) laboratory fire accident was simulated with the MELCOR severe accident analysis code. Fire-driven air movement along with wind-driven air infiltration transported a portion of these actinides from the building. This fraction is referred to as the leak-path factor. The potential effect of smoke aerosol on the transport of the actinides was investigated to verify the validity of neglecting the smoke as conservative. The input model for the NMSF consisted of a system of control volumes, flow pathways, and surfaces sufficient to model the thermal-hydraulic conditions within the facility and the aerosol transport data necessary to simulate the transport of PuO 2 particles. The thermal-hydraulic, heat-transfer, and aerosol-transport models are solved simultaneously with data being exchanged between models. A MELCOR input model was designed such that it would reproduce the salient features of the fire per the corresponding CFAST calculation. Air infiltration into and out of the facility would be affected strongly by wind-driven differential pressures across the building. Therefore, differential pressures were applied to each side of the building according to guidance found in the ASHRAE handbook using a standard-velocity head equation with a leading multiplier to account for the orientation of the wind with the building. The model for the transport of aerosols considered all applicable transport processes, but the deposition within the building clearly was dominated by gravitational settling

  12. RISK ASSESSMENT BY STRUCTURAL ANALYSIS AND VIBRATION MEASUREMENT EQUIPMENT OPERATING AT OIL FACILITIES

    OpenAIRE

    Marius STAN

    2013-01-01

    Vibration analysis applications in operation is one of the diagnostic methods ofoperation of the facility. Analysis of these types of failures indicated the existence of specificfeatures prints and related equipment vibration spectra. Modeling and identification of theseparticular aspects in the spectrum of vibration machines help to control the operation of oilfacilities built safely.

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

    International Nuclear Information System (INIS)

    1992-01-01

    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

  14. Characterization and application of automated in-vacuum PIXE/EBS system for direct analysis of chloride and sulfate ions attack in cementitious materials

    Science.gov (United States)

    Rihawy, M. S.; Alwazzeh, M.; Abbas, K.

    2018-01-01

    Ion beam analysis (IBA) techniques (Particle Induced X-ray Emission, PIXE and Elastic Backscattering Spectrometry, EBS), were applied to investigate chloride and sulfate ions diffusion into laboratory prepared mortar samples. Development and characterization of an automated in-vacuum macro PIXE/EBS system is thoroughly discussed. Depth profile information of both chloride and sulfate ions in laboratory prepared mortar samples, after immersion in sea water for nine months, was rapidly and easily obtained at fairly low cost and with standardless analysis, demonstrating the value of the application of IBA to elemental depth profiling in cementitious materials. Chloride and sulfate depth profiles were obtained for two sets of mortar samples, one prepared with different water/cement (W/C) ratios and the other with different sand/cement (S/C) ratios. Results showed higher diffusion rates of both chloride and sulfate ions when both ratios are increased. Additionally, the W/C ratio has a stronger influence in both sulfate and chloride penetration than the S/C ratio, and chloride ions penetrate faster than sulfates. Advantages and limitations of applying IBA techniques in this investigation are discussed. The comparison between PIXE and other X-ray based analytical techniques, namely X-ray fluorescence (XRF) and energy and wavelength dispersive X-rays (EDX/WDX), as well as other traditional wet chemical methods is reviewed, and industrial applications are discussed.

  15. Preliminary analysis of West Valley Waste Removal System equipment development and mock demonstration facilities

    International Nuclear Information System (INIS)

    Janicek, G.P.

    1981-06-01

    This report defines seven areas requiring further investigation to develop and demonstrate a safe and viable West Valley Waste Removal System. These areas of endeavor are discussed in terms of their minimum facility requirements. It is concluded that utilizing separated specific facilities at different points in time is of a greater advantage than an exact duplication of the West Valley tanks. Savannah River Plant's full-scale, full-circle and half-circle tanks, and their twelfth scale model tank would all be useful to varying degrees but would require modifications. Hanford's proposed full-size mock tank would be useful, but is not seriously considered because its construction may not coincide with West Valley needs. Costs of modifying existing facilities and/or constructing new facilities are assessed in terms of their benefit to the equipment development and mock demonstration. Six facilities were identified for further analysis which would benefit development of waste removal equipment

  16. Radiation analysis for a generic centralized interim storage facility

    International Nuclear Information System (INIS)

    Gillespie, S.G.; Lopez, P.; Eble, R.G.

    1997-01-01

    This paper documents the radiation analysis performed for the storage area of a generic Centralized Interim Storage Facility (CISF) for commercial spent nuclear fuel (SNF). The purpose of the analysis is to establish the CISF Protected Area and Restricted Area boundaries by modeling a representative SNF storage array, calculating the radiation dose at selected locations outside the storage area, and comparing the results with regulatory radiation dose limits. The particular challenge for this analysis is to adequately model a large (6000 cask) storage array with a reasonable amount of analysis time and effort. Previous analyses of SNF storage systems for Independent Spent Fuel Storage Installations at nuclear plant sites (for example in References 5.1 and 5.2) had only considered small arrays of storage casks. For such analyses, the dose contribution from each storage cask can be modeled individually. Since the large number of casks in the CISF storage array make such an approach unrealistic, a simplified model is required

  17. External-RBS, PIXE and NRA analysis for ancient swords

    Energy Technology Data Exchange (ETDEWEB)

    Santos, Hellen C., E-mail: hellencsa@gmail.com; Added, Nemitala; Silva, Tiago F.; Rodrigues, C.L.

    2015-02-15

    Elemental composition of the steel of two ancient swords (Japanese and Damascus from a private collection) was characterized using in air IBA techniques. Our results contribute for the understanding the processes of manufacturing (hammering and quenching) and surface treatments applied in these swords. The Particle Induced X-ray Emission (PIXE) measurements along the Damascus blade allowed to identify and to trace a superficial concentration profile for the elements such Cr, Mn, Fe, Ni, Cu, Zn and As, while results for the Japanese blade showed only the presence of iron. The carbon content on the surface was also investigated using a resonant region in the Elastic Backscattering Spectrometry (EBS) measurements and the results have shown a slightly difference between the surfaces under investigation. In order to investigate the nitrogen content on surface, that could explain the hardening process, we used Nuclear Reaction Analysis (NRA) and the results shown that nitrogen content was under our detection limit for the technique (0.3% in mass). The measurements of PIXE, NRA and EBS were taken using the external beam setup installed at Lamfi – São Paulo/Brazil, the latter being successfully implemented for the first time in this facility.

  18. External-RBS, PIXE and NRA analysis for ancient swords

    Science.gov (United States)

    Santos, Hellen C.; Added, Nemitala; Silva, Tiago F.; Rodrigues, C. L.

    2015-02-01

    Elemental composition of the steel of two ancient swords (Japanese and Damascus from a private collection) was characterized using in air IBA techniques. Our results contribute for the understanding the processes of manufacturing (hammering and quenching) and surface treatments applied in these swords. The Particle Induced X-ray Emission (PIXE) measurements along the Damascus blade allowed to identify and to trace a superficial concentration profile for the elements such Cr, Mn, Fe, Ni, Cu, Zn and As, while results for the Japanese blade showed only the presence of iron. The carbon content on the surface was also investigated using a resonant region in the Elastic Backscattering Spectrometry (EBS) measurements and the results have shown a slightly difference between the surfaces under investigation. In order to investigate the nitrogen content on surface, that could explain the hardening process, we used Nuclear Reaction Analysis (NRA) and the results shown that nitrogen content was under our detection limit for the technique (0.3% in mass). The measurements of PIXE, NRA and EBS were taken using the external beam setup installed at Lamfi - São Paulo/Brazil, the latter being successfully implemented for the first time in this facility.

  19. External-RBS, PIXE and NRA analysis for ancient swords

    International Nuclear Information System (INIS)

    Santos, Hellen C.; Added, Nemitala; Silva, Tiago F.; Rodrigues, C.L.

    2015-01-01

    Elemental composition of the steel of two ancient swords (Japanese and Damascus from a private collection) was characterized using in air IBA techniques. Our results contribute for the understanding the processes of manufacturing (hammering and quenching) and surface treatments applied in these swords. The Particle Induced X-ray Emission (PIXE) measurements along the Damascus blade allowed to identify and to trace a superficial concentration profile for the elements such Cr, Mn, Fe, Ni, Cu, Zn and As, while results for the Japanese blade showed only the presence of iron. The carbon content on the surface was also investigated using a resonant region in the Elastic Backscattering Spectrometry (EBS) measurements and the results have shown a slightly difference between the surfaces under investigation. In order to investigate the nitrogen content on surface, that could explain the hardening process, we used Nuclear Reaction Analysis (NRA) and the results shown that nitrogen content was under our detection limit for the technique (0.3% in mass). The measurements of PIXE, NRA and EBS were taken using the external beam setup installed at Lamfi – São Paulo/Brazil, the latter being successfully implemented for the first time in this facility

  20. Reliability and Maintainability Analysis of a High Air Pressure Compressor Facility

    Science.gov (United States)

    Safie, Fayssal M.; Ring, Robert W.; Cole, Stuart K.

    2013-01-01

    This paper discusses a Reliability, Availability, and Maintainability (RAM) independent assessment conducted to support the refurbishment of the Compressor Station at the NASA Langley Research Center (LaRC). The paper discusses the methodologies used by the assessment team to derive the repair by replacement (RR) strategies to improve the reliability and availability of the Compressor Station (Ref.1). This includes a RAPTOR simulation model that was used to generate the statistical data analysis needed to derive a 15-year investment plan to support the refurbishment of the facility. To summarize, study results clearly indicate that the air compressors are well past their design life. The major failures of Compressors indicate that significant latent failure causes are present. Given the occurrence of these high-cost failures following compressor overhauls, future major failures should be anticipated if compressors are not replaced. Given the results from the RR analysis, the study team recommended a compressor replacement strategy. Based on the data analysis, the RR strategy will lead to sustainable operations through significant improvements in reliability, availability, and the probability of meeting the air demand with acceptable investment cost that should translate, in the long run, into major cost savings. For example, the probability of meeting air demand improved from 79.7 percent for the Base Case to 97.3 percent. Expressed in terms of a reduction in the probability of failing to meet demand (1 in 5 days to 1 in 37 days), the improvement is about 700 percent. Similarly, compressor replacement improved the operational availability of the facility from 97.5 percent to 99.8 percent. Expressed in terms of a reduction in system unavailability (1 in 40 to 1 in 500), the improvement is better than 1000 percent (an order of magnitude improvement). It is worthy to note that the methodologies, tools, and techniques used in the LaRC study can be used to evaluate

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

    Energy Technology Data Exchange (ETDEWEB)

    Blanchard, A.

    1999-05-10

    '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.'

  2. Criticality safety analysis for mockup facility

    International Nuclear Information System (INIS)

    Shin, Young Joon; Shin, Hee Sung; Kim, Ik Soo; Oh, Seung Chul; Ro, Seung Gy; Bae, Kang Mok

    2000-03-01

    Benchmark calculations for SCALE4.4 CSAS6 module have been performed for 31 UO 2 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 K eff is 0.28356 well below than the critical limit, K eff =0.95 at normal condition. In a hypothetical accidental condition, the maximum K eff 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. K eff has been calculated as function of slab thickness and the volume ratio of water to nuclear material. The result shows that the K eff increases as the water volume ratio increases. It is also revealed that the K eff reaches to the maximum value when water if filled in the empty space of nuclear material. The maximum K eff value is 0.93960 lower than the subcritical limit

  3. New mass-spectrometric facility for the analysis of highly radioactive samples

    International Nuclear Information System (INIS)

    Warmack, R.J.; Landau, L.; Christie, W.H.; Carter, J.A.

    1981-01-01

    A new facility has been completed for the analysis of highly radioactive, gamma-emitting solid samples. A commercial spark-source mass spectrometer was adapted for remote handling and loading. Electrodes are prepared in a hot cell and transported to the adjacent lead-shielded source for analysis. The source was redesigned for ease of shielding, loading, and maintenance. Both solutions and residues from irradiated nuclear fuel dissolutions have been analyzed for elemental concentrations to < 1 ppM; isotopic data have also been obtained

  4. Exploratory Studies Facility Subsurface Fire Hazards Analysis

    International Nuclear Information System (INIS)

    Logan, Richard C.

    2002-01-01

    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

  5. The visigothic treasure of Torredonjimeno (Jaen, Spain): A study with IBA techniques

    International Nuclear Information System (INIS)

    Perea, A.; Climent-Font, A.; Fernandez-Jimenez, M.; Enguita, O.; Gutierrez, P.C.; Calusi, S.; Migliori, A.; Montero, I.

    2006-01-01

    The visigothic treasure of Torredonjimeno (Jaen, Spain) was found by chance in the year 1926 buried in an olive grove. The finding consisted of some hundreds fragments of gold objects and gems coming from several votive crowns and crosses, some of them belonging to an unidentified visigothic king. The treasure may belong chronologically to the same period as the Guarrazar treasure or, possibly, to a somewhat later time, but the pieces are fragmented and of less technological workmanship than the latter. This is the reason why the Torredonjimeno treasure has not attracted as much attention from archeologists and art historians as that from Guarrazar. On the occasion of an exhibition showing together all the objects of the treasure, it is normally kept in three different museums in Barcelona, Cordoba and Madrid, a number of pieces were analyzed, using PIXE, PIGE and RBS, at the external microbeam facility installed at the Center for Micro-Analysis of Materials

  6. 340 Waste Handling Facility interim safety basis

    International Nuclear Information System (INIS)

    Bendixsen, R.B.

    1995-01-01

    This document establishes the interim safety basis (ISB) for the 340 Waste Handling Facility (340 Facility). An ISB is a documented safety basis that provides a justification for the continued operation of the facility until an upgraded final safety analysis report is prepared that complies with US Department of Energy (DOE) Order 5480.23, Nuclear Safety Analysis Reports. The ISB for the 340 Facility documents the current design and operation of the facility. The 340 Facility ISB (ISB-003) is based on a facility walkdown and review of the design and operation of the facility, as described in the existing safety documentation. The safety documents reviewed, to develop ISB-003, include the following: OSD-SW-153-0001, Operating Specification Document for the 340 Waste Handling Facility (WHC 1990); OSR-SW-152-00003, Operating Limits for the 340 Waste Handling Facility (WHC 1989); SD-RE-SAP-013, Safety Analysis Report for Packaging, Railroad Liquid Waste Tank Cars (Mercado 1993); SD-WM-TM-001, Safety Assessment Document for the 340 Waste Handling Facility (Berneski 1994a); SD-WM-SEL-016, 340 Facility Safety Equipment List (Berneski 1992); and 340 Complex Fire Hazard Analysis, Draft (Hughes Assoc. Inc. 1994)

  7. NASA Johnson Space Center Usability Testing and Analysis Facility (WAF) Overview

    Science.gov (United States)

    Whitmore, M.

    2004-01-01

    The Usability Testing and Analysis Facility (UTAF) is part of the Space Human Factors Laboratory at the NASA Johnson Space Center in Houston, Texas. The facility provides support to the Office of Biological and Physical Research, the Space Shuttle Program, the International Space Station Program, and other NASA organizations. In addition, there are ongoing collaborative research efforts with external businesses and universities. The UTAF provides human factors analysis, evaluation, and usability testing of crew interfaces for space applications. This includes computer displays and controls, workstation systems, and work environments. The UTAF has a unique mix of capabilities, with a staff experienced in both cognitive human factors and ergonomics. The current areas of focus are: human factors applications in emergency medical care and informatics; control and display technologies for electronic procedures and instructions; voice recognition in noisy environments; crew restraint design for unique microgravity workstations; and refinement of human factors processes. This presentation will provide an overview of ongoing activities, and will address how the projects will evolve to meet new space initiatives.

  8. RISK ASSESSMENT BY STRUCTURAL ANALYSIS AND VIBRATION MEASUREMENT EQUIPMENT OPERATING AT OIL FACILITIES

    Directory of Open Access Journals (Sweden)

    Marius STAN

    2013-05-01

    Full Text Available Vibration analysis applications in operation is one of the diagnostic methods ofoperation of the facility. Analysis of these types of failures indicated the existence of specificfeatures prints and related equipment vibration spectra. Modeling and identification of theseparticular aspects in the spectrum of vibration machines help to control the operation of oilfacilities built safely.

  9. Undergraduate Research and Training in Ion-Beam Analysis of Environmental Materials

    Science.gov (United States)

    Vineyard, Michael F.; Chalise, Sajju; Clark, Morgan L.; LaBrake, Scott M.; McCalmont, Andrew M.; McGuire, Brendan C.; Mendez, Iseinie I.; Watson, Heather C.; Yoskowitz, Joshua T.

    We have an active undergraduate research program at the Union College Ion-Beam Analysis Laboratory (UCIBAL) focused on the study of environmental materials. Accelerator-based ion-beam analysis (IBA) is a powerful tool for the study of environmental pollution because it can provide information on a broad range of elements with high sensitivity and low detection limits, is non-destructive, and requires little or no sample preparation. It also provides excellent training for the next generation of environmental scientists. Beams of protons and alpha particles with energies of a few MeV from the 1.1-MV tandem Pelletron accelerator (NEC Model 3SDH) in the UCIBAL are used to characterize environmental samples using IBA techniques such as proton-induced X-ray emission, Rutherford back-scattering, and proton-induced gamma-ray emission. Recent projects include the characterization of atmospheric aerosols in the Adirondack Mountains of upstate New York, the study of heavy metal pollutants in river sediment, measurements of Pb diffusion in sulfide minerals to help constrain the determination of the age of iron meteorites, and the search for heavy metals and toxins in artificial turf.

  10. Probabilistic safety analysis for nuclear fuel cycle facilities, an exemplary application for a fuel fabrication plant

    International Nuclear Information System (INIS)

    Gmal, B.; Gaenssmantel, G.; Mayer, G.; Moser, E.F.

    2013-01-01

    In order to assess the risk of complex technical systems, the application of the Probabilistic Safety Assessment (PSA) in addition to the Deterministic Safety Analysis becomes of increasing interest. Besides nuclear installations this applies to e. g. chemical plants. A PSA is capable of expanding the basis for the risk assessment and of complementing the conventional deterministic analysis, by which means the existing safety standards of that facility can be improved if necessary. In the available paper, the differences between a PSA for a nuclear power plant and a nuclear fuel cycle facility (NFCF) are discussed in shortness and a basic concept for a PSA for a nuclear fuel cycle facility is described. Furthermore, an exemplary PSA for a partial process in a fuel assembly fabrication facility is described. The underlying data are partially taken from an older German facility, other parts are generic. Moreover, a selected set of reported events corresponding to this partial process is taken as auxiliary data. The investigation of this partial process from the fuel fabrication as an example application shows that PSA methods are in principle applicable to nuclear fuel cycle facilities. Here, the focus is on preventing an initiating event, so that the system analysis is directed to the modeling of fault trees for initiating events. The quantitative results of this exemplary study are given as point values for the average occurrence frequencies. They include large uncertainties because of the limited documentation and data basis available, and thus have only methodological character. While quantitative results are given, further detailed information on process components and process flow is strongly required for robust conclusions with respect to the real process. (authors)

  11. Preparation of safety analysis reports (SARs) for near surface radioactive waste disposal facilities. Format and content of SARs

    International Nuclear Information System (INIS)

    1995-02-01

    All facilities at which radioactive wastes are processed, stored and disposed of have the potential for causing hazards to humans and to the environment. Precautions must be taken in the siting, design and operation of the facilities to ensure that an adequate level of safety is achieved. The processes by which this is evaluated is called safety assessment. An important part of safety assessment is the documentation of the process. A well prepared safety analysis report (SAR) is essential if approval of the facility is to be obtained from the regulatory authorities. This TECDOC describes the format and content of a safety analysis report for a near surface radioactive waste disposal facility and will serve essentially as a checklist in this respect

  12. Cost analysis of the US spent nuclear fuel reprocessing facility

    Energy Technology Data Exchange (ETDEWEB)

    Schneider, E.A.; Deinert, M.R. [Department of Mechanical Engineering, University of Texas, Austin TX (United States); Cady, K.B. [Department of Theoretical and Applied Mechanics, Cornell University, Ithaca NY (United States)

    2009-09-15

    The US Department of Energy is actively seeking ways in which to delay or obviate the need for additional nuclear waste repositories beyond Yucca Mountain. All of the realistic approaches require the reprocessing of spent nuclear fuel. However, the US currently lacks the infrastructure to do this and the costs of building and operating the required facilities are poorly established. Recent studies have also suggested that there is a financial advantage to delaying the deployment of such facilities. We consider a system of government owned reprocessing plants, each with a 40 year service life, that would reprocess spent nuclear fuel generated between 2010 and 2100. Using published data for the component costs, and a social discount rate appropriate for intergenerational analyses, we establish the unit cost for reprocessing and show that it increases slightly if deployment of infrastructure is delayed by a decade. The analysis indicates that achieving higher spent fuel discharge burnup is the most important pathway to reducing the overall cost of reprocessing. The analysis also suggests that a nuclear power production fee would be a way for the US government to recover the costs in a manner that is relatively insensitive to discount and nuclear power growth rates. (author)

  13. The ionoluminescence apparatus at the LABEC external microbeam facility

    International Nuclear Information System (INIS)

    Calusi, S.; Colombo, E.; Giuntini, L.; Giudice, A. Lo; Manfredotti, C.; Massi, M.; Pratesi, G.; Vittone, E.

    2008-01-01

    In this paper, we describe the main features of the ionoluminescence (IL) apparatus recently installed at the external scanning microbeam facility of the 3 MV Tandetron accelerator of the INFN LABEC Laboratory in Firenze. The peculiarity of this IL set-up resides in the fact that the light produced by the ion irradiation of the specimen is collected by a bifurcated optical fiber, so that photons are shunted both to a CCD spectrometer, working in the 200-900 nm wavelength range, and to a photomultiplier (PMT). The accurate focusing of the optical system allows high photon collection efficiency and this results in rapid acquisition of luminescence spectra with low ion currents on luminescent materials; simultaneously, luminescence maps with a spatial resolution of 10 μm can be acquired through the synchronization of PMT photon detection with the position of the scanning focused ion beam. An optical filter with a narrow passband facing the photomultiplier allows chromatic selectivity of the luminescence centres. The IL apparatus is synergistically integrated into the existing set-up for ion beam analyses (IBA). The upgraded system permits simultaneous IL and PIXE/PIGE/BS measurements. With our integrated system, we have been studying raw lapis lazuli samples of different known origins and precious lapis lazuli artworks of the Collezione Medicea of Museum of Natural History, University of Firenze, aiming at characterising their composition and provenance

  14. The ionoluminescence apparatus at the LABEC external microbeam facility

    Energy Technology Data Exchange (ETDEWEB)

    Calusi, S.; Colombo, E. [INFN Sezione di Torino, Via P.Giuria 1, 10125 Torino (Italy); Dipartimento di Fisica Sperimentale and NIS Excellence Centre, Universita di Torino, Via P. Giuria 1, 10125 Torino (Italy); Giuntini, L. [Dipartimento di Fisica, Universita and INFN Sezione di Firenze, Via Sansone 1, 50019, Sesto Fiorentino, Firenze (Italy)], E-mail: giuntini@fi.infn.it; Giudice, A. Lo [Dipartimento di Fisica Sperimentale and NIS Excellence Centre, Universita di Torino, Via P. Giuria 1, 10125 Torino (Italy); Manfredotti, C. [INFN Sezione di Torino, Via P.Giuria 1, 10125 Torino (Italy); Dipartimento di Fisica Sperimentale and NIS Excellence Centre, Universita di Torino, Via P. Giuria 1, 10125 Torino (Italy); Massi, M. [Dipartimento di Fisica, Universita and INFN Sezione di Firenze, Via Sansone 1, 50019, Sesto Fiorentino, Firenze (Italy); Pratesi, G. [Dipartimento di Scienze della Terra and Museo di Storia Naturale, Universita di Firenze, Via G. La Pira 4, 50121 Firenze (Italy); Vittone, E. [INFN Sezione di Torino, Via P.Giuria 1, 10125 Torino (Italy); Dipartimento di Fisica Sperimentale and NIS Excellence Centre, Universita di Torino, Via P. Giuria 1, 10125 Torino (Italy)

    2008-05-15

    In this paper, we describe the main features of the ionoluminescence (IL) apparatus recently installed at the external scanning microbeam facility of the 3 MV Tandetron accelerator of the INFN LABEC Laboratory in Firenze. The peculiarity of this IL set-up resides in the fact that the light produced by the ion irradiation of the specimen is collected by a bifurcated optical fiber, so that photons are shunted both to a CCD spectrometer, working in the 200-900 nm wavelength range, and to a photomultiplier (PMT). The accurate focusing of the optical system allows high photon collection efficiency and this results in rapid acquisition of luminescence spectra with low ion currents on luminescent materials; simultaneously, luminescence maps with a spatial resolution of 10 {mu}m can be acquired through the synchronization of PMT photon detection with the position of the scanning focused ion beam. An optical filter with a narrow passband facing the photomultiplier allows chromatic selectivity of the luminescence centres. The IL apparatus is synergistically integrated into the existing set-up for ion beam analyses (IBA). The upgraded system permits simultaneous IL and PIXE/PIGE/BS measurements. With our integrated system, we have been studying raw lapis lazuli samples of different known origins and precious lapis lazuli artworks of the Collezione Medicea of Museum of Natural History, University of Firenze, aiming at characterising their composition and provenance.

  15. MYRRHA. An innovative and unique research facility

    Energy Technology Data Exchange (ETDEWEB)

    Fernandez, Rafaeol; Neerdael, Bernard; Schyns, Marc; Dyck, Steven Van; Michiels, Sidney; Ait Abderrahim, Hamid, E-mail: myrrha@sckcen.be [Belgian Nuclear Research Centre (SCK-CEN), Mol (Belgium)

    2012-03-15

    The MYRRHA project started in 1998 by SCK{center_dot}CEN in collaboration with Ion Beam Applications (IBA, Louvain-la-Neuve), as an upgrade of the ADONIS project. MYRRHA is designed as a multi-purpose irradiation facility in order to support research programmes on fission and fusion reactor structural materials and nuclear fuel development. Applications of these are found in Accelerator Driven Systems (ADS) systems and in present generation as well as in next generation critical reactors. The first objective of MYRRHA however, will be to demonstrate on one hand the ADS concept at a reasonable power level and on the other hand the technological feasibility of transmutation of Minor Actinides (MA) and Long-Lived Fission Products (LLFP) arising from the reprocessing of radioactive waste. MYRRHA will also help the development of the Pb-alloys technology needed for the LFR (Lead Fast Reactor) Gen.IV concept. Transmutation of MA can be completed in an efficient way in fast neutron spectrum facilities. Both critical reactors and sub-critical ADS are potential candidates as dedicated transmutation systems. However, critical reactors, heavily loaded with fuel containing large amounts of MA, pose safety problems caused by unfavourable reactivity coefficients due to the little delayed neutron fraction. A sub-critical ADS operates in a flexible and safe manner even with a core loading containing a high amount of MA leading to achieve a high efficient transmutation. Thus, the sub-criticality is not a virtue but rather a necessity for an efficient and economical burning of the MA. Besides the reduction of the HLW burden, the MYRRHA project will serve the purpose of developing the lead alloys technology as a reactor coolant that can be used in one of the Generation IV reactor concepts namely the Lead Fast Reactor (LFR). Although carrying out the MYRRHA project will lead to the demonstration of the efficient and safe transmutation of MA in ADS systems as the ultimate goal the

  16. Site-specific meteorology identification for DOE facility accident analysis

    International Nuclear Information System (INIS)

    Rabin, S.B.

    1995-01-01

    Currently, chemical dispersion calculations performed for safety analysis of DOE facilities assume a Pasquill D-Stability Class with a 4.5 m/s windspeed. These meteorological conditions are assumed to conservatively address the source term generation mechanism as well as the dispersion mechanism thereby resulting in a net conservative downwind consequence. While choosing this Stability Class / Windspeed combination may result in an overall conservative consequence, the level of conservative can not be quantified. The intent of this paper is to document a methodology which incorporates site-specific meteorology to determine a quantifiable consequence of a chemical release. A five-year meteorological database, appropriate for the facility location, is utilized for these chemical consequence calculations, and is consistent with the approach used for radiological releases. The hourly averages of meteorological conditions have been binned into 21 groups for the chemical consequence calculations. These 21 cases each have a probability of occurrence based on the number of times each case has occurred over the five year sampling period. A code has been developed which automates the running of all the cases with a commercially available air modeling code. The 21 cases are sorted by concentration. A concentration may be selected by the user for a quantified level of conservatism. The methodology presented is intended to improve the technical accuracy and defensability of Chemical Source Term / Dispersion Safety Analysis work. The result improves the quality of safety analyses products without significantly increasing the cost

  17. 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)

  18. Analysis of obsidians by PIXE technique

    International Nuclear Information System (INIS)

    Nuncio Q, A.E.

    1998-01-01

    This work presents the characterization of obsydian samples from different mineral sites in Mexico, undertaken by an Ion Beam Analysis: PIXE (Proton Induced X-ray Emission). As part of an intensive investigation of obsidian in Mesoamerica by anthropologists from Mexico National Institute of Anthropology and History, 818 samples were collected from different volcanic sources in central Mexico for the purpose of establishing a data bank of element concentrations of each source. Part of this collection was analyzed by Neutron activation analysis and most of the important elements concentrations reported. In this work, a non-destructive IBA technique (PIXE) are used to analyze obsydian samples. The application of this technique were carried out at laboratories of the ININ Nuclear Center facilities. The samples consisted of of obsydians from ten different volcanic sources. This pieces were mounted on a sample holder designed for the purpose of exposing each sample to the proton beam. This PIXE analysis was carried out with an ET Tandem Accelerator at the ININ. X-ray spectrometry was carried out with an external beam facility employing a Si(Li) detector set at 52.5 degrees in relation to the target normal (parallel to the beam direction) and 4.2 cm away from the target center. A filter was set in front of the detector, to determine the best attenuation conditions to obtain most of the elements, taking into account that X-ray spectra from obsydians are dominated by intense major elements lines. Thus, a 28 μ m- thick aluminium foil absorber was selected and used to reduce the intensity of the major lines as well as pile-up effects. The mean proton energy was 2.62 MeV, and the beam profile was about 4 mm in diameter. As results were founded elemental concentrations of a set of samples from ten different sources: Altotonga (Veracruz), Penjamo (Guanajuato), Otumba (Mexico), Zinapecuaro (Michoacan), Ucareo (Michoacan), Tres Cabezas (Puebla), Sierra Navajas (Hidalgo), Zaragoza

  19. Integrated Urban Flood Analysis considering Optimal Operation of Flood Control Facilities in Urban Drainage Networks

    Science.gov (United States)

    Moon, Y. I.; Kim, M. S.; Choi, J. H.; Yuk, G. M.

    2017-12-01

    eavy rainfall has become a recent major cause of urban area flooding due to the climate change and urbanization. To prevent property damage along with casualties, a system which can alert and forecast urban flooding must be developed. Optimal performance of reducing flood damage can be expected of urban drainage facilities when operated in smaller rainfall events over extreme ones. Thus, the purpose of this study is to execute: A) flood forecasting system using runoff analysis based on short term rainfall; and B) flood warning system which operates based on the data from pump stations and rainwater storage in urban basins. In result of the analysis, it is shown that urban drainage facilities using short term rainfall forecasting data by radar will be more effective to reduce urban flood damage than using only the inflow data of the facility. Keywords: Heavy Rainfall, Urban Flood, Short-term Rainfall Forecasting, Optimal operating of urban drainage facilities. AcknowledgmentsThis research was supported by a grant (17AWMP-B066744-05) from Advanced Water Management Research Program (AWMP) funded by Ministry of Land, Infrastructure and Transport of Korean government.

  20. Irradiation facilities in JRR-3M

    International Nuclear Information System (INIS)

    Ohtomo, Akitoshi; Sigemoto, Masamitsu; Takahashi, Hidetake

    1992-01-01

    Irradiation facilities have been installed in the upgraded JRR-3 (JRR-3M) in Japan Atomic Energy Research Institute (JAERI). There are hydraulic rabbit facilities (HR), pneumatic rabbit facilities (PN), neutron activation analysis facility (PN3), uniform irradiation facility (SI), rotating irradiation facility and capsule irradiation facilities to carry out the neutron irradiation in the JRR-3M. These facilities are operated using a process control computer system to centerize the process information. Some of the characteristics for the facilities were satisfactorily measured at the same time of reactor performance test in 1990. During reactor operation, some of the tests are continued to confirm the basic characteristics on facilities, for example, PN3 was confirmed to have enough performance for activation analysis. Measurement of neutron flux at all irradiation positions has been carried out for the equilibrium core. (author)

  1. Groundwater flow analysis using mixed hybrid finite element method for radioactive waste disposal facilities

    International Nuclear Information System (INIS)

    Aoki, Hiroomi; Shimomura, Masanori; Kawakami, Hiroto; Suzuki, Shunichi

    2011-01-01

    In safety assessments of radioactive waste disposal facilities, ground water flow analysis are used for calculating the radionuclide transport pathway and the infiltration flow rate of groundwater into the disposal facilities. For this type of calculations, the mixed hybrid finite element method has been used and discussed about the accuracy of ones in Europe. This paper puts great emphasis on the infiltration flow rate of groundwater into the disposal facilities, and describes the accuracy of results obtained from mixed hybrid finite element method by comparing of local water mass conservation and the reliability of the element breakdown numbers among the mixed hybrid finite element method, finite volume method and nondegenerated finite element method. (author)

  2. Exploratory Studies Facility Subsurface Fire Hazards Analysis

    International Nuclear Information System (INIS)

    Kubicek, J. L.

    2001-01-01

    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

  3. Risk assessment of CST-7 proposed waste treatment and storage facilities Volume I: Limited-scope probabilistic risk assessment (PRA) of proposed CST-7 waste treatment & storage facilities. Volume II: Preliminary hazards analysis of proposed CST-7 waste storage & treatment facilities

    Energy Technology Data Exchange (ETDEWEB)

    Sasser, K.

    1994-06-01

    In FY 1993, the Los Alamos National Laboratory Waste Management Group [CST-7 (formerly EM-7)] requested the Probabilistic Risk and Hazards Analysis Group [TSA-11 (formerly N-6)] to conduct a study of the hazards associated with several CST-7 facilities. Among these facilities are the Hazardous Waste Treatment Facility (HWTF), the HWTF Drum Storage Building (DSB), and the Mixed Waste Receiving and Storage Facility (MWRSF), which are proposed for construction beginning in 1996. These facilities are needed to upgrade the Laboratory`s storage capability for hazardous and mixed wastes and to provide treatment capabilities for wastes in cases where offsite treatment is not available or desirable. These facilities will assist Los Alamos in complying with federal and state requlations.

  4. MYRRHA. An experimental ADS Facility for Research and Development

    International Nuclear Information System (INIS)

    Ait Abderrahim, H.

    2006-01-01

    Full text of publication follows: Since 1998, SCK-CEN in partnership with IBA s.a. and many European research laboratories, is designing a multipurpose ADS for R and D applications MYRRHA - and is conducting an associated R and D support programme. MYRRHA is an Accelerator Driven System (ADS) under development at Mol in Belgium and aiming to serve as a basis for the European experimental ADS to provide protons and neutrons for various R and D applications. It consists of a proton accelerator delivering a 350 MeV * 5 mA proton beam to a liquid Pb-Bi spallation target that in turn couples to a Pb-Bi cooled, subcritical fast core. In a first stage, the project focuses mainly on demonstration of the ADS concept, safety research on sub-critical systems and nuclear waste transmutation studies. In a later stage, the device will also be dedicated to research on structural materials, nuclear fuel, liquid metal technology and associated aspects and on sub-critical reactor physics. Subsequently, it will be used as fast spectrum irradiation facility and as radioisotope production facility. Along the above design features, the MYRRHA project team is developing the MYRRHA project as a multipurpose irradiation facility for R and D applications on the basis of an Accelerator Driven System (ADS). The project is intended to fit into the European strategy towards an ADS Demo facility for nuclear waste transmutation as described in the PDS-XADS FP5 Project. As such it should serve the following task catalogue: ADS concept demonstration, Safety studies for ADS, MA transmutation studies, LLFP transmutation studies, Medical radioisotopes, Material research, Fuel research. A first preliminary conceptual design file of MYRRHA was completed by the end of 2001 and has been reviewed by an International Technical Guidance Committee that concluded that there are no show stoppers in the project even thought some topics such as the safety studies and the fuel qualification need to be addressed

  5. A description of the BNL active surface analysis facility

    International Nuclear Information System (INIS)

    Tyler, J.W.

    1989-11-01

    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 600 0 C. (author)

  6. Influence of growth regulators (IBA, BA on anatomical and morphological changes in bromeliads in in vitro culture

    Directory of Open Access Journals (Sweden)

    Renata Galek

    2014-01-01

    Full Text Available The subject of study were Tillandsia coronata and Guzmania monostachya. The material has been obtained by means of in vitro propagation. The plants were grown for 18 weeks on various kinds of media. Morphological changes were recorded in both species subjected to action of growth regulators. The changes in plant habit were linked with anatomic build. The effect of cytokinin BA upon growth of the stem pith was found, transversely to its axis, through development of numerous meristematic centres and growth and development of adventitious shoots. Leaves of plant grown on media containing cyto-kinin BA were build of a higher number of cell layers of assimilation parenchyma. In plants grown on media with addition of cytokinin the size of stomatal cells was smaller and was accompanied by analogous changes in size of epidermis cells proper. The bushy type of the plants, caused by presence of cytokinin in medium, resulted from the increase of thickness and breadth of leaves and growth of the stem pith, with simultaneous inhibition of cells' elongation. Auxin IBA did not favour the growth of the existing axillary shoots, but stimulated elongation of the stem pith. The stomata of plants of both species grown on media with addition of auxin were bigger. As result of the applied growth regulators a higher frequency of appearance of binucleate cells was found in parenchyma cells of the stem and leaves in both the species studied.

  7. Large scale and low latency analysis facilities for the CMS experiment: development and operational aspects

    CERN Document Server

    Riahi, Hassen

    2010-01-01

    While a majority of CMS data analysis activities rely on the distributed computing infrastructure on the WLCG Grid, dedicated local computing facilities have been deployed to address particular requirements in terms of latency and scale. The CMS CERN Analysis Facility (CAF) was primarily designed to host a large variety of latency-critical workfows. These break down into alignment and calibration, detector commissioning and diagnosis, and high-interest physics analysis requiring fast turnaround. In order to reach the goal for fast turnaround tasks, the Workload Management group has designed a CRABServer based system to fit with two main needs: to provide a simple, familiar interface to the user (as used in the CRAB Analysis Tool[7]) and to allow an easy transition to the Tier-0 system. While the CRABServer component had been initially designed for Grid analysis by CMS end-users, with a few modifications it turned out to be also a very powerful service to manage and monitor local submissions on the CAF. Tran...

  8. Improving primary health care facility performance in Ghana: efficiency analysis and fiscal space implications.

    Science.gov (United States)

    Novignon, Jacob; Nonvignon, Justice

    2017-06-12

    Health centers in Ghana play an important role in health care delivery especially in deprived communities. They usually serve as the first line of service and meet basic health care needs. Unfortunately, these facilities are faced with inadequate resources. While health policy makers seek to increase resources committed to primary healthcare, it is important to understand the nature of inefficiencies that exist in these facilities. Therefore, the objectives of this study are threefold; (i) estimate efficiency among primary health facilities (health centers), (ii) examine the potential fiscal space from improved efficiency and (iii) investigate the efficiency disparities in public and private facilities. Data was from the 2015 Access Bottlenecks, Cost and Equity (ABCE) project conducted by the Institute for Health Metrics and Evaluation. The Stochastic Frontier Analysis (SFA) was used to estimate efficiency of health facilities. Efficiency scores were then used to compute potential savings from improved efficiency. Outpatient visits was used as output while number of personnel, hospital beds, expenditure on other capital items and administration were used as inputs. Disparities in efficiency between public and private facilities was estimated using the Nopo matching decomposition procedure. Average efficiency score across all health centers included in the sample was estimated to be 0.51. Also, average efficiency was estimated to be about 0.65 and 0.50 for private and public facilities, respectively. Significant disparities in efficiency were identified across the various administrative regions. With regards to potential fiscal space, we found that, on average, facilities could save about GH₵11,450.70 (US$7633.80) if efficiency was improved. We also found that fiscal space from efficiency gains varies across rural/urban as well as private/public facilities, if best practices are followed. The matching decomposition showed an efficiency gap of 0.29 between private

  9. 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

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

    International Nuclear Information System (INIS)

    Vasconcelos, Vanderley de; Reis, Sergio Carneiro dos; Costa, Antonio Carlos Lopes da; Jordao, Elizabete

    2008-01-01

    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

  11. Thermal Analysis Of A 9975 Package In A Facility Fire Accident

    International Nuclear Information System (INIS)

    Gupta, N.

    2011-01-01

    Surplus plutonium bearing materials in the U.S. Department of Energy (DOE) complex are stored in the 3013 containers that are designed to meet the requirements of the DOE standard DOE-STD-3013. The 3013 containers are in turn packaged inside 9975 packages that are designed to meet the NRC 10 CFR Part 71 regulatory requirements for transporting the Type B fissile materials across the DOE complex. The design requirements for the hypothetical accident conditions (HAC) involving a fire are given in 10 CFR 71.73. The 9975 packages are stored at the DOE Savannah River Site in the K-Area Material Storage (KAMS) facility for long term of up to 50 years. The design requirements for safe storage in KAMS facility containing multiple sources of combustible materials are far more challenging than the HAC requirements in 10 CFR 71.73. While the 10 CFR 71.73 postulates an HAC fire of 1475 F and 30 minutes duration, the facility fire calls for a fire of 1500 F and 86 duration. This paper describes a methodology and the analysis results that meet the design limits of the 9975 component and demonstrate the robustness of the 9975 package.

  12. NASA Johnson Space Center Usability Testing and Analysis facility (UTAF) Overview

    Science.gov (United States)

    Whitmore, Mihriban; Holden, Kritina L.

    2005-01-01

    The Usability Testing and Analysis Facility (UTAF) is part of the Space Human Factors Laboratory at the NASA Johnson Space Center in Houston, Texas. The facility performs research for NASA's HumanSystems Integration Program, under the HumanSystems Research and Technology Division. Specifically, the UTAF provides human factors support for space vehicles, including the International Space Station, the Space Shuttle, and the forthcoming Crew Exploration Vehicle. In addition, there are ongoing collaborative research efforts with external corporations and universities. The UTAF provides human factors analysis, evaluation, and usability testing of crew interfaces for space applications. This includes computer displays and controls, workstation systems, and work environments. The UTAF has a unique mix of capabilities, with a staff experienced in both cognitive human factors and ergonomics. The current areas of focus are: human factors applications in emergency medical care and informatics; control and display technologies for electronic procedures and instructions; voice recognition in noisy environments; crew restraint design for unique microgravity workstations; and refinement of human factors processes and requirements. This presentation will provide an overview of ongoing activities, and will address how the UTAF projects will evolve to meet new space initiatives.

  13. Stored energy analysis in scale-down test facility

    International Nuclear Information System (INIS)

    Deng Chengcheng; Qin Benke; Fang Fangfang; Chang Huajian; Ye Zishen

    2013-01-01

    In the integral test facilities that simulate the accident transient process of the prototype nuclear power plant, the stored energy in the metal components has a direct influence on the simulation range and the test results of the facilities. Based on the heat transfer theory, three methods analyzing the stored energy were developed, and a thorough study on the stored energy problem in the scale-down test facilities was further carried out. The lumped parameter method and power integration method were applied to analyze the transient process of energy releasing and to evaluate the average total energy stored in the reactor pressure vessel of the ACME (advanced core-cooling mechanism experiment) facility, which is now being built in China. The results show that the similarity requirements for such three methods to analyze the stored energy in the test facilities are reduced gradually. Under the condition of satisfying the integral similarity of natural circulation, the stored energy releasing process in the scale-down test facilities can't maintain exact similarity. The stored energy in the reactor pressure vessel wall of ACME, which is released quickly during the early stage of rapid depressurization of system, will not make a major impact on the long-term behavior of system. And the scaling distortion of integral average total energy of the stored heat is acceptable. (authors)

  14. 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.

  15. 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.

  16. Present and future role of ion beam analysis in the study of cultural heritage materials: The example of the AGLAE facility

    International Nuclear Information System (INIS)

    Salomon, J.; Dran, J.-C.; Guillou, T.; Moignard, B.; Pichon, L.; Walter, P.; Mathis, F.

    2008-01-01

    The application of IBA to cultural heritage mostly relies on the use of PIXE because of its high sensitivity and its ease of implementation at atmospheric pressure. The need for depth information not easily available with this technique has conducted to associate RBS also in external beam mode. We have progressively developed a set-up that permits such a combination of techniques either simultaneously or sequentially. The set-up is currently further improved to permit NRA measurement (depth profiles of light elements) in addition to PIXE and RBS. The coupling of all these techniques provides a wealth of information on cultural heritage objects, not easily attainable with any other single method

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

    International Nuclear Information System (INIS)

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

    1993-01-01

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

  18. Analysis of Student Satisfaction Toward Quality of Service Facility

    Science.gov (United States)

    Napitupulu, D.; Rahim, R.; Abdullah, D.; Setiawan, MI; Abdillah, LA; Ahmar, AS; Simarmata, J.; Hidayat, R.; Nurdiyanto, H.; Pranolo, A.

    2018-01-01

    The development of higher education is very rapid rise to the tight competition both public universities and private colleges. XYZ University realized to win the competition, required continuous quality improvement, including the quality of existing service facilities. Amenities quality services is believed to support the success of the learning activities and improve user satisfaction. This study aims to determine the extent to which the quality of the services effect on user satisfaction. The research method used is survey-based questionnaire that measure perception and expectation. The results showed a gap between perception and expectations of the respondents have a negative value for each item. This means XYZ service facility at the university is not currently meet the expectations of society members. Three service facility that has the lowest index is based on the perception of respondents is a laboratory (2.56), computer and multimedia (2.63) as well as wifi network (2.99). The magnitude of the correlation between satisfaction with the quality of service facilities is 0.725 which means a strong and positive relationship. The influence of the quality of service facilities to the satisfaction of the students is 0.525 meaning that the variable quality of the services facility can explain 52.5% of the variable satisfaction. The study provided recommendations for improvements to enhance the quality of services facility at the XYZ university facilities.

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

    International Nuclear Information System (INIS)

    Sanchez, F. A.; Calzetta, O

    2004-01-01

    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 10 6 n/cm 2 s 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 [es

  20. The CERN analysis facility-a PROOF cluster for day-one physics analysis

    International Nuclear Information System (INIS)

    Grosse-Oetringhaus, J F

    2008-01-01

    ALICE (A Large Ion Collider Experiment) at the LHC plans to use a PROOF cluster at CERN (CAF - CERN Analysis Facility) for analysis. The system is especially aimed at the prototyping phase of analyses that need a high number of development iterations and thus require a short response time. Typical examples are the tuning of cuts during the development of an analysis as well as calibration and alignment. Furthermore, the use of an interactive system with very fast response will allow ALICE to extract physics observables out of first data quickly. An additional use case is fast event simulation and reconstruction. A test setup consisting of 40 machines is used for evaluation since May 2006. The PROOF system enables the parallel processing and xrootd the access to files distributed on the test cluster. An automatic staging system for files either catalogued in the ALICE file catalog or stored in the CASTOR mass storage system has been developed. The current setup and ongoing development towards disk quotas and CPU fairshare are described. Furthermore, the integration of PROOF into ALICE's software framework (AliRoot) is discussed

  1. 100 mg 251Cf activation analysis facility at the Savannah River Laboratory

    International Nuclear Information System (INIS)

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

    1975-01-01

    The 252 Cf Activation Analysis Facility at the Savannah River Laboratory (SRL) is used routinely for multielement analyses of a wide variety of solid and liquid samples (e.g., metal alloys, fly ash and other airborne particles, rocks, and aqueous and nonaqueous solutions). An automated absolute activation analysis technique, developed to use neutron transport codes to calculate multienergy group neutron spectra and fluxes, converts counting data directly into elemental concentrations expressed in parts per million. The facility contains four sources of 252 Cf totaling slightly over 100 mg. A pneumatic ''rabbit'' system permits automatic irradiation/decay/counting regimes to be performed unattended on up to 100 samples. Detection sensitivities of less than or equal to 400 ppb natural uranium and less than or equal to 0.5 nCi/g for 239 Pu are observed. Detection limits for over 65 elements have been determined. Over 40 elements are detectable at the one part per million level or less. Overall accuracies of +- 10 percent are observed for most elements. (auth)

  2. Risk assessment of CST-7 proposed waste treatment and storage facilities Volume I: Limited-scope probabilistic risk assessment (PRA) of proposed CST-7 waste treatment ampersand storage facilities. Volume II: Preliminary hazards analysis of proposed CST-7 waste storage ampersand treatment facilities

    International Nuclear Information System (INIS)

    Sasser, K.

    1994-06-01

    In FY 1993, the Los Alamos National Laboratory Waste Management Group [CST-7 (formerly EM-7)] requested the Probabilistic Risk and Hazards Analysis Group [TSA-11 (formerly N-6)] to conduct a study of the hazards associated with several CST-7 facilities. Among these facilities are the Hazardous Waste Treatment Facility (HWTF), the HWTF Drum Storage Building (DSB), and the Mixed Waste Receiving and Storage Facility (MWRSF), which are proposed for construction beginning in 1996. These facilities are needed to upgrade the Laboratory's storage capability for hazardous and mixed wastes and to provide treatment capabilities for wastes in cases where offsite treatment is not available or desirable. These facilities will assist Los Alamos in complying with federal and state requlations

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

    International Nuclear Information System (INIS)

    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

  4. Seismic risk analysis for the Babcock and Wilcox facility, Leechburg, Pennsylvania

    International Nuclear Information System (INIS)

    1977-01-01

    The results of a detailed seismic risk analysis of the Babcock and Wilcox Plutonium Fuel Fabrication facility at Leechburg, Pennsylvania are presented. This report focuses on earthquakes; the other natural hazards, being addressed in separate reports, are severe weather (strong winds and tornados) and floods. The calculational method used is based on Cornell's work (1968); it has been previously applied to safety evaluations of major projects. 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. Because of the aseismicity of the region around the site, an analysis different from the conventional closest approach in a tectonic province was adapted. Earthquakes as far from the site as 1,000 km were included, as were the possibility of earthquakes at the site. In addition, various uncertainties in the input were explicitly considered in the analysis. The results of the risk analysis, which include a Bayesian estimate of the uncertainties, are presented, expressed as return period accelerations. The best estimate curve indicates that the Babcock and Wilcox facility will experience 0.05 g every 220 years and 0.10 g every 1400 years. The bounding curves roughly represent the one standard deviation confidence limits about the best estimate, reflecting the uncertainty in certain of the input. Detailed examination of the results show that the accelerations are very insensitive to the details of the source region geometries or the historical earthquake statistics in each region and that each of the source regions contributes almost equally to the cumulative risk at the site. If required for structural analysis, acceleration response spectra for the site can be constructed by scaling the mean response spectrum for alluvium in WASH 1255 by these peak accelerations

  5. Use of risk assessment methods for security design and analysis of nuclear and radioactive facilities

    International Nuclear Information System (INIS)

    Vasconcelos, Vanderley de; Andrade, Marcos C.; Jordao, Elizabete

    2011-01-01

    The objective of this work is to evaluate the applicability of risk assessment methods for analyzing the physical protection of nuclear and radioactive facilities. One of the important processes for physical protection in nuclear and radioactive facilities is the identifying of areas containing nuclear materials, structures, systems or components to be protected from sabotage, which could directly or indirectly lead to unacceptable radiological consequences. A survey of the international guidelines and recommendations about vital area identification, design basis threat (DBT), and the security of nuclear and radioactive facilities was carried out. The traditional methods used for quantitative risk assessment, like FMEA (Failure Mode and Effect Analysis), Event and Decision Trees, Fault and Success Trees, Vulnerability Assessment, Monte Carlo Simulation, Probabilistic Safety Assessment, Scenario Analysis, and Game Theory, among others, are highlighted. The applicability of such techniques to security issues, their pros and cons, the general resources needed to implement them, as data or support software, are analyzed. Finally, an approach to security design and analysis, beginning with a qualitative and preliminary examination to determine the range of possible scenarios, outcomes, and the systems to be included in the analyses, and proceeding to a progressively use of more quantitative techniques is presented. (author)

  6. Analysis of raft foundations for spent fuel pool in nuclear facilities

    International Nuclear Information System (INIS)

    Subramanian, K.V.; Kashikar, A.V.; Nath, C.; Shintre, C.C.

    2005-01-01

    Foundation rafts are analysed as a plate on elastic foundation with the representation of the foundation media using the Winkler idealisation i.e. series of linear uncoupled springs. The elastic constant of the Winkler springs is derived using the sub-grade modulus. However, the Winkler approach has limitations due to incompatibility of the deflections at raft-soil interface. The deflection of the raft at the point of contact and the deformation of the foundation media at this point of contact are incompatible in this approach. This particularly influences flexible rafts and further if the foundation media is soil. This paper discusses the analysis of raft, in general, and the analysis of the foundation raft for a Spent Fuel pool facility using 'variable k approach' where deformations at a node and influencing nodes are computed using Boussinesq's theory. The limitations stated above are overcome in this approach. Some studies on the sensitivity of parameters were carried out in the form of variation of moduli of elasticity of concrete and deformation modulus of soil. Analysis is also performed with conventional method using 'Winkler' soil springs. It is concluded that the Winkler model does not correctly predict the behaviour of the mat both qualitatively and quantitatively and could lead to underestimation of soil pressures leading to unconservative design. The approach involving soil structure interaction like the one presented here is hence recommended for important structures like those involved in Nuclear facilities. (authors)

  7. Analysis of glycerin waste in A-Area sanitary treatment facility material

    International Nuclear Information System (INIS)

    1995-01-01

    TNX has a large supply of 55 gallon drums containing pure glycerin and glycerin with additives. The glycerin drums were procured to simulate the glass stream in a pilot-scale melter process at TNX. Since the glycerin was not used for this process, TNX is looking at disposing the material in a sanitary waste treatment facility onsite. The effect of adding the contents of the drums to sewage bacteria was tested. A drum of pure glycerin and a drum of glycerin mixed with lithium chloride were tested. The test consisted of mixing sanitary sludge material with the glycerin material. The purpose of the test was to determine if the glycerin impacted the aerobic bacterial population. The bacterial densities were determined by taking samples from the sludge/glycerin mixtures and using aerobic plate count methods. The total organic carbon (TOC) levels were measured before and after testing. The results indicate that the cell density of the aerobic bacteria increased with the addition of glycerin and the glycerin mixture and the TOC removal rate was different for all tests. Disposal of glycerin in the wastewater treatment facilities should pose no problems. Additional testing and analysis of the mixed samples should be done before its disposal in a waste water treatment facility

  8. Facility effluent monitoring plan for the 325 Facility

    International Nuclear Information System (INIS)

    1998-01-01

    The Applied Chemistry Laboratory (325 Facility) houses radiochemistry research, radioanalytical service, radiochemical process development, and hazardous and mixed hazardous waste treatment activities. The laboratories and specialized facilities enable work ranging from that with nonradioactive materials to work with picogram to kilogram quantities of fissionable materials and up to megacurie quantities of other radionuclides. The special facilities include two shielded hot-cell areas that provide for process development or analytical chemistry work with highly radioactive materials, and a waste treatment facility for processing hazardous, mixed, low-level, and transuranic wastes generated by Pacific Northwest Laboratory. Radioactive material storage and usage occur throughout the facility and include a large number of isotopes. This material is in several forms, including solid, liquid, particulate, and gas. Some of these materials are also heated during testing which can produce vapors. The research activities have been assigned to the following activity designations: High-Level Hot Cell, Hazardous Waste Treatment Unit, Waste Form Development, Special Testing Projects, Chemical Process Development, Analytical Hot Cell, and Analytical Chemistry. The following summarizes the airborne 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

  9. 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.

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

    International Nuclear Information System (INIS)

    Lee, Hee-Seock; Kim, Dong-hyun; Oranj, Leila Mokhtari; Oh, Joo-Hee; Lee, Arim; Jung, Nam-Suk

    2015-01-01

    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

  11. Reliability Analysis Of Fire System On The Industry Facility By Use Fameca Method

    International Nuclear Information System (INIS)

    Sony T, D.T.; Situmorang, Johnny; Ismu W, Puradwi; Demon H; Mulyanto, Dwijo; Kusmono, Slamet; Santa, Sigit Asmara

    2000-01-01

    FAMECA is one of the analysis method to determine system reliability on the industry facility. Analysis is done by some procedure that is identification of component function, determination of failure mode, severity level and effect of their failure. Reliability value is determined by three combinations that is severity level, component failure value and critical component. Reliability of analysis has been done for fire system on the industry by FAMECA method. Critical component which identified is pump, air release valve, check valve, manual test valve, isolation valve, control system etc

  12. Enraizamento de estacas de oliveira submetidas a aplicação de fertilizantes orgânicos e AIB Rooting of olive tree cuttings using organic fertilizations and IBA

    Directory of Open Access Journals (Sweden)

    Marcelo Caetano de Oliveira

    2010-04-01

    Full Text Available Estacas semilenhosas de oliveiras 'Ascolano 315', foram preparadas com aproximadamente 12 cm de comprimento e quatro folhas, sendo, em seguida, tratadas, ou não, com 3000 mg L-1 de AIB por cinco segundos O experimento foi conduzido em casa de vegetação, com sistema de nebulização intermitente, sendo as estacas colocadas em bancadas de propagação, contendo a perlita como substrato. Antes do plantio das estacas, foram aplicados os fertilizantes orgânicos Biofertilizante e Nippoterra, nas dosagens 0, 20, 40 e 60 mL L-1. Os produtos foram aplicados nas parcelas experimentais com regador manual, em dosagem única. Passados 58 dias, foi mensurada a porcentagem de estacas com calo, enraizadas, enraizadas e/ou com calo, número médio de raízes e comprimento médio das raízes. Concluiu-se que a dosagem de 40 mL L-1 de Biofertilizante propiciou melhores resultados, com a utilização de AIB.Semi hardwood cutting was colletecd in the medium portion of the 'Ascolano 315' olive trees, prepared with 12 cm in length and four leaves, treated or not with 3000 mg L-1 of IBA by five seconds. The experiment was conducted in a greenhouse, with a system of intermittent nebulization. The cutting was placed in propagation supports, containing perlite as a substrate. Before the plantation of the cutting, organic fertilizers Biofertilizante and Nippoterra were applied in the proportion: 0, 20, 40 and 60 mL L-1. The products were applied in the experimental portions in a single dose. After 58 days, the percentage of cutting with callus, taken root, taken root and/or with callus, average number of roots and average length of the roots were evaluated. The 40 mL L-1 of Biofertilizante gave the best results, with IBA.

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

    International Nuclear Information System (INIS)

    Payne, T.E.; McGlinn, P.J.

    2007-01-01

    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)

  14. PANDA a multi-purpose thermal-hydraulics facility devoted to nuclear reactor containment safety analysis

    International Nuclear Information System (INIS)

    Paladino, Domenico

    2014-01-01

    This paper presents the multi purpose facility PANDA devised for the safety analysis of nuclear reactor containment. The passive safety systems for LWRs have been explained with details about the PAssive Nachzerfallswärmeabfuhr und Druck-Abbau Testanlage (PANDA)

  15. High-current Rhodotron for X-ray facility

    International Nuclear Information System (INIS)

    Umezu, Toru; Tsujiura, Yuichiro; Bol, Jean Louis

    2009-01-01

    The Rhodotron is a widely employed high-power industrial accelerator developed and exclusively distributed by IBA. Most early examples of the accelerator were optimized to operate at 10 MeV. A new Rhodotron configuration recently advanced produces a lower-energy higher-current beam dedicated with x-ray to sterilize and enhancement materials. Core elements of this system's evolution include a higher performance RF electron gun (operating range, response control, and cathode lifetime). This operational machine is now producing 100 mA at 7 MeV (700 kW of beam) and treat medical devices, thick cable and pipes with a high efficiency. (author)

  16. Strategic facility planning improves capital decision making.

    Science.gov (United States)

    Reeve, J R

    2001-03-01

    A large, Midwestern IDS undertook a strategic facility-planning process to evaluate its facility portfolio and determine how best to allocate future investments in facility development. The IDS assembled a facility-planning team, which initiated the planning process with a market analysis to determine future market demands and identify service areas that warranted facility expansion. The team then analyzed each of the IDS's facilities from the perspective of uniform capacity measurements, highest and best use compared with needs, building condition and investment-worthiness, and facility growth and site development opportunities. Based on results of the analysis, the strategy adopted entailed, in part, shifting some space from inpatient care to ambulatory care services and demolishing and replacing the 11 percent of facilities deemed to be in the worst condition.

  17. MEASURE: An integrated data-analysis and model identification facility

    Science.gov (United States)

    Singh, Jaidip; Iyer, Ravi K.

    1990-01-01

    The first phase of the development of MEASURE, an integrated data analysis and model identification facility is described. The facility takes system activity data as input and produces as output representative behavioral models of the system in near real time. In addition a wide range of statistical characteristics of the measured system are also available. The usage of the system is illustrated on data collected via software instrumentation of a network of SUN workstations at the University of Illinois. Initially, statistical clustering is used to identify high density regions of resource-usage in a given environment. The identified regions form the states for building a state-transition model to evaluate system and program performance in real time. The model is then solved to obtain useful parameters such as the response-time distribution and the mean waiting time in each state. A graphical interface which displays the identified models and their characteristics (with real time updates) was also developed. The results provide an understanding of the resource-usage in the system under various workload conditions. This work is targeted for a testbed of UNIX workstations with the initial phase ported to SUN workstations on the NASA, Ames Research Center Advanced Automation Testbed.

  18. National Ignition Facility (NIF) Control Network Design and Analysis

    International Nuclear Information System (INIS)

    Bryant, R M; Carey, R W; Claybourn, R V; Pavel, G; Schaefer, W J

    2001-01-01

    The control network for the National Ignition Facility (NIF) is designed to meet the needs for common object request broker architecture (CORBA) inter-process communication, multicast video transport, device triggering, and general TCP/IP communication within the NIF facility. The network will interconnect approximately 650 systems, including the embedded controllers, front-end processors (FEPs), supervisory systems, and centralized servers involved in operation of the NIF. All systems are networked with Ethernet to serve the majority of communication needs, and asynchronous transfer mode (ATM) is used to transport multicast video and synchronization triggers. CORBA software infra-structure provides location-independent communication services over TCP/IP between the application processes in the 15 supervisory and 300 FEP systems. Video images sampled from 500 video cameras at a 10-Hz frame rate will be multicast using direct ATM Application Programming Interface (API) communication from video FEPs to any selected operator console. The Ethernet and ATM control networks are used to broadcast two types of device triggers for last-second functions in a large number of FEPs, thus eliminating the need for a separate infrastructure for these functions. Analysis, design, modeling, and testing of the NIF network has been performed to provide confidence that the network design will meet NIF control requirements

  19. CATHARE 2 analysis of the small break LOCA experiment SP-SB-03, conducted in SPES facility

    International Nuclear Information System (INIS)

    Meloni, P.

    1995-01-01

    SPES integral test facility is a scale model of a commercial three-loop PWR plant, making the simulation of a wide range of accident scenarios possible. A Small Break Loss of Coolant test was carried out in this facility in 1991 to serve as a counterpart of tests conducted on BETHSY (France), LSTF (Japan) and LOBI (EC) facilities. A post-test analysis of this test, performed with CATHARE 2 code was realized by ENEA in the framework of the co-operation ENEA-CEA on advanced reactors. This paper presents a survey of the results of the post-test calculation. (author). 5 refs, 11 figs, 3 tabs

  20. The new 6 MV AMS-facility DREAMS at Dresden

    International Nuclear Information System (INIS)

    Akhmadaliev, Shavkat; Heller, René; Hanf, Daniel; Rugel, Georg; Merchel, Silke

    2013-01-01

    Highlights: ► New 6 MV tandem accelerator in operation in Germany for AMS, IBA and HE-implantation. ► DREsden AMS (DREAMS) primarily used for radionuclides 10 Be, 26 Al, 36 Cl, 41 Ca and 129 I. ► Quality assurance by traceable calibration materials and interlaboratory comparisons. High accuracy data for future DREAMS users. ► Energy calibration of accelerator by 1 H( 15 N,γα) 12 C yield correction factor of 1.019. - Abstract: A new 6 MV electrostatic tandem accelerator has been put into operation at Helmholtz-Zentrum Dresden-Rossendorf (HZDR). The system is equipped for accelerator mass spectrometry and opens a new research field at HZDR and the Helmholtz Association. It will be also used for ion beam analysis as well as for material modification via high-energy ion implantation. The research activity at the DREsden Accelerator Mass Spectrometry facility (DREAMS) based on a 6 MV Tandetron is primarily dedicated to the long-lived radioisotopes of 10 Be, 26 Al, 36 Cl, 41 Ca, and 129 I. DREAMS background levels have been found to be at 4.5 × 10 −16 for 10 Be/ 9 Be, 8 × 10 −16 for 26 Al/ 27 Al, 3 × 10 −15 for 36 Cl/ 35 Cl and 8 × 10 −15 for 41 Ca/ 40 Ca, respectively. The observed background of 2 × 10 −13 for 129 I/ 127 I originates from intrinsic 129 I from AgI produced from commercial KI. The introduction of quality assurance approaches for AMS, such as the use of traceable calibration materials and taking part in interlaboratory comparisons, guarantees high accuracy data for future DREAMS users. During first experiments an energy calibration of the accelerator has been carried out using the nuclear reaction 1 H( 15 N,γα) 12 C yielding an energy correction factor of 1.019.

  1. Elemental thin film depth profiles by ion beam analysis using simulated annealing - a new tool

    International Nuclear Information System (INIS)

    Jeynes, C; Barradas, N P; Marriott, P K; Boudreault, G; Jenkin, M; Wendler, E; Webb, R P

    2003-01-01

    Rutherford backscattering spectrometry (RBS) and related techniques have long been used to determine the elemental depth profiles in films a few nanometres to a few microns thick. However, although obtaining spectra is very easy, solving the inverse problem of extracting the depth profiles from the spectra is not possible analytically except for special cases. It is because these special cases include important classes of samples, and because skilled analysts are adept at extracting useful qualitative information from the data, that ion beam analysis is still an important technique. We have recently solved this inverse problem using the simulated annealing algorithm. We have implemented the solution in the 'IBA DataFurnace' code, which has been developed into a very versatile and general new software tool that analysts can now use to rapidly extract quantitative accurate depth profiles from real samples on an industrial scale. We review the features, applicability and validation of this new code together with other approaches to handling IBA (ion beam analysis) data, with particular attention being given to determining both the absolute accuracy of the depth profiles and statistically accurate error estimates. We include examples of analyses using RBS, non-Rutherford elastic scattering, elastic recoil detection and non-resonant nuclear reactions. High depth resolution and the use of multiple techniques simultaneously are both discussed. There is usually systematic ambiguity in IBA data and Butler's example of ambiguity (1990 Nucl. Instrum. Methods B 45 160-5) is reanalysed. Analyses are shown: of evaporated, sputtered, oxidized, ion implanted, ion beam mixed and annealed materials; of semiconductors, optical and magnetic multilayers, superconductors, tribological films and metals; and of oxides on Si, mixed metal silicides, boron nitride, GaN, SiC, mixed metal oxides, YBCO and polymers. (topical review)

  2. The relationship of sport participation to provision of sports facilities and socioeconomic status: a geographical analysis.

    Science.gov (United States)

    Eime, Rochelle M; Harvey, Jack; Charity, Melanie J; Casey, Meghan; Westerbeek, Hans; Payne, Warren R

    2017-06-01

    Ecological models have been applied to investigate multiple domains influencing physical activity behaviour, including individual, social, organisational, community, environmental and policy factors. With regard to the built environment, research to date has been limited to small geographical areas and/or small samples of participants. This study examined the geographical association between provision of sport facilities and participation in sport across an entire Australian state, using objective total enumerations of both, for a group of sports, with adjustment for the effect of socioeconomic status (SES). De-identified membership registration data were obtained from state sport governing bodies of four popular team sports. Associations between participation rate, facility provision rate and SES were investigated using correlation and regression methods. Participation rate was positively associated with provision of facilities, although this was complicated by SES and region effects. The non-metropolitan region generally had higher participation rates and better provision of facilities than the metropolitan region. Better provision of sports facilities is generally associated with increased sport participation, but SES and region are also contributing factors. Implications for public health: Community-level analysis of the population, sport participation and provision of facilities should be used to inform decisions of investments in sports facilities. © 2017 The Authors.

  3. Sustainable Facilities Management

    DEFF Research Database (Denmark)

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

    2004-01-01

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

  4. ATLAS Tier-3 within IFIC-Valencia analysis facility

    CERN Document Server

    Villaplana, M; The ATLAS collaboration; Fernández, A; Salt, J; Lamas, A; Fassi, F; Kaci, M; Oliver, E; Sánchez, J; Sánchez-Martínez, V

    2012-01-01

    The ATLAS Tier-3 at IFIC-Valencia is attached to a Tier-2 that has 50% of the Spanish Federated Tier-2 resources. In its design, the Tier-3 includes a GRID-aware part that shares some of the features of IFIC Tier-2 such as using Lustre as a file system. ATLAS users, 70% of IFIC users, also have the possibility of analysing data with a PROOF farm and storing them locally. In this contribution we discuss the design of the analysis facility as well as the monitoring tools we use to control and improve its performance. We also comment on how the recent changes in the ATLAS computing GRID model affect IFIC. Finally, how this complex system can coexist with the other scientific applications running at IFIC (non-ATLAS users) is presented.

  5. 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

  6. Shielding of Medical Facilities. Shielding Design Considerations for PET-CT Facilities

    International Nuclear Information System (INIS)

    Cruzate, J.A.; Discacciatti, A.P.

    2011-01-01

    The radiological evaluation of a Positron Emission Tomography (PET) facility consists of the assessment of the annual effective dose both to workers occupationally exposed, and to members of the public. This assessment takes into account the radionuclides involved, the facility features, the working procedures, the expected number of patients per year, and so on. The evaluation embraces the distributions of rooms, the thickness and physical material of walls, floors and ceilings. This work detail the methodology used for making the assessment of a PET facility design taking into account only radioprotection aspects. The assessment results must be compared to the design requirements established by national regulations in order to determine whether or not, the facility complies with those requirements, both for workers and for members of the public. The analysis presented is useful for both, facility designers and regulators. In addition, some guidelines for improving the shielding design and working procedures are presented in order to help facility designer's job. (authors)

  7. Technical Merits and Leadership in Facility Management

    National Research Council Canada - National Science Library

    Shoemaker, Jerry

    1997-01-01

    .... The document is divided into six chapters; the introduction, facility management and leadership, building systems, facility operations, facility maintenance strategies, and the conclusion and final analysis...

  8. 340 waste handling facility interim safety basis

    Energy Technology Data Exchange (ETDEWEB)

    VAIL, T.S.

    1999-04-01

    This document presents an interim safety basis for the 340 Waste Handling Facility classifying the 340 Facility as a Hazard Category 3 facility. The hazard analysis quantifies the operating safety envelop for this facility and demonstrates that the facility can be operated without a significant threat to onsite or offsite people.

  9. 340 waste handling facility interim safety basis

    International Nuclear Information System (INIS)

    VAIL, T.S.

    1999-01-01

    This document presents an interim safety basis for the 340 Waste Handling Facility classifying the 340 Facility as a Hazard Category 3 facility. The hazard analysis quantifies the operating safety envelop for this facility and demonstrates that the facility can be operated without a significant threat to onsite or offsite people

  10. Engineering Evaluation/Cost Analysis for the 100-N Area Ancillary Facilities and Integration Plan

    International Nuclear Information System (INIS)

    Mukherjee, B.

    1997-09-01

    This document presents the results of an engineering evaluation/cost analysis (EE/CA) that was conducted to evaluate alternatives for addressing final disposition of contaminated buildings and structures in the 100-N Area of the Hanford Site. The Hanford Site is located in southeastern Washington State and is owned by the U.S. Government and operated by the U.S. Department of Energy, Richland Operations Office (RL). In November 1989, the 100 Area of the Hanford Site (as well as the 200, 300, and 1100 Areas) was placed on the U.S. Environmental Protection Agency's National Priorities List (NPL) under the Comprehensive Environmental Response, Compensation, and Liability Act of 1980. The 100 Area NPL includes the 100-N Area, which is in various stages of the remediation process. It has been determined by RL that hazardous substances in the 100-N Area ancillary facilities may present a potential threat to human health or the environment, and that a non-time critical removal action at these facilities is warranted. To help determine the most appropriate action, RL, in cooperation with the Washington State Department of Ecology (Ecology) and the EPA, has prepared this EE/CA. The scope of the evaluation includes the inactive contaminated ancillary facilities in the 100-N Area, the facilities residing in the buffer zone, and the Hanford Generating Plant (HGP) and the solid waste management units (SWMUs) inside HGP support facilities. The 105-N Reactor and 109-N Heat Exchange facilities are excluded from this EE/CA evaluation

  11. Shielding structure analysis for LSDS facility

    Energy Technology Data Exchange (ETDEWEB)

    Choi, Hong Yeop; Kim, Jeong Dong; Lee, Yong Deok; Kim, Ho Dong [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2014-05-15

    The nuclear material (Pyro, Spent nuclear fuel) itself and the target material to generate neutrons is the LSDS system for isotopic fissile assay release of high intensity neutron and gamma rays. This research was performed to shield from various strong radiation. A shielding evaluation was carried out with a facilities model of LSDS system. The MCNPX 2.5 code was used and a shielding evaluation was performed for the shielding structure and location. The radiation dose based on the hole structure and location of the wall was evaluated. The shielding evaluation was performed to satisfy the safety standard for a normal person (1 μSv/h) and to use enough interior space. The MCNPX2.5 code was used and a dose evaluation was performed for the location of the shielding material, shielding structure, and hole structure. The evaluation result differs according to the shielding material location. The dose rate was small when the shielding material was positioned at the center. The dose evaluation result regarding the location of the shielding material was applied to the facility and the shielding thickness was determined (In 50 cm + Borax 5 cm + Out 45cm). In the existing hole structure, the radiation leak is higher than the standard. A hole structure model to prevent leakage of radiation was proposed. The general public dose limit was satisfied when using the concrete reinforcement and a zigzag structure. The shielding result will be of help to the facility shielding optimization.

  12. Shielding structure analysis for LSDS facility

    International Nuclear Information System (INIS)

    Choi, Hong Yeop; Kim, Jeong Dong; Lee, Yong Deok; Kim, Ho Dong

    2014-01-01

    The nuclear material (Pyro, Spent nuclear fuel) itself and the target material to generate neutrons is the LSDS system for isotopic fissile assay release of high intensity neutron and gamma rays. This research was performed to shield from various strong radiation. A shielding evaluation was carried out with a facilities model of LSDS system. The MCNPX 2.5 code was used and a shielding evaluation was performed for the shielding structure and location. The radiation dose based on the hole structure and location of the wall was evaluated. The shielding evaluation was performed to satisfy the safety standard for a normal person (1 μSv/h) and to use enough interior space. The MCNPX2.5 code was used and a dose evaluation was performed for the location of the shielding material, shielding structure, and hole structure. The evaluation result differs according to the shielding material location. The dose rate was small when the shielding material was positioned at the center. The dose evaluation result regarding the location of the shielding material was applied to the facility and the shielding thickness was determined (In 50 cm + Borax 5 cm + Out 45cm). In the existing hole structure, the radiation leak is higher than the standard. A hole structure model to prevent leakage of radiation was proposed. The general public dose limit was satisfied when using the concrete reinforcement and a zigzag structure. The shielding result will be of help to the facility shielding optimization

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

    International Nuclear Information System (INIS)

    Orndoff, J.D.; Paxton, H.C.; Wimett, T.F.

    1979-05-01

    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

  14. Facility effluent monitoring plan for the 324 Facility

    International Nuclear Information System (INIS)

    1994-11-01

    The 324 Facility [Waste Technology Engineering Laboratory] in the 300 Area primarily supports the research and development of radioactive and nonradioactive waste vitrification technologies, biological waste remediation technologies, spent nuclear fuel studies, waste mixing and transport studies, and tritium development programs. All of the above-mentioned programs deal with, and have the potential to, release hazardous and/or radioactive material. The potential for discharge would primarily result from (1) conducting research activities using the hazardous materials, (2) storing radionuclides and hazardous chemicals, and (3) waste accumulation and storage. This report summarizes the airborne and liquid effluents, and the results of the Facility Effluent Monitoring Plan (FEMP) determination for the facility. The complete monitoring plan includes characterizing effluent streams, monitoring/sampling design criteria, a description of the monitoring systems and sample analysis, and quality assurance requirements

  15. Analysis of the State of the Network of Restaurant Facilities in the Districts of the Kharkiv City

    Directory of Open Access Journals (Sweden)

    Genadiy Anisimov

    2018-01-01

    Full Text Available The analysis of the state of the network of restaurants in the regions of Kharkiv (Ukraine based on the data from 2014-2017 years has been carried out. The dynamics of such characteristic indicators of the network as the number of facilities, the total network capacity, the number of facilities by types, their capacity, and the average number of places in facilities are considered. The basic tendencies of research objects dynamics are formulated. A comparison of the state of the network with regulatory requirements and data on the state of the networks in the European Union has been made.

  16. The new AMS system at CEDAD for the analysis of {sup 10}Be, {sup 26}Al, {sup 129}I and actinides: Set-up and performances

    Energy Technology Data Exchange (ETDEWEB)

    Calcagnile, Lucio, E-mail: lucio.calcagnile@unisalento.it [CEDAD (Centre for Dating and Diagnostics), Department of Engineering for Innovation, University of Salento (Italy); Quarta, Gianluca; Maruccio, Lucio [CEDAD (Centre for Dating and Diagnostics), Department of Engineering for Innovation, University of Salento (Italy); Synal, Hans-Arno; Müller, Arnold Milenko [Laboratory of Ion Beam Physics, ETH Zurich, 8093 Zurich (Switzerland)

    2015-10-15

    The Centre for Dating and Diagnostics (CEDAD) at the University of Salento was established in 2001 and became fully operational for routine {sup 14}C radiocarbon dating in 2003. The facility has been continuously upgraded over the years with the installation of different beam lines for high energy ion implantation, IBA analyses both in vacuum and in air and nuclear microprobe. In 2011 a second AMS beamline was installed consisting of a dedicated high energy mass spectrometer for the AMS analysis of rare nuclides such as {sup 10}Be, {sup 26}Al, {sup 129}I and actinides. First tests on {sup 10}Be allowed to optimize the operating parameters resulting in the proper separation of {sup 10}Be from the interfering isobar {sup 10}B. In this paper we present the further tests and optimizations which resulted in an enhancement of the overall transmission efficiency, the reduction of the background (in the 10{sup −15} range) and in the possibility to obtain precision levels in routine {sup 10}Be/{sup 9}Be measurements of the order of 0.5%. Furthermore the first results obtained for the analysis of {sup 26}Al and {sup 129}I are also presented.

  17. Triassico: A Sphere Positioning System for Surface Studies with IBA Techniques

    Science.gov (United States)

    Fontana, Cristiano L.; Doyle, Barney L.

    We propose here a novel device, called the Triassico, to microscopically study the entire surface of millimeter-sized spheres. The sphere dimensions can be as small as 1 mm, and the upper limit defined only by the power and by the mechanical characteristics of the motors used. Three motorized driving rods are arranged so an equilateral triangle is formed by the rod's axes, on such a triangle the sphere sits. Movement is achieved by rotating the rods with precise relative speeds and by exploiting the friction between the sphere and the rods surfaces. The sphere can be held in place by gravity or by an opposing trio of rods. By rotating the rods with specific relative angular velocities, a net torque can be exerted on the sphere which then rotates. No repositioning of the sphere or of the motors is needed to cover the full surface with the investigating tools. An algorithm was developed to position the sphere at any arbitrary polar and azimuthal angle. The algorithm minimizes the number of rotations needed by the rods, in order to efficiently select a particular position on the sphere surface. A prototype Triassico was developed for the National Ignition Facility, of the Lawrence Livermore National Laboratory (Livermore, California, USA), as a sphere manipulation apparatus for ion microbeam analysis at Sandia National Laboratories (Albuquerque, NM, USA) of Xe-doped DT inertial confinement fusion fuel spheres. Other applications span from samples orientation, ball bearing manufacturing, or jewelry.

  18. A graded approach to safety documentation at processing facilities

    International Nuclear Information System (INIS)

    Cowen, M.L.

    1992-01-01

    Westinghouse Savannah River Company (WSRC) has over 40 major Safety Analysis Reports (SARs) in preparation for non-reactor facilities. These facilities include nuclear material production facilities, waste management facilities, support laboratories and environmental remediation facilities. The SARs for these various projects encompass hazard levels from High to Low, and mission times from startup, through operation, to shutdown. All of these efforts are competing for scarce resources, and therefore some mechanism is required for balancing the documentation requirements. Three of the key variables useful for the decision making process are Depth of Safety Analysis, Urgency of Safety Analysis, and Resource Availability. This report discusses safety documentation at processing facilities

  19. DUPIC facility engineering

    Energy Technology Data Exchange (ETDEWEB)

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

    1997-09-01

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

  20. DUPIC facility engineering

    International Nuclear Information System (INIS)

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

    1997-09-01

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

  1. Pressure Effects Analysis of National Ignition Facility Capacitor Module Events

    International Nuclear Information System (INIS)

    Brereton, S; Ma, C; Newton, M; Pastrnak, J; Price, D; Prokosch, D

    1999-01-01

    Capacitors and power conditioning systems required for the National Ignition Facility (NIF) have experienced several catastrophic failures during prototype demonstration. These events generally resulted in explosion, generating a dramatic fireball and energetic shrapnel, and thus may present a threat to the walls of the capacitor bay that houses the capacitor modules. The purpose of this paper is to evaluate the ability of the capacitor bay walls to withstand the overpressure generated by the aforementioned events. Two calculations are described in this paper. The first one was used to estimate the energy release during a fireball event and the second one was used to estimate the pressure in a capacitor module during a capacitor explosion event. Both results were then used to estimate the subsequent overpressure in the capacitor bay where these events occurred. The analysis showed that the expected capacitor bay overpressure was less than the pressure tolerance of the walls. To understand the risk of the above events in NIF, capacitor module failure probabilities were also calculated. This paper concludes with estimates of the probability of single module failure and multi-module failures based on the number of catastrophic failures in the prototype demonstration facility

  2. Berkeley Low Background Facility

    International Nuclear Information System (INIS)

    Thomas, K. J.; Norman, E. B.; Smith, A. R.; Poon, A. W. P.; Chan, Y. D.; Lesko, K. T.

    2015-01-01

    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

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

    International Nuclear Information System (INIS)

    Gabrielsen, B.L.; Tsai, K.

    1981-04-01

    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

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

    International Nuclear Information System (INIS)

    Orndoff, J.D.; Paxton, H.C.; Wimett, T.F.

    1980-12-01

    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

  5. The inhibition of subchondral bone lesions significantly reversed the weight-bearing deficit and the overexpression of CGRP in DRG neurons, GFAP and Iba-1 in the spinal dorsal horn in the monosodium iodoacetate induced model of osteoarthritis pain.

    Directory of Open Access Journals (Sweden)

    Degang Yu

    Full Text Available Chronic pain is the most prominent and disabling symptom of osteoarthritis (OA. Clinical data suggest that subchondral bone lesions contribute to the occurrence of joint pain. The present study investigated the effect of the inhibition of subchondral bone lesions on joint pain.Osteoarthritic pain was induced by an injection of monosodium iodoacetate (MIA into the rat knee joint. Zoledronic acid (ZOL, a third generation of bisphosphonate, was used to inhibit subchondral bone lesions. Joint histomorphology was evaluated using X-ray micro computed tomography scanning and hematoxylin-eosin staining. The activity of osteoclast in subchondral bone was evaluated using tartrate-resistant acid phosphatase staining. Joint pain was evaluated using weight-bearing asymmetry, the expression of calcitonin gene-related peptide (CGRP in the dorsal root ganglion (DRG, and spinal glial activation status using glial fibrillary acidic protein (GFAP and ionized calcium binding adaptor molecule-1 (Iba-1 immunofluorescence. Afferent neurons in the DRGs that innervated the joints were identified using retrograde fluorogold labeling.MIA injections induced significant histomorphological alterations and joint pain. The inhibition of subchondral bone lesions by ZOL significantly reduced the MIA-induced weight-bearing deficit and overexpression of CGRP in DRG neurons, GFAP and Iba-1 in the spinal dorsal horn at 3 and 6 weeks after MIA injection; however, joint swelling and synovial reaction were unaffected.The inhibition of subchondral bone lesions alleviated joint pain. Subchondral bone lesions should be a key target in the management of osteoarthritic joint pain.

  6. Descriptions of reference LWR facilities for analysis of nuclear fuel cycles. Appendixes

    International Nuclear Information System (INIS)

    Schneider, K.J.; Kabele, T.J.

    1979-09-01

    The appendixes present the calculations that were used to derive the release factors discussed for each fuel cycle facility in Volume I. Appendix A presents release factor calculations for a surface mine, underground mine, milling facility, conversion facility, diffusion enrichment facility, fuel fabrication facility, PWR, BWR, and reprocessing facility. Appendix B contains additional release factors calculated for a BWR, PWR, and a reprocessing facility. Appendix C presents release factors for a UO 2 fuel fabrication facility

  7. PROOF as a Service on the Cloud: a Virtual Analysis Facility based on the CernVM ecosystem

    CERN Document Server

    Berzano, Dario; Buncic, Predrag; Charalampidis, Ioannis; Ganis, Gerardo; Lestaris, Georgios; Meusel, René

    2014-01-01

    PROOF, the Parallel ROOT Facility, is a ROOT-based framework which enables interactive parallelism for event-based tasks on a cluster of computing nodes. Although PROOF can be used simply from within a ROOT session with no additional requirements, deploying and configuring a PROOF cluster used to be not as straightforward. Recently great efforts have been spent to make the provisioning of generic PROOF analysis facilities with zero configuration, with the added advantages of positively affecting both stability and scalability, making the deployment operations feasible even for the end user. Since a growing amount of large-scale computing resources are nowadays made available by Cloud providers in a virtualized form, we have developed the Virtual PROOF-based Analysis Facility: a cluster appliance combining the solid CernVM ecosystem and PoD (PROOF on Demand), ready to be deployed on the Cloud and leveraging some peculiar Cloud features such as elasticity. We will show how this approach is effective both for sy...

  8. INVESTIGATION OF QUANTIFICATION OF FLOOD CONTROL AND WATER UTILIZATION EFFECT OF RAINFALL INFILTRATION FACILITY BY USING WATER BALANCE ANALYSIS MODEL

    OpenAIRE

    文, 勇起; BUN, Yuki

    2013-01-01

    In recent years, many flood damage and drought attributed to urbanization has occurred. At present infiltration facility is suggested for the solution of these problems. Based on this background, the purpose of this study is investigation of quantification of flood control and water utilization effect of rainfall infiltration facility by using water balance analysis model. Key Words : flood control, water utilization , rainfall infiltration facility

  9. Using GIFTS on the Cray-1 for the large coil test facility test: stand design analysis

    International Nuclear Information System (INIS)

    Baudry, T.V.; Gray, W.H.

    1981-06-01

    The GIFTS finite element program has been used extensively throughout the Large Coil Test Facility (LCTF) test stand design analysis. Effective use has been made of GIFTS both as a preprocessor to other finite element programs and as a complete structural analysis package. The LCTF test stand design involved stress analysis ranging from simple textbook-type problems to very complicated three-dimensional structural problems. Two areas of the design analysis are discussed

  10. The accelerator under the Louvre (the new AGLAE)

    CERN Multimedia

    CERN. Geneva

    2017-01-01

    THE ACCELERATOR UNDER THE LOUVRE (THE NEW AGLAE) Speaker: Claire Pacheco 1,2 1C2RMF, Palais du Louvre, 75001 Paris, France ² New AGLAE FR 3506 – CNRS/Ministère de la Culture et de la Communication Abstract: For more than 20 years, the AGLAE facility is exclusively dedicated to the study of Cultural Heritage objects in the Louvre premises, at the crossroad of social science and hard science. Because Cultural Heritage artifacts are unique, sometimes sampling cannot be considered. Moreover, the conservation state may also prohibit to work under vacuum. For these reasons, an extracted beamline has been developed especially for ion beam analysis (IBA) on Cultural Heritage objects at the AGLAE facility [1]. Multidisciplinary, the New AGLAE project will provide an exceptional and multipurpose beam line with a performance in spatial resolution, beam stability and a capability of multi-particle detection much higher than for the previous facility. This talk will describe the milest...

  11. Final safety analysis report for the irradiated fuels storage facility

    International Nuclear Information System (INIS)

    Bingham, G.E.; Evans, T.K.

    1976-01-01

    A fuel storage facility has been constructed at the Idaho Chemical Processing Plant to provide safe storage for spent fuel from two commercial HTGR's, Fort St. Vrain and Peach Bottom, and from the Rover nuclear rocket program. The new facility was built as an addition to the existing fuel storage basin building to make maximum use of existing facilities and equipment. The completed facility provides dry storage for one core of Peach Bottom fuel (804 elements), 1 1 / 2 cores of Fort St. Vrain fuel (2200 elements), and the irradiated fuel from the 20 reactors in the Rover program. The facility is designed to permit future expansion at a minimum cost should additional storage space for graphite-type fuels be required. A thorough study of the potential hazards associated with the Irradiated Fuels Storage Facility has been completed, indicating that the facility is capable of withstanding all credible combinations of internal accidents and pertinent natural forces, including design basis natural phenomena of a 10,000 year flood, a 175-mph tornado, or an earthquake having a bedrock acceleration of 0.33 g and an amplification factor of 1.3, without a loss of integrity or a significant release of radioactive materials. The design basis accident (DBA) postulated for the facility is a complete loss of cooling air, even though the occurrence of this situation is extremely remote, considering the availability of backup and spare fans and emergency power. The occurrence of the DBA presents neither a radiation nor an activity release hazard. A loss of coolant has no effect upon the fuel or the facility other than resulting in a gradual and constant temperature increase of the stored fuel. The temperature increase is gradual enough that ample time (28 hours minimum) is available for corrective action before an arbitrarily imposed maximum fuel centerline temperature of 1100 0 F is reached

  12. A DOE-STD-3009 hazard and accident analysis methodology for non-reactor nuclear facilities

    International Nuclear Information System (INIS)

    MAHN, JEFFREY A.; WALKER, SHARON ANN

    2000-01-01

    This paper demonstrates the use of appropriate consequence evaluation criteria in conjunction with generic likelihood of occurrence data to produce consistent hazard analysis results for nonreactor nuclear facility Safety Analysis Reports (SAR). An additional objective is to demonstrate the use of generic likelihood of occurrence data as a means for deriving defendable accident sequence frequencies, thereby enabling the screening of potentially incredible events ( -6 per year) from the design basis accident envelope. Generic likelihood of occurrence data has been used successfully in performing SAR hazard and accident analyses for two nonreactor nuclear facilities at Sandia National Laboratories. DOE-STD-3009-94 addresses and even encourages use of a qualitative binning technique for deriving and ranking nonreactor nuclear facility risks. However, qualitative techniques invariably lead to reviewer requests for more details associated with consequence or likelihood of occurrence bin assignments in the test of the SAR. Hazard analysis data displayed in simple worksheet format generally elicits questions about not only the assumptions behind the data, but also the quantitative bases for the assumptions themselves (engineering judgment may not be considered sufficient by some reviewers). This is especially true where the criteria for qualitative binning of likelihood of occurrence involves numerical ranges. Oftentimes reviewers want to see calculations or at least a discussion of event frequencies or failure probabilities to support likelihood of occurrence bin assignments. This may become a significant point of contention for events that have been binned as incredible. This paper will show how the use of readily available generic data can avoid many of the reviewer questions that will inevitably arise from strictly qualitative analyses, while not significantly increasing the overall burden on the analyst

  13. Evaluation of methods for seismic analysis of nuclear fuel reprocessing and fabrication facilities

    International Nuclear Information System (INIS)

    Arthur, D.F.; Dong, R.G.; Murray, R.C.; Nelson, T.A.; Smith, P.D.; Wight, L.H.

    1978-01-01

    Methods of seismic analysis for critical structures and equipment in nuclear fuel reprocessing plants (NFRPs) and mixed oxide fuel fabrication plants (MOFFPs) are evaluated. The purpose of this series of reports is to provide the NRC with a technical basis for assessing seismic analysis methods and for writing regulatory guides in which methods ensuring the safe design of nuclear fuel cycle facilities are recommended. The present report evaluates methods of analyzing buried pipes and wells, sloshing effects in large pools, earth dams, multiply supported equipment, pile foundations, and soil-structure interactions

  14. Thermal analysis of the drywell for the Nuclear Material Storage Facility

    International Nuclear Information System (INIS)

    Steinke, R.G.

    1997-01-01

    The Nuclear Materials Storage Facility Renovation Project has a conceptual design for the facility to store nuclear materials in containers inside drywells with passive cooling for long-term storage. The CFX thermal-hydraulic computer program was used to analyze internal heat-transfer processes by conduction, convection, and radiation with natural circulation of air by hydraulic buoyancy with turbulence and thermal stratification (TS) evaluated. A vertical drywell was modeled with 14 containers on support plates at 12-in. intervals. The TS of bay air outside the drywell increased the container maximum temperature by 0.728 F for each 1.0 F of bay-air TS from the bottom to the top of the drywell. The drywell outer-surface peak heat flux was shifted downward because of the effect of bay-air TS. An equivalent model was evaluated by the nodal-network conduction, convection, and radiation heat-transfer computer program (Thermal System Analysis Program) TSAP. The TSAP results are in good agreement with the CFX-model results, with the difference in results understood based on the approximations of each model

  15. WHC-SD-W252-FHA-001, Rev. 0: Preliminary fire hazard analysis for Phase II Liquid Effluent Treatment and Disposal Facility, Project W-252

    International Nuclear Information System (INIS)

    Barilo, N.F.

    1995-01-01

    A Fire Hazards Analysis was performed to assess the risk from fire and other related perils and the capability of the facility to withstand these hazards. This analysis will be used to support design of the facility

  16. Local flow distribution analysis inside the reactor pools of KALIMER-600 and PDRC performance test facility

    International Nuclear Information System (INIS)

    Jeong, Ji Hwan; Hwang, Seong Won; Choi, Kyeong Sik

    2010-05-01

    In the study, 3-dimensional thermal hydraulic analysis was carried out focusing on the thermal hydraulic behavior inside the reactor pools for both KALIMER-600 and one-fifth scale-down test facility. STAR-CD, one of the commercial CFD codes, was used to analyze 3-dimensional incompressible steady-state thermal hydraulic behavior in both designs of KALIMER-600 and the scale-down test facility. In the KALIMER-600 CFD analysis, the pressure drops in the core and IHX gave a good agreement within 1% error range. It was found that the porous media model was appropriate to analyze the pressure distribution inside reactor core and IHX. Also, a validation analysis showed the pressure drop through the porous media under the condition of 80% flow rate and thermal power was calculated 64% less than in 100% condition giving a physically reasonable analytic result. Since the temperatures in the hot-side pool and cold-side pool were estimated to be very close to 540 and 390 .deg. C specified on the design values respectively, the CFD models of heat source and sink was confirmed. Through the study, the methodology of 3-dimensional CFD analysis about KALIMER-600 has been established and proven. Performed with the methodology, the analysis data such as flow velocity, temperature and pressure distribution were compared by normalizing those data for the actual sized modeling and scale-down modeling. As a result, the characteristics of thermal hydraulic behavior were almost identical for the actual sized modeling and scale-down modeling and the similarity scaling law used in the design of the sodium test facility by KAERI was found to be correct

  17. Cause finding experiments and environmental analysis on the accident of the fire and explosion in TRP bituminization facility

    International Nuclear Information System (INIS)

    Fujine, Sachio; Murata, Mikio; Abe, Hitoshi

    1999-09-01

    This report is the summary of the cause finding experiments and environmental analysis on the accident of the fire and explosion occurred at March 11th, 1997, in TRP bituminization facility of PNC (Power Reactor and Nuclear Fuel Development Corporation). Regarding the cause finding experiments, chemical components have been analyzed for the effluent samples taken from PNC's facility, bituminized mock waste has been produced using the simulated salt effluent prepared according to the results of chemical analysis, thermal analysis and experiment of runaway exothermic reaction have been conducted using the mock waste, and the component of flammable gases emitted from the heated waste have been collected and analyzed. Regarding environmental analysis on the accident, the amount of radioactive cesium released by the accident has been calculated by the comparative analysis using the atmospheric dispersion simulation code SPEEDI with the data of environmental monitoring and the public dose has been assessed. (author)

  18. Development and Commissioning of an External Beam Facility in the Union College Ion Beam Analysis Laboratory

    Science.gov (United States)

    Yoskowitz, Joshua; Clark, Morgan; Labrake, Scott; Vineyard, Michael

    2015-10-01

    We have developed an external beam facility for the 1.1-MV tandem Pelletron accelerator in the Union College Ion Beam Analysis Laboratory. The beam is extracted from an aluminum pipe through a 1 / 4 ' ' diameter window with a 7.5- μm thick Kapton foil. This external beam facility allows us to perform ion beam analysis on samples that cannot be put under vacuum, including wet samples and samples too large to fit into the scattering chamber. We have commissioned the new facility by performing proton induced X-ray emission (PIXE) analysis of several samples of environmental interest. These include samples of artificial turf, running tracks, and a human tooth with an amalgam filling. A 1.7-MeV external proton beam was incident on the samples positioned 2 cm from the window. The resulting X-rays were measured using a silicon drift detector and were analyzed using GUPIX software to determine the concentrations of elements in the samples. The results on the human tooth indicate that while significant concentrations of Hg, Ag, and Sn are present in the amalgam filling, only trace amounts of Hg appear to have leached into the tooth. The artificial turf and running tracks show rather large concentrations of a broad range of elements and trace amounts of Pb in the turf infill.

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

    International Nuclear Information System (INIS)

    Lee, Young Soon; Jung, Jea Hee; Lee, Keun O; Son, Ki Sang; Wang, Sang Chul; Lee, Chang Jin; Ku, Min Ho; Park, Nam Young

    2003-03-01

    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

  20. 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.

  1. A qualitative analysis of facilities maintenance — A school ...

    African Journals Online (AJOL)

    I analysed school facilities maintenance, a school governance function in South Africa. Qualitative interviews were conducted with 13 principals and three deputy principals as coordinators of this function at their schools. The interviews were purposively and conveniently selected to gather data regarding school facilities ...

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

    International Nuclear Information System (INIS)

    Shin, Hee Sung; Ahn, Seong Kyu; Song, Dae Yong; Lee, Tae Hoon; Kim, Ho Dong; Seo, Ji Sun; Im, Hye In; Jang, Je Nam

    2009-12-01

    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

  3. Waste sampling and characterization facility (WSCF)

    International Nuclear Information System (INIS)

    1994-10-01

    The Waste Sampling and Characterization Facility (WSCF) complex consists of the main structure (WSCF) and four support structures located in the 600 Area of the Hanford site east of the 200 West area and south of the Hanford Meterology Station. WSCF is to be used for low level sample analysis, less than 2 mRem. The Laboratory features state-of-the-art analytical and low level radiological counting equipment for gaseous, soil, and liquid sample analysis. In particular, this facility is to be used to perform Resource Conservation and Recovery Act (RCRA) of 1976 and Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) of 1980 sample analysis in accordance with U.S. Environmental Protection Agency Protocols, room air and stack monitoring sample analysis, waste water treatment process support, and contractor laboratory quality assurance checks. The samples to be analyzed contain very low concentrations of radioisotopes. The main reason that WSCF is considered a Nuclear Facility is due to the storage of samples at the facility. This maintenance Implementation Plan has been developed for maintenace functions associate with the WSCF

  4. Pre-feasibility analysis of powering a remote research facility under arid conditions in Kazakhstan

    Directory of Open Access Journals (Sweden)

    Sagimbayev Sagi

    2017-01-01

    Full Text Available This study evaluates the feasibility of using photovoltaic solar cells and solar water heating in a remote off-grid research facility for scientists in the steppe of Kazakhstan. The objective of the facility is to observe wildlife in this region, especially saiga antelope, whose population has been drastically reduced in recent years. The analysis is conducted using RETScreen software and includes energy, cost, emissions, and financial assessment. The proposed energy model is compared with a traditional base case scenario (based on a diesel boiler and reciprocating engine. Despite the challenges and constraints, the project pays off within its lifespan. It eliminates greenhouse gas emissions and reduces human interference with local wildlife.

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

    International Nuclear Information System (INIS)

    1978-01-01

    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

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

    Energy Technology Data Exchange (ETDEWEB)

    1978-12-29

    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.

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

    International Nuclear Information System (INIS)

    Pili-Vincens, C.

    1998-01-01

    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

  8. Dose verification with different ion chambers for SRT/SBRT plans

    Science.gov (United States)

    Durmus, I. F.; Tas, B.; Okumus, A.; Uzel, O. E.

    2017-02-01

    Verification of patient plan is very important in stereotactic treatments. VMAT plans were prepared with 6MV-FFF or 10MV-FFF energies for 25 intracranial and extracranial stereotactic patients. Absolute dose was measured for dose verification in each plans. Iba® CC01, Iba® CC04, Iba® CC13 ion chambers placed at a depth of 5cm in solid phantom (RW3). Also we scanned this phantom with ion chambers by Siemens® Biograph mCT. QA plans were prepared by transferring twenty five patient plans to phantom assemblies for three ion chambers. All plans were performed separately for three ion chambers at Elekta® Versa HD linear accelerator. Statistical analysis of results were made by Wilcoxon signed-rank test. Difference between dose values were determined %1.84±3.4 (p: 0.001) with Iba CC13 ion chamber, %1.80±3.4 (p: 0.002) with Iba CC04 ion chamber and %0.29±4.6 (p: 0.667) with Iba CC01 ion chamber. In stereotactic treatments, dosimetric uncertainty increases in small areas. We determined more accurate results with small sized detectors. Difference between TPS calculations and all measurements were founded lower than %2.

  9. Study of fast reactor safety test facilities. Preliminary report

    International Nuclear Information System (INIS)

    Bell, G.I.; Boudreau, J.E.; McLaughlin, T.; Palmer, R.G.; Starkovich, V.; Stein, W.E.; Stevenson, M.G.; Yarnell, Y.L.

    1975-05-01

    Included are sections dealing with the following topics: (1) perspective and philosophy of fast reactor safety analysis; (2) status of accident analysis and experimental needs; (3) experiment and facility definitions; (4) existing in-pile facilities; (5) new facility options; and (6) data acquisition methods

  10. Economics of reusable facilities

    International Nuclear Information System (INIS)

    Antia, D.D.J.

    1992-01-01

    In this paper some of the different economic development strategies that can be used for reusable facilities in the UK, Norway, Netherlands and in some production sharing contracts are outlined. These strategies focus on an integrated decision analysis approach which considers development phasing, reservoir management, tax planning and where appropriate facility purchase, leasing, or sale and leaseback decisions

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

    International Nuclear Information System (INIS)

    Shedrow, C.B.

    1999-01-01

    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

  12. 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.

  13. PROOF-based analysis on the ATLAS grid facilities: first experience with the PoD/PanDa plugin

    International Nuclear Information System (INIS)

    Vilucchi, E; Nardo, R Di; Mancini, G; Pineda, A R Sanchez; Salvo, A De; Donato, C Di; Doria, A; Ganis, G; Manafov, A; Mazza, S; Preltz, F; Rebatto, D; Salvucci, A

    2014-01-01

    In the ATLAS computing model Grid resources are managed by PanDA, the system designed for production and distributed analysis, and data are stored under various formats in ROOT files. End-user physicists have the choice to use either the ATHENA framework or directly ROOT, that provides users the possibility to use PROOF to exploit the computing power of multi-core machines or to dynamically manage analysis facilities. Since analysis facilities are, in general, not dedicated to PROOF only, PROOF-on-Demand (PoD) is used to enable PROOF on top of an existing resource management system. In a previous work we investigated the usage of PoD to enable PROOF-based analysis on Tier-2 facilities using the PoD/gLite plug-in interface. In this paper we present the status of our investigations using the recently developed PoD/PanDA plug-in to enable PROOF and a real end-user ATLAS physics analysis as payload. For this work, data were accessed using two different protocols: XRootD and file protocol. The former in the site where the SRM interface is Disk Pool Manager (DPM) and the latter where the SRM interface is StoRM with GPFS file system. We will first describe the results of some benchmark tests we run on the ATLAS Italian Tier-1 and Tier-2s sites and at CERN. Then, we will compare the results of different types of analysis, comparing performances accessing data in relation to different types of SRM interfaces and accessing data with XRootD in the LAN and in the WAN using the ATLAS XROOTD storage federation infrastructure.

  14. Mitigating risks related to facilities management.

    Science.gov (United States)

    O'Neill, Daniel P; Scarborough, Sydney

    2013-07-01

    By looking at metrics focusing on the functionality, age, capital investment, transparency, and sustainability (FACTS) of their organizations' facilities, facilities management teams can build potential business cases to justify upgrading the facilities. A FACTS analysis can ensure that capital spent on facilities will produce a higher or more certain ROI than alternatives. A consistent process for managing spending helps to avoid unexpected spikes that cost the enterprise more in the long run.

  15. Factors influencing women's preference for health facility deliveries in Jharkhand state, India: a cross sectional analysis.

    Science.gov (United States)

    Bhattacharyya, Sanghita; Srivastava, Aradhana; Roy, Reetabrata; Avan, Bilal I

    2016-03-07

    Expanding institutional deliveries is a policy priority to achieve MDG5. India adopted a policy to encourage facility births through a conditional cash incentive scheme, yet 28% of deliveries still occur at home. In this context, it is important to understand the care experience of women who have delivered at home, and also at health facilities, analyzing any differences, so that services can be improved to promote facility births. This study aims to understand women's experience of delivery care during home and facility births, and the factors that influence women's decisions regarding their next place of delivery. A community-based cross-sectional survey was undertaken in a district of Jharkhand state in India. Interviews with 500 recently delivered women (210 delivered at facility and 290 delivered at home) included socio-demographic characteristics, experience of their recent delivery, and preference of future delivery site. Data analysis included frequencies, binary and multiple logistic regressions. There is no major difference in the experience of care between home and facility births, the only difference in care being with regard to pain relief through massage, injection and low cost of delivery for those having home births. 75% women wanted to deliver their next child at a facility, main reasons being availability of medicine (29.4%) and perceived health benefits for mother and baby (15%). Women with higher education (AOR = 1.67, 95% CI = 1.04-3.07), women who were above 25 years (AOR = 2.14, 95% CI = 1.26-3.64), who currently delivered at facility (AOR = 5.19, 95% CI = 2.97-9.08) and had health problem post-delivery (AOR = 1.85, 95% CI = 1.08-3.19) were significant predictors of future facility-based delivery. The predictors for facility deliveries include, availability of medicines and supplies, potential health benefits for the mother and newborn and the perception of good care from the providers. There is a growing

  16. Sanford Underground Research Facility - The United State's Deep Underground Research Facility

    Science.gov (United States)

    Vardiman, D.

    2012-12-01

    The 2.5 km deep Sanford Underground Research Facility (SURF) is managed by the South Dakota Science and Technology Authority (SDSTA) at the former Homestake Mine site in Lead, South Dakota. The US Department of Energy currently supports the development of the facility using a phased approach for underground deployment of experiments as they obtain an advanced design stage. The geology of the Sanford Laboratory site has been studied during the 125 years of operations at the Homestake Mine and more recently as part of the preliminary geotechnical site investigations for the NSF's Deep Underground Science and Engineering Laboratory project. The overall geology at DUSEL is a well-defined stratigraphic sequence of schist and phyllites. The three major Proterozoic units encountered in the underground consist of interbedded schist, metasediments, and amphibolite schist which are crosscut by Tertiary rhyolite dikes. Preliminary geotechnical site investigations included drift mapping, borehole drilling, borehole televiewing, in-situ stress analysis, laboratory analysis of core, mapping and laser scanning of new excavations, modeling and analysis of all geotechnical information. The investigation was focused upon the determination if the proposed site rock mass could support the world's largest (66 meter diameter) deep underground excavation. While the DUSEL project has subsequently been significantly modified, these data are still available to provide a baseline of the ground conditions which may be judiciously extrapolated throughout the entire Proterozoic rock assemblage for future excavations. Recommendations for facility instrumentation and monitoring were included in the preliminary design of the DUSEL project design and include; single and multiple point extensometers, tape extensometers and convergence measurements (pins), load cells and pressure cells, smart cables, inclinometers/Tiltmeters, Piezometers, thermistors, seismographs and accelerometers, scanners (laser

  17. Comprehensive facilities plan

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-09-01

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

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

    International Nuclear Information System (INIS)

    Auerbach, J.M.; Montgomery, D.S.; McCauley, E.W.; Stone, G.F.

    1986-01-01

    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

  19. COGEMA's UMF [Uranium Management Facility

    International Nuclear Information System (INIS)

    Lamorlette, G.; Bertrand, J.P.

    1988-01-01

    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

  20. The construction of a facility for 14 Mev neutron activation analysis of oxygen in aluminium

    International Nuclear Information System (INIS)

    Bjoernstad, T.; Alstad, J.

    1984-02-01

    The article describes the construction and performance of a facility for 14 MeV neutron activation analysis, mainly for oxygen in aluminium, at the University of Oslo. It consists of a sealed tube neutron generator, a biaxial rotation system for samples in irradiation position, a mechanism for automatic separation of sample and container, and appropriate detectors and counting electronics. Especially considered are the procedures for sample preparation and packing, standardization, optimization of the energy range for integration and optimization of the irradiation, decay and counting times. The applicability of the facility is exemplified by analytical results from comparative investigations in different laboratories using different methods. (Auth.)

  1. Design basis threat analysis and implementation of the physical protection system at Nuclear Facility of BATAN Yogyakarta

    International Nuclear Information System (INIS)

    Syarip

    2005-01-01

    An analysis to determine the design basis threat (DBT) and its follow-up through the implementation of physical protection system at the nuclear facility of BATAN Yogyakarta has been done. Methodology used for the analysis is based on the IAEA guidance for the development and maintenance of a DBT. Based on the analysis results, it can be concluded that the threat motivation is influenced by political situation (related to the government policy), criminal, sabotage and theft. The characteristics of threats are: not so well organized, terror, theft of materials information, involving insider (collusion), and intimidation to workers. Potential threat could from guests/students who take a practical job or laboratory exercise. Therefore, it is necessary to be anticipated the possibility and its impact of turmoil/demonstrators such as destruction of: lighting, road, fence, sabotage on the electric and communication lines, surrounding the Yogyakarta nuclear facility

  2. Advanced Microanalysis Facility

    Data.gov (United States)

    Federal Laboratory Consortium — The Advanced Microanalysis Facility fully integrates capabilities for chemical and structural analysis of electronic materials and devices for the U.S. Army and DoD....

  3. Radioactive wastes. Safety of storage facilities

    International Nuclear Information System (INIS)

    Devillers, Ch.

    2001-01-01

    A radioactive waste storage facility is designed in a way that ensures the isolation of wastes with respect to the biosphere. This function comprises the damping of the gamma and neutron radiations from the wastes, and the confinement of the radionuclides content of the wastes. The safety approach is based on two time scales: the safety of the insulation system during the main phase of radioactive decay, and the assessment of the radiological risks following this phase. The safety of a surface storage facility is based on a three-barrier concept (container, storage structures, site). The confidence in the safety of the facility is based on the quality assurance of the barriers and on their surveillance and maintenance. The safety of a deep repository will be based on the site quality, on the design and construction of structures and on the quality of the safety demonstration. This article deals with the safety approach and principles of storage facilities: 1 - recall of the different types of storage facilities; 2 - different phases of the life of a storage facility and regulatory steps; 3 - safety and radiation protection goals (time scales, radiation protection goals); 4 - safety approach and principles of storage facilities: safety of the isolation system (confinement system, safety analysis, scenarios, radiological consequences, safety principles), assessment of the radiation risks after the main phase of decay; 5 - safety of surface storage facilities: safety analysis of the confinement system of the Aube plant (barriers, scenarios, modeling, efficiency), evaluation of radiological risks after the main phase of decay; experience feedback of the Manche plant; variants of surface storage facilities in France and abroad (very low activity wastes, mine wastes, short living wastes with low and average activity); 6 - safety of deep geological disposal facilities: legal framework of the French research; international context; safety analysis of the confinement system

  4. Thermal-Hydraulic Analysis of SWAMUP Facility Using ATHLET-SC Code

    Energy Technology Data Exchange (ETDEWEB)

    Wang, Zidi; Cao, Zhen; Liu, Xiaojing, E-mail: xiaojingliu@sjtu.edu.cn [School of Nuclear Science and Engineering, Shanghai Jiao Tong University, Shanghai (China)

    2015-03-16

    During the loss of coolant accident (LOCA) of supercritical water-cooled reactor (SCWR), the pressure in the reactor system will undergo a rapid decrease from the supercritical pressure to the subcritical condition. This process is called trans-critical transients, which is of crucial importance for the LOCA analysis of SCWR. In order to simulate the trans-critical transient, a number of system codes for SCWR have been developed up to date. However, the validation work for the trans-critical models in these codes is still missing. The test facility Supercritical WAter MUltiPurpose loop (SWAMUP) with 2 × 2 rod bundle in Shanghai Jiao Tong University (SJTU) will be applied to provide test data for code validation. Some pre-test calculations are important and necessary to show the feasibility of the experiment. In this study, trans-critical transient analysis is performed for the SWAMUP facility with the system code ATHLET-SC, which is modified in SJTU, for supercritical water system. This paper presents the system behavior, e.g., system pressure, coolant mass flow, cladding temperature during the depressurization. The effects of some important parameters such as heating power, depressurization rate on the system characteristics are also investigated in this paper. Additionally, some sensitivities study of the code models, e.g., heat transfer coefficient, critical heat flux correlation are analyzed and discussed. The results indicate that the revised system code ATHLET-SC is capable of simulating thermal-hydraulic behavior during the trans-critical transient. According to the results, the cladding temperature during the transient is kept at a low value. However, the pressure difference of the heat exchanger after depressurization could reach 6 MPa, which should be considered in the experiment.

  5. New markers to identify the provenance of lapis lazuli: trace elements in pyrite by means of micro-PIXE

    Energy Technology Data Exchange (ETDEWEB)

    Re, A. [Istituto Nazionale di Fisica Nucleare (INFN), Sezione di Torino, Torino (Italy); Angelici, D. [Istituto Nazionale di Fisica Nucleare (INFN), Sezione di Torino, Torino (Italy); Universita di Torino, Dipartimento di Fisica, Torino (Italy); Universita di Torino, Dipartimento di Scienze della Terra, Torino (Italy); Lo Giudice, A. [Istituto Nazionale di Fisica Nucleare (INFN), Sezione di Torino, Torino (Italy); Universita di Torino, Dipartimento di Fisica, Torino (Italy); Maupas, E. [Universita di Torino, Dipartimento di Fisica, Torino (Italy); Giuntini, L.; Calusi, S.; Massi, M.; Mando, P.A. [Universita di Firenze, Dipartimento di Fisica, Sesto Fiorentino, Firenze (Italy); Istituto Nazionale di Fisica Nucleare (INFN), Sezione di Firenze, Sesto Fiorentino, Firenze (Italy); Gelli, N. [Istituto Nazionale di Fisica Nucleare (INFN), Sezione di Firenze, Sesto Fiorentino, Firenze (Italy); Borghi, A. [Universita di Torino, Dipartimento di Scienze della Terra, Torino (Italy); Gallo, L.M. [Museo Regionale di Scienze Naturali, Torino (Italy); Pratesi, G. [Universita di Firenze, Dipartimento di Scienze della Terra, Firenze (Italy); Museo di Storia Naturale, Firenze (Italy)

    2013-04-15

    Lapis lazuli has been used for glyptics and carving since the fifth millennium BC to produce jewels, amulets, seals, inlays, etc; the identification of the origin of the stone used for carving artworks may be valuable for reconstructing old trade routes. Since ancient lapis lazuli art objects are precious, only non-destructive techniques can be used to identify their provenance, and ion beam analysis (IBA) techniques allow us to characterise this stone in a fully non-invasive way. In addition, by using an ion microprobe, we have been able to focus the analysis on single crystals, as their typical dimensions may range from a few microns to hundreds of microns. Provenance markers, identified in previous IBA studies and already presented elsewhere, were based on the presence/absence of mineral phases, on the presence/quantity of trace elements inside a phase and on characteristic features of the luminescence spectra. In this work, a systematic study on pyrite crystals, a common accessory mineral in lapis lazuli, was carried out, following a multi-technique approach: optical microscopy and SEM-EDX to select crystals for successive trace element micro-PIXE measurements at two Italian facilities, the INFN Laboratori Nazionali di Legnaro and the INFN LABEC laboratory in Firenze. The results of this work allowed us to obtain new markers for lapis lazuli provenance identification. (orig.)

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

    International Nuclear Information System (INIS)

    Dionne, B.J.; Morris, S. III; Baum, J.W.

    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 Achievableclose quotes (ALARA) analysis for use at other DOE nuclear facilities as an example of a risk-based decision technique

  7. Ballistic Test Facility

    Data.gov (United States)

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

  8. Design of the PISCES-Upgrade facility

    International Nuclear Information System (INIS)

    Waganer, L.M.; Doerner, R.

    1994-01-01

    The PISCES-Upgrade facility is currently in the design and fabrication phases for the University of California. McDonnell Douglas is under contract to develop this experimental facility in order to enhance the capability for investigation of fusion materials erosion-redeposition and edge plasma behaviors. The advance in facility capability requires innovative design approaches and application of sophisticated analysis techniques

  9. Nonreactor nuclear facilities: standards and criteria guide

    International Nuclear Information System (INIS)

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

    1981-09-01

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

  10. Verification of fire and explosion accident analysis codes (facility design and preliminary results)

    International Nuclear Information System (INIS)

    Gregory, W.S.; Nichols, B.D.; Talbott, D.V.; Smith, P.R.; Fenton, D.L.

    1985-01-01

    For several years, the US Nuclear Regulatory Commission has sponsored the development of methods for improving capabilities to analyze the effects of postulated accidents in nuclear facilities; the accidents of interest are those that could occur during nuclear materials handling. At the Los Alamos National Laboratory, this program has resulted in three computer codes: FIRAC, EXPAC, and TORAC. These codes are designed to predict the effects of fires, explosions, and tornadoes in nuclear facilities. Particular emphasis is placed on the movement of airborne radioactive material through the gaseous effluent treatment system of a nuclear installation. The design, construction, and calibration of an experimental ventilation system to verify the fire and explosion accident analysis codes are described. The facility features a large industrial heater and several aerosol smoke generators that are used to simulate fires. Both injected thermal energy and aerosol mass can be controlled using this equipment. Explosions are simulated with H 2 /O 2 balloons and small explosive charges. Experimental measurements of temperature, energy, aerosol release rates, smoke concentration, and mass accumulation on HEPA filters can be made. Volumetric flow rate and differential pressures also are monitored. The initial experiments involve varying parameters such as thermal and aerosol rate and ventilation flow rate. FIRAC prediction results are presented. 10 figs

  11. Risks, costs and benefits analysis for exhumation of buried radioactive materials at a nuclear fuel fabrication facility

    International Nuclear Information System (INIS)

    Kirk, J.S.; Moore, R.A.; Huston, T.E.

    1996-01-01

    A Risks, Costs and Benefits analysis provides a tool for selecting a cost-effective remedial action alternative. This analysis can help avoid transferring risks to other populations and can objectively measure the benefits of a specific remedial action project. This paper describes the methods and results of a Risks, Costs and Benefits analysis performed at a nuclear fuel fabrication facility. The analysis examined exhuming and transporting radioactive waste to an offsite disposal facility. Risks evaluated for the remedial action project were divided into two categories: risks posed to the worker and risks posed to public health. Risks to workers included exposure to radioactive contaminants during excavation and packaging of waste materials and the use of heavy machinery. Potential public health risks included exposure to radioactive materials during transport from the exhumation site to the disposal facility. Methods included use of site-specific and published data, and existing computer models. Occupational risks were quantified using data from similar onsite remedial action projects. Computer modeling was used to evaluate public health risks from transporting radioactive materials; the consequences or probability of traffic accidents; and radiation exposure to potential inhabitants occupying the site considering various land use scenarios. A costs analysis was based on data obtained from similar onsite remedial action projects. Scenarios used to identify benefits resulting from the remedial action project included (1) an evaluation of reduction in risks to human health; (2) cost reductions associated with the unrestricted release of the property; and (3) benefits identified by evaluating regulatory mandates applicable to decommissioning. This paper will provide an overview of the methods used and a discussion of the results of a Risks, Costs and Benefits analysis for a site-specific remedial action scenario

  12. IBA techniques: Examples of useful combinations for the characterisation of cultural heritage materials

    Science.gov (United States)

    Beck, L.; Pichon, L.; Moignard, B.; Guillou, T.; Walter, P.

    2011-12-01

    For many years, ion beam analysis techniques have successfully been used to the study of cultural heritage objects. The chemical composition of work art is usually determined by PIXE, but in many cases, RBS and/or PIGE can provide useful complementary information. RBS gives information about the depth distribution and concentration in light elements, such as carbon and oxygen. In the past years, the experimental facilities at the AGLAE (Accélérateur Grand Louvre d'Analyse Élémentaire) accelerator has been progressively developed in order to apply simultaneously PIXE, PIGE and RBS under optimal conditions using an external beam. This combination is now routinely used for point analyses or mappings. In this contribution, we present several examples of applications: manufacturing technology of lustre-decorated ceramics and silver plating, control of altered or restored surfaces, and quantification of organic phase in painting and bone. The final conclusion is that the association of PIXE with RBS is very attractive for the investigation of cultural heritage objects, in particular of materials containing both mineral and organic components or possessing a multilayered structure. The first results of the production of monochromatic X-rays for radiography purposes by PIXE are also presented.

  13. IBA techniques: Examples of useful combinations for the characterisation of cultural heritage materials

    International Nuclear Information System (INIS)

    Beck, L.; Pichon, L.; Moignard, B.; Guillou, T.; Walter, P.

    2011-01-01

    For many years, ion beam analysis techniques have successfully been used to the study of cultural heritage objects. The chemical composition of work art is usually determined by PIXE, but in many cases, RBS and/or PIGE can provide useful complementary information. RBS gives information about the depth distribution and concentration in light elements, such as carbon and oxygen. In the past years, the experimental facilities at the AGLAE (Accélérateur Grand Louvre d’Analyse Élémentaire) accelerator has been progressively developed in order to apply simultaneously PIXE, PIGE and RBS under optimal conditions using an external beam. This combination is now routinely used for point analyses or mappings. In this contribution, we present several examples of applications: manufacturing technology of lustre-decorated ceramics and silver plating, control of altered or restored surfaces, and quantification of organic phase in painting and bone. The final conclusion is that the association of PIXE with RBS is very attractive for the investigation of cultural heritage objects, in particular of materials containing both mineral and organic components or possessing a multilayered structure. The first results of the production of monochromatic X-rays for radiography purposes by PIXE are also presented.

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

    International Nuclear Information System (INIS)

    Krstulovich, S.F.

    1987-01-01

    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

  15. Criticality safety considerations. Integral Monitored Retrievable Storage (MRS) Facility

    International Nuclear Information System (INIS)

    1986-09-01

    This report summarizes the criticality analysis performed to address criticality safety concerns and to support facility design during the conceptual design phase of the Monitored Retrievable Storage (MRS) Facility. The report addresses the criticality safety concerns, the design features of the facility relative to criticality, and the results of the analysis of both normal operating and hypothetical off-normal conditions. Key references are provided (Appendix C) if additional information is desired by the reader. The MRS Facility design was developed and the related analysis was performed in accordance with the MRS Facility Functional Design Criteria and the Basis for Design. The detailed description and calculations are documented in the Integral MRS Facility Conceptual Design Report. In addition to the summary portion of this report, explanatary notes for various terms, calculation methodology, and design parameters are presented in Appendix A. Appendix B provides a brief glossary of technical terms

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

    International Nuclear Information System (INIS)

    Pili-Vincens, C.

    1997-01-01

    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

  17. Analysis of general specifications for nuclear facilities environmental monitoring vehicles

    International Nuclear Information System (INIS)

    Xu Xiaowei

    2014-01-01

    At present, with the nuclear energy more increasingly extensive application, the continuous stable radiation monitoring has become the focus of the public attention. The main purpose of the environmental monitoring vehicle for the continuous monitoring of the environmental radiation dose rate and the radionuclides concentration in the medium around nuclear facilities is that the environmental radiation level and the radioactive nuclides activity in the environment medium are measured. The radioactive pollution levels, the scope contaminated and the trends of the pollution accumulation are found out. The change trends for the pollution are observed and the monitoring results are explained. The domestic demand of the environmental monitoring for the nuclear facilities is shown in this report. The changes and demands of the routine environmental monitoring and the nuclear emergency monitoring are researched. The revision opinions for EJ/T 981-1995 General specifications for nuclear facilities environmental monitoring vehicles are put forward. The purpose is to regulate domestic environmental monitoring vehicle technical criterion. The criterion makes it better able to adapt and serve the environmental monitoring for nuclear facilities. The technical guarantee is provided for the environmental monitoring of the nuclear facilities. (authors)

  18. Quantifying the relative irreplaceability of important bird and biodiversity areas.

    Science.gov (United States)

    Di Marco, Moreno; Brooks, Thomas; Cuttelod, Annabelle; Fishpool, Lincoln D C; Rondinini, Carlo; Smith, Robert J; Bennun, Leon; Butchart, Stuart H M; Ferrier, Simon; Foppen, Ruud P B; Joppa, Lucas; Juffe-Bignoli, Diego; Knight, Andrew T; Lamoreux, John F; Langhammer, Penny F; May, Ian; Possingham, Hugh P; Visconti, Piero; Watson, James E M; Woodley, Stephen

    2016-04-01

    World governments have committed to increase the global protected areas coverage by 2020, but the effectiveness of this commitment for protecting biodiversity depends on where new protected areas are located. Threshold- and complementarity-based approaches have been independently used to identify important sites for biodiversity. We brought together these approaches by performing a complementarity-based analysis of irreplaceability in important bird and biodiversity areas (IBAs), which are sites identified using a threshold-based approach. We determined whether irreplaceability values are higher inside than outside IBAs and whether any observed difference depends on known characteristics of the IBAs. We focused on 3 regions with comprehensive IBA inventories and bird distribution atlases: Australia, southern Africa, and Europe. Irreplaceability values were significantly higher inside than outside IBAs, although differences were much smaller in Europe than elsewhere. Higher irreplaceability values in IBAs were associated with the presence and number of restricted-range species; number of criteria under which the site was identified; and mean geographic range size of the species for which the site was identified (trigger species). In addition, IBAs were characterized by higher irreplaceability values when using proportional species representation targets, rather than fixed targets. There were broadly comparable results when measuring irreplaceability for trigger species and when considering all bird species, which indicates a good surrogacy effect of the former. Recently, the International Union for Conservation of Nature has convened a consultation to consolidate global standards for the identification of key biodiversity areas (KBAs), building from existing approaches such as IBAs. Our results informed this consultation, and in particular a proposed irreplaceability criterion that will allow the new KBA standard to draw on the strengths of both threshold- and

  19. Challenges for proteomics core facilities.

    Science.gov (United States)

    Lilley, Kathryn S; Deery, Michael J; Gatto, Laurent

    2011-03-01

    Many analytical techniques have been executed by core facilities established within academic, pharmaceutical and other industrial institutions. The centralization of such facilities ensures a level of expertise and hardware which often cannot be supported by individual laboratories. The establishment of a core facility thus makes the technology available for multiple researchers in the same institution. Often, the services within the core facility are also opened out to researchers from other institutions, frequently with a fee being levied for the service provided. In the 1990s, with the onset of the age of genomics, there was an abundance of DNA analysis facilities, many of which have since disappeared from institutions and are now available through commercial sources. Ten years on, as proteomics was beginning to be utilized by many researchers, this technology found itself an ideal candidate for being placed within a core facility. We discuss what in our view are the daily challenges of proteomics core facilities. We also examine the potential unmet needs of the proteomics core facility that may also be applicable to proteomics laboratories which do not function as core facilities. Copyright © 2011 WILEY-VCH Verlag GmbH & Co. KGaA, Weinheim.

  20. Uncertainty and sensitivity analysis on probabilistic safety assessment of an experimental facility

    International Nuclear Information System (INIS)

    Burgazzi, L.

    2000-01-01

    The aim of this work is to perform an uncertainty and sensitivity analysis on the probabilistic safety assessment of the International Fusion Materials Irradiation Facility (IFMIF), in order to assess the effect on the final risk values of the uncertainties associated with the generic data used for the initiating events and component reliability and to identify the key quantities contributing to this uncertainty. The analysis is conducted on the expected frequency calculated for the accident sequences, defined through the event tree (ET) modeling. This is in order to increment credit to the ET model quantification, to calculate frequency distributions for the occurrence of events and, consequently, to assess if sequences have been correctly selected on the probability standpoint and finally to verify the fulfillment of the safety conditions. Uncertainty and sensitivity analysis are performed using respectively Monte Carlo sampling and an importance parameter technique. (author)

  1. Thermal and chemical analysis of carbon dioxide reforming of methane using the out-of-pile test facility

    International Nuclear Information System (INIS)

    Huang Ziyong; Ohashi, Hirofumi; Inagaki, Yoshiyuki

    2000-03-01

    In the Japan Atomic Energy Research Institute, a hydrogen production system is being designed to produce hydrogen by means of steam reforming of natural gas (its main composition is methane(CH 4 )) using nuclear heat (10 MW, 1178 K) supplied by the High Temperature Engineering Test Reactor (HTTR). Prior to coupling of the steam reforming system with the HTTR, an out-of-pile demonstration test was planned to confirm safety, controllability and performance of the steam reforming system under simulated operational conditions of the prototype. The out-of-pile test facility simulates key components downstream to an intermediate heat exchanger of the HTTR hydrogen production system on a scale of 1 : 30 and has a hydrogen production capacity of 110 Nm 3 /h using an electric heater as a reactor substitute. The test facility is presently under construction. Reforming of natural gas with carbon dioxide CO 2 (CO 2 reforming) using the out-of-pile test facility is also being considered. In recent years, catalytic reforming of natural gas with CO 2 to synthesis gas (CO and H 2 ) has been proposed as one of the most promising technologies for utilization of those two greenhouse gases. Numerical analysis on heat and mass balance has practical significance in CO 2 reforming when the steam reforming process is adopted in the out-of-pile test. Numerical analysis of CO 2 reforming and reforming of natural gas with CO 2 and steam (CO 2 +H 2 O reforming) have been carried out using the mathematical model. Results such as the methane conversion rate, product gas composition, and the components temperature distribution considering the effects of helium gas temperature, reforming pressure, molar ratio of process gases and so on have been obtained in the numerical analysis. Heat and mass balance of the out-of-pile test facility considering chemical reactions are evaluated well. The methane conversation rates are about 0.36 and 0.35 which correspond to the equilibrium at 1085 and 1100 K for

  2. Thermal and chemical analysis of carbon dioxide reforming of methane using the out-of-pile test facility

    Energy Technology Data Exchange (ETDEWEB)

    Huang Ziyong [Institute of Nuclear Energy Technology, Tsinghua University (China); Ohashi, Hirofumi; Inagaki, Yoshiyuki [Department of Advanced Nuclear Heat Technology, Oarai Research Establishment, Japan Atomic Energy Research Institute, Oarai, Ibaraki (Japan)

    2000-03-01

    In the Japan Atomic Energy Research Institute, a hydrogen production system is being designed to produce hydrogen by means of steam reforming of natural gas (its main composition is methane(CH{sub 4})) using nuclear heat (10 MW, 1178 K) supplied by the High Temperature Engineering Test Reactor (HTTR). Prior to coupling of the steam reforming system with the HTTR, an out-of-pile demonstration test was planned to confirm safety, controllability and performance of the steam reforming system under simulated operational conditions of the prototype. The out-of-pile test facility simulates key components downstream to an intermediate heat exchanger of the HTTR hydrogen production system on a scale of 1 : 30 and has a hydrogen production capacity of 110 Nm{sup 3}/h using an electric heater as a reactor substitute. The test facility is presently under construction. Reforming of natural gas with carbon dioxide CO{sub 2} (CO{sub 2} reforming) using the out-of-pile test facility is also being considered. In recent years, catalytic reforming of natural gas with CO{sub 2} to synthesis gas (CO and H{sub 2}) has been proposed as one of the most promising technologies for utilization of those two greenhouse gases. Numerical analysis on heat and mass balance has practical significance in CO{sub 2} reforming when the steam reforming process is adopted in the out-of-pile test. Numerical analysis of CO{sub 2} reforming and reforming of natural gas with CO{sub 2} and steam (CO{sub 2}+H{sub 2}O reforming) have been carried out using the mathematical model. Results such as the methane conversion rate, product gas composition, and the components temperature distribution considering the effects of helium gas temperature, reforming pressure, molar ratio of process gases and so on have been obtained in the numerical analysis. Heat and mass balance of the out-of-pile test facility considering chemical reactions are evaluated well. The methane conversation rates are about 0.36 and 0.35 which

  3. An ImageJ plugin for ion beam imaging and data processing at AIFIRA facility

    Energy Technology Data Exchange (ETDEWEB)

    Devès, G.; Daudin, L. [Univ. Bordeaux, F-33170 Gradignan (France); CNRS, IN2P3, CENBG, UMR 5797, F-33170 Gradignan (France); Bessy, A.; Buga, F.; Ghanty, J.; Naar, A.; Sommar, V. [Univ. Bordeaux, F-33170 Gradignan (France); Michelet, C.; Seznec, H.; Barberet, P. [Univ. Bordeaux, F-33170 Gradignan (France); CNRS, IN2P3, CENBG, UMR 5797, F-33170 Gradignan (France)

    2015-04-01

    Quantification and imaging of chemical elements at the cellular level requires the use of a combination of techniques such as micro-PIXE, micro-RBS, STIM, secondary electron imaging associated with optical and fluorescence microscopy techniques employed prior to irradiation. Such a numerous set of methods generates an important amount of data per experiment. Typically for each acquisition the following data has to be processed: chemical map for each element present with a concentration above the detection limit, density and backscattered maps, mean and local spectra corresponding to relevant region of interest such as whole cell, intracellular compartment, or nanoparticles. These operations are time consuming, repetitive and as such could be source of errors in data manipulation. In order to optimize data processing, we have developed a new tool for batch data processing and imaging. This tool has been developed as a plugin for ImageJ, a versatile software for image processing that is suitable for the treatment of basic IBA data operations. Because ImageJ is written in Java, the plugin can be used under Linux, Mas OS X and Windows in both 32-bits and 64-bits modes, which may interest developers working on open-access ion beam facilities like AIFIRA. The main features of this plugin are presented here: listfile processing, spectroscopic imaging, local information extraction, quantitative density maps and database management using OMERO.

  4. Analytical methods used at model facility

    International Nuclear Information System (INIS)

    Wing, N.S.

    1984-01-01

    A description of analytical methods used at the model LEU Fuel Fabrication Facility is presented. The methods include gravimetric uranium analysis, isotopic analysis, fluorimetric analysis, and emission spectroscopy

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

    International Nuclear Information System (INIS)

    Dionne, B.J.; Morris, S.C. III; Baum, J.W.

    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 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

  6. On the origin of high spin states (J > Jsub(max) of IBA=10) and their enhanced E1 decay mode in 218Ra

    International Nuclear Information System (INIS)

    Gai, M.

    1984-01-01

    The high spin states of 218 Ra exhibit a band of alternating parity states with enhanced E1 decay mode (B(E1) >=10 -2 W.u.). Various theoretical models are discussed, such as the octupole model, f and g boson model, second order E1 operator in IBA1 model, and the cluster model. The enhanced E1 deexcitation favors the cluster model. The low spin negative parity states lie on a J(J+1) trajectory contrary to the assumed vibrational character of the negative parity states in 218 Ra. A change in the character of states above the 11 - state is observed via a change in the moment of inertia and a decrease in the B(E1)/B(E2) branch ratios. Two quasi-particle 11 - states systematically occurring in the Ra-isotopes may be responsible for this change. The well known effect of loss of collectivity arising from two quasi-particle states, as observed in the hindrance of B(E2), is suggested to more dramatically hinder the B(E1) and lead to a reduction in the branch ratio B(E1)/B(E2). This observation suggests that the E1 enhancement is of collective character

  7. New-doses limits introduction analysis for the design and operation of teletherapy facilities established by IAEA

    International Nuclear Information System (INIS)

    Castaneda M, A.; Jimenez C, I.; Ramirez M, J.C.; Sanchez V, H.F.

    1996-01-01

    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

  8. Safety analysis of the Los Alamos critical experiments facility

    International Nuclear Information System (INIS)

    Paxton, H.C.

    1975-10-01

    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 10 19 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

  9. Analysis of federal and state policies and environmental issues for bioethanol production facilities.

    Science.gov (United States)

    McGee, Chandra; Chan Hilton, Amy B

    2011-03-01

    The purpose of this work was to investigate incentives and barriers to fuel ethanol production from biomass in the U.S. during the past decade (2000-2010). In particular, we examine the results of policies and economic conditions during this period by way of cellulosic ethanol activity in four selected states with the potential to produce different types of feedstocks (i.e., sugar, starch, and cellulosic crops) for ethanol production (Florida, California, Hawaii, and Iowa). Two of the four states, Iowa and California, currently have commercial ethanol production facilities in operation using corn feedstocks. While several companies have proposed commercial scale facilities in Florida and Hawaii, none are operating to date. Federal and state policies and incentives, potential for feedstock production and conversion to ethanol and associated potential environmental impacts, and environmental regulatory conditions among the states were investigated. Additionally, an analysis of proposed and operational ethanol production facilities provided evidence that a combination of these policies and incentives along with the ability to address environmental issues and regulatory environment and positive economic conditions all impact ethanol production. The 2000-2010 decade saw the rise of the promise of cellulosic ethanol. Federal and state policies were enacted to increase ethanol production. Since the initial push for development, expansion of cellulosic ethanol production has not happened as quickly as predicted. Government and private funding supported the development of ethanol production facilities, which peaked and then declined by the end of the decade. Although there are technical issues that remain to be solved to more efficiently convert cellulosic material to ethanol while reducing environmental impacts, the largest barriers to increasing ethanol production appear to be related to government policies, economics, and logistical issues. The numerous federal and state

  10. Fire hazards analysis for W-413, West Area Tank Farm Storage and Staging Facility

    International Nuclear Information System (INIS)

    Huckfeldt, R.A.; Lott, D.T.

    1994-01-01

    In accordance with DOE Order 5480.7A, a Fire Hazards Analysis must be performed for all new facilities. The purpose of the analysis is to comprehensively assess the risk from fire within individual fire areas in relation to proposed fire protection so as to ascertain whether the fire protection objectives of the Order are met. The Order acknowledges a graded approach commensurate with the hazards involved. Tank Farms Operations must sore/stage material and equipment such as pipes, fittings, conduit, instrumentation and others related items until work packages are ready to work. Consumable materials, such as nut, bolts and welding rod, are also requires to be stored for routine and emergency work. Connex boxes and open storage is currently used for much of the storage because of the limited space at and 272WA. Safety issues based on poor housekeeping and material deteriorating due to weather damage has resulted from this inadequate storage space. It has been determined that a storage building in close proximity to the Tank Farm work force would be cost effective. This facility is classified as a safety class 4 building

  11. Analysis of obsydians and films of silicon carbide by RBS technique

    International Nuclear Information System (INIS)

    Franco S, F.

    1998-01-01

    Motivated by archaeological interest this work is presented, which consist in the characterization of obsydian samples from different mineral sites in Mexico and films of silicon carbide, undertaken by an Ion Beam Analysis: RBS (Rutherford Back Scattering). As part of an intensive investigation of obsydian in Mesoamerica by anthropologists from Mexico National Institute of Anthropology and History, 818 samples were collected from different volcanic sources in Central Mexico for the purpose of establishing a data bank of element concentrations of each source. Part of this collection was analyzed by Neutron activation analysis and most of the important elements concentrations reported. In the first part of this work, the non-destructive IBA technique, RBS are used to analyze obsydian samples. The last part is an analysis of thin films of silicon carbide as a part of a research program of the Universidad Nacional Autonoma de Mexico and ININ. The application of this technique were carried out at the IF-UNAM, and the analysis was performed at laboratories of the ININ Nuclear Centre facilities. The samples considered in this work were mounted on a sample holder designed for the purpose of exposing each sample to the alpha particles beam. This RBS analysis was carried out with an ET Tandem accelerator at the IF UNAM. The spectrometry was carried out with employing a Si(Li) detector set at 15 degrees in relation to the target normal. The mean projectile energy was 2.00 MeV, and the beam profile was about 4 mm in diameter. As results were founded elemental concentrations of a set of samples from ten different sources: Altotonga (Veracruz), Penjamo (Guanajuato), Otumba (Mexico), Zinapecuaro (MIchoacan), Ucareo (Michoacan), Tres Cabezas (Puebla), Sierra Navajas (Hidalgo), Zaragoza (Puebla), Guadalupe Victoria (Puebla) and Oyameles (Puebla). The mean values are accompanied by errors expressed as one standard devistion of the mean for each element

  12. The association between the physical environment and the well-being of older people in residential care facilities: A multilevel analysis.

    Science.gov (United States)

    Nordin, Susanna; McKee, Kevin; Wijk, Helle; Elf, Marie

    2017-12-01

    To investigate the associations between the quality of the physical environment and the psychological and social well-being of older people living in residential care facilities. Many older people in care facilities have cognitive and physical frailties and are at risk of experiencing low levels of well-being. High-quality physical environments can support older people as frailty increases and promote their well-being. Although the importance of the physical environment for residents' well-being is recognized, more research is needed. A cross-sectional survey of 20 care facilities from each of which 10 residents were sampled. As the individual resident data were nested in the facilities, a multilevel analysis was conducted. Data were collected during 2013 and 2014. The care facilities were purposely sampled to ensure a high level of variation in their physical characteristics. Residents' demographic and health data were collected via medical records and interviews. Residents' well-being and perceived quality of care were assessed via questionnaires and interviews. Environmental quality was assessed with a structured observational instrument. Multilevel analysis indicated that cognitive support in the physical environment was associated with residents' social well-being, after controlling for independence and perceived care quality. However, no significant association was found between the physical environment and residents' psychological well-being. Our study demonstrates the role of the physical environment for enhancing the social well-being of frail older people. Professionals and practitioners involved in the design of care facilities have a responsibility to ensure that such facilities meet high-quality specifications. © 2017 The Authors. Journal of Advanced Nursing Published by John Wiley & Sons Ltd.

  13. Seismic evaluation of critical facilities at the Lawrence Livermore Laboratory

    International Nuclear Information System (INIS)

    Murray, R.C.; Tokarz, F.J.

    1976-01-01

    The performance of critical facilities at the Lawrence Livermore Laboratory (LLL) are being evaluated for severe earthquake loading. Facilities at Livermore, Site-300 and the Nevada Test Site are included in this study. These facilities are identified, the seismic criteria used for the analysis are indicated, the various methods used for structural analysis are discussed and a summary of the results of facilities analyzed to date are presented

  14. Composite Structures Manufacturing Facility

    Data.gov (United States)

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

  15. 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.

  16. Source term analysis for a RCRA mixed waste disposal facility

    International Nuclear Information System (INIS)

    Jordan, D.L.; Blandford, T.N.; MacKinnon, R.J.

    1996-01-01

    A Monte Carlo transport scheme was used to estimate the source strength resulting from potential releases from a mixed waste disposal facility. Infiltration rates were estimated using the HELP code, and transport through the facility was modeled using the DUST code, linked to a Monte Carlo driver

  17. Distinct spatial distribution of microglia and macrophages following mesenchymal stem cell implantation in mouse brain.

    Science.gov (United States)

    Le Blon, Debbie; Hoornaert, Chloé; Daans, Jasmijn; Santermans, Eva; Hens, Niel; Goossens, Herman; Berneman, Zwi; Ponsaerts, Peter

    2014-09-01

    Although implantation of cellular material in the central nervous system (CNS) is a key direction in CNS regenerative medicine, this approach is currently limited by the occurrence of strong endogenous immune cell responses. In a model of mesenchymal stem cell (MSC) grafting in the CNS of immune-competent mice, we previously described that MSC grafts become highly surrounded and invaded by Iba1(+) myeloid cells (microglia and/or macrophages). Here, following grafting of blue fluorescent protein (BFP)-expressing MSC in the CNS of CX3CR1(+/-) and CX3CR1(-/-) mice, our results indicate: (1) that the observed inflammatory response is independent of the fractalkine signalling axis, and (2) that a significant spatial distribution of Iba1(+) inflammatory cells occurs, in which Iba1(+) CX3CR1(+) myeloid cells mainly surround the MSC graft and Iba1(+) CX3CR1(-) myeloid cells mainly invade the graft at 10 days post transplantation. Although Iba1(+) CX3CR1(+) myeloid cells are considered to be of resident microglial origin, Iba1(+) CX3CR1(-) myeloid cells are most likely of peripheral monocyte/macrophage origin. In order to confirm the latter, we performed MSC-BFP grafting experiments in the CNS of eGFP(+) bone marrow chimeric C57BL/6 mice. Analysis of MSC-BFP grafts in the CNS of these mice confirmed our observation that peripheral monocytes/macrophages invade the MSC graft and that resident microglia surround the MSC graft site. Furthermore, analysis of major histocompatibility complex class II (MHCII) expression revealed that mainly macrophages, but not microglia, express this M1 pro-inflammatory marker in the context of MSC grafting in the CNS. These results again highlight the complexity of cell implantation immunology in the CNS.

  18. In-facility transport code review

    International Nuclear Information System (INIS)

    Spore, J.W.; Boyack, B.E.; Bohl, W.R.

    1996-07-01

    The following computer codes were reviewed by the In-Facility Transport Working Group for application to the in-facility transport of radioactive aerosols, flammable gases, and/or toxic gases: (1) CONTAIN, (2) FIRAC, (3) GASFLOW, (4) KBERT, and (5) MELCOR. Based on the review criteria as described in this report and the versions of each code available at the time of the review, MELCOR is the best code for the analysis of in-facility transport when multidimensional effects are not significant. When multi-dimensional effects are significant, GASFLOW should be used

  19. A qualitative analysis of facilities maintenance - a school governance function in South Africa

    Directory of Open Access Journals (Sweden)

    M I Xaba

    2012-01-01

    Full Text Available I analysed school facilities maintenance, a school governance function in South Africa. Qualitative interviews were conducted with 13 principals and three deputy principals as coordinators of this function at their schools. The interviews were purposively and conveniently selected to gather data regarding school facilities maintenance and gain insight into the challenges this function presents to schools and their governing bodies. Findings indicate that schools generally do not have organisational structures for planned facilities maintenance, nor do they have policies on facilities maintenance. Evidence of facilities maintenance at schools mainly relates to concerns with facilities repairs, (mostly "as the need arises" and general campus cleanliness; mostly with emergency and corrective forms of maintenance as opposed to crucial preventive maintenance. Therefore, there is a need for interim facilities maintenance committees and, in the long term, a whole-school approach to facilities maintenance that makes facilities maintenance a strategic lever for school functionality.

  20. Protection of Facilities and Risk Assessment Application

    OpenAIRE

    Nađ, Ivan; Mihaljević, Branko; Mihalinčić, Martina

    2014-01-01

    The state of security on a specific area imposes the necessity for constant analysis of the existing system of protection of key state facilities, especially facilities of special significance for the defence. The facilities of special significance for the defence are an important part of the daily life, and enable smooth functioning of the economy and all other state activities. The protection of facilities of special significance for the defence is considered to be a system of obligatory me...

  1. An Application Of Facility Location Models With Hotspot Analysis For Optimal Location Of Abattoir Bio-Energy Plant In Anambra State Of Nigeria

    Directory of Open Access Journals (Sweden)

    E. C. Chukwuma

    2015-08-01

    Full Text Available Poor waste management strategy in abattoir in the the study area has needs a major attention considering it negative impacts on man land and water. Sitting of centralized biogas plant in a strategic location in the state would be the major means of combating the environmental challenges of increase in abattoir waste generation as result of population explosion in the state. This study investigates optimal location for sitting central abattoir waste treatment facility in Anambra State of Nigeria using facility location models with hotspot analysis in GIS environment. The result of the study shows that Using centre of gravity model the central location was estimated to be at Xc Yc 6.900953016 6.110157865. Based on inadequacy of the model hotspot analysis operation was done the hotspot analysis delineated clusters of abattoirs significantly higher in bio-wastes production than the overall study area. The hotspot analysis shows that the West regions of the study area has many abattoir that is classified as hotspot abattoirs. Using the hotspot abattoirs as proposed sites for load-distance model three abattoirs were identified as proposed sites- Obosi slaugher house Nkpor Private slaughter house and Oye-olise Ogbunike slaugher house. Their load distance values are 17250.40058 16299.24005 and 18210.14631 respectively. The optimal location for construction of central abattoir bio-waste treatment facility based on the application of these location facility models and hotspot analysis is Nkpor private slaughter house or its environs.

  2. Nonreactor nuclear facilities: Standards and criteria guide

    International Nuclear Information System (INIS)

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

    1986-09-01

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

  3. Transport of Indole-3-Butyric Acid and Indole-3-Acetic Acid in Arabidopsis Hypocotyls Using Stable Isotope Labeling1[C][W][OA

    Science.gov (United States)

    Liu, Xing; Barkawi, Lana; Gardner, Gary; Cohen, Jerry D.

    2012-01-01

    The polar transport of the natural auxins indole-3-butyric acid (IBA) and indole-3-acetic acid (IAA) has been described in Arabidopsis (Arabidopsis thaliana) hypocotyls using radioactive tracers. Because radioactive assays alone cannot distinguish IBA from its metabolites, the detected transport from applied [3H]IBA may have resulted from the transport of IBA metabolites, including IAA. To test this hypothesis, we used a mass spectrometry-based method to quantify the transport of IBA in Arabidopsis hypocotyls by following the movement of [13C1]IBA and the [13C1]IAA derived from [13C1]IBA. We also assayed [13C6]IAA transport in a parallel control experiment. We found that the amount of transported [13C1]IBA was dramatically lower than [13C6]IAA, and the IBA transport was not reduced by the auxin transport inhibitor N-1-naphthylphthalamic acid. Significant amounts of the applied [13C1]IBA were converted to [13C1]IAA during transport, but [13C1]IBA transport was independent of IBA-to-IAA conversion. We also found that most of the [13C1]IBA was converted to ester-linked [13C1]IBA at the apical end of hypocotyls, and ester-linked [13C1]IBA was also found in the basal end at a level higher than free [13C1]IBA. In contrast, most of the [13C6]IAA was converted to amide-linked [13C6]IAA at the apical end of hypocotyls, but very little conjugated [13C6]IAA was found in the basal end. Our results demonstrate that the polar transport of IBA is much lower than IAA in Arabidopsis hypocotyls, and the transport mechanism is distinct from IAA transport. These experiments also establish a method for quantifying the movement of small molecules in plants using stable isotope labeling. PMID:22323783

  4. An Analysis of the Charter School Facility Landscape in Albuquerque

    Science.gov (United States)

    Hesla, Kevin; Johnson, Jessica; Callahan, Kelly; Roskom, Greta; Ziebarth, Todd

    2017-01-01

    In 2016, the National Charter School Resource Center (NCSRC), the Colorado League of Charter Schools (the League), the New Mexico Coalition for Charter Schools (NMCCS), and the National Alliance for Public Charter Schools (the Alliance) collaborated to collect data and information about charter school facilities and facilities expenditures in the…

  5. An Analysis of the Charter School Facility Landscape in Delaware

    Science.gov (United States)

    Hesla, Kevin; Johnson, Jessica M.; Massett, Kendall; Ziebarth, Todd

    2018-01-01

    In the spring of 2016, the National Charter School Resource Center (NCSRC), the Colorado League of Charter Schools (the League), the Delaware Charter Schools Network (DCSN), and the National Alliance for Public Charter Schools (the Alliance) collaborated to collect data and information about charter school facilities and facilities expenditures in…

  6. Textiles Performance Testing Facilities

    Data.gov (United States)

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

  7. Imagery Data Base Facility

    Data.gov (United States)

    Federal Laboratory Consortium — The Imagery Data Base Facility supports AFRL and other government organizations by providing imagery interpretation and analysis to users for data selection, imagery...

  8. The utility of a geographic information system in facility/land use-related opportunities and constraints analysis for the Rocky Flats Environmental Technology Site

    International Nuclear Information System (INIS)

    Stewart, J.

    1994-01-01

    Facility/land use-related opportunities and constraints analysis, which is indispensable for the evaluation of potential future uses for a site, is essentially spatial in nature. Spatial analysis is best accomplished using a geographic information system (GIS), as a GIS allows the identification and reporting or mapping of complex relationships among multiple data layers such as geology, soils, vegetation, contamination, and facilities. GIS-based maps and reports are valuable tools for communicating facility/land use-related opportunities and constraints to decision makers. This paper defines the term open-quotes GIS,close quotes, provides an example of how a GIS could be used to conduct opportunities and constraints analysis at the Rocky Flats Environmental Technology Site (RFETS), and summarizes the benefits of using a GIS for this analysis. Because a GIS is often seen as a open-quotes black boxclose quotes shrouded in technical jargon, this paper attempts to describe the concepts and benefits of a GIS in language understandable to decision makers who are not GIS experts but who migth profit from the use of GIS products. The purpose of this paper is to alert DOE decision makers to a valuable source of facility/land use-related information that already exists at many sites and that should not be overlook during the analysis of future use options

  9. An Analysis of the Charter School Facility Landscape in Massachusetts

    Science.gov (United States)

    National Alliance for Public Charter Schools, 2013

    2013-01-01

    In the spring of 2012, the Massachusetts Charter Public School Association, the Colorado League of Charter Schools, and the National Alliance for Public Charter Schools worked to collect data that would reveal and accurately portray the adequacy of charter school facilities and the average spending for facilities out of charter schools' operating…

  10. Ion beam analysis and spectrometry techniques for Cultural Heritage studies

    International Nuclear Information System (INIS)

    Beck, L.

    2013-01-01

    The implementation of experimental techniques for the characterisation of Cultural heritage materials has to take into account some requirements. The complexity of these past materials requires the development of new techniques of examination and analysis, or the transfer of technologies developed for the study of advanced materials. In addition, due to precious aspect of artwork it is also necessary to use the non-destructive methods, respecting the integrity of objects. It is for this reason that the methods using radiations and/or particles play a important role in the scientific study of art history and archaeology since their discovery. X-ray and γ-ray spectrometry as well as ion beam analysis (IBA) are analytical tools at the service of Cultural heritage. This report mainly presents experimental developments for IBA: PIXE, RBS/EBS and NRA. These developments were applied to the study of archaeological composite materials: layered materials or mixtures composed of organic and non-organic phases. Three examples are shown: evolution of silvering techniques for the production of counterfeit coinage during the Roman Empire and in the 16. century, the characterization of composites or mixed mineral/organic compounds such as bone and paint. In these last two cases, the combination of techniques gave original results on the proportion of both phases: apatite/collagen in bone, pigment/binder in paintings. Another part of this report is then dedicated to the non-invasive/non-destructive characterization of prehistoric pigments, in situ, for rock art studies in caves and in the laboratory. Finally, the perspectives of this work are presented. (author) [fr

  11. A system approach to nuclear facility monitoring

    Energy Technology Data Exchange (ETDEWEB)

    Argo, P.E.; Doak, J.E.; Howse, J.W.

    1996-09-01

    Sensor technology for use in nuclear facility monitoring has reached and advanced stage of development. Research on where to place these sensors in a facility and how to combine their outputs in a meaningful fashion does not appear to be keeping pace. In this paper, we take a global view of the problem where sensor technology is viewed as only one piece of a large puzzle. Other pieces of this puzzle include the optimal location and type of sensors used in a specific facility, the rate at which sensors record information, and the risk associated with the materials/processes at a facility. If the data are analyzed off-site, how will they be transmitted? Is real-time analysis necessary? Are we monitoring only the facility itself, or might we also monitor the processing that occurs there? How are we going to combine the output from the various sensors to give us an accurate picture of the state of the facility? This paper will not try to answer all these questions, but rather it will attempt to stimulate thought in this area by formulating a systems approach to the problem demonstrated by a prototype system and a systems proposed for an actual facility. Our focus will be on the data analysis aspect of the problem.

  12. Safeguarding uranium enrichment facilities. Review and analysis of the status of safeguards technology for uranium enrichment facilities

    International Nuclear Information System (INIS)

    1977-09-01

    The objective of this paper is to examine critically the diversion potential at uranium enrichment facilities and to outline a basic safeguards strategy which counters all identified hazards as completely as possible yet with a minimum of non-essential redundancy. Where existing technology does not appear to be adequate for effective safeguards, the limitations are examined, and suggestions for further R and D effort are made. Parts of this report are generally applicable to all currently known enrichment processes, while other parts are specifically directed toward facilities based on the gas centrifuge process. It is hoped that additional sections discussing a safeguards strategy for gas diffusion facilities can be added later. It should be emphasized that this is a technical report, and does not reflect any legal positions. The safeguards strategy and subsequent inspection procedures are intended as guidelines, not as negotiating positions

  13. Effluent Treatment Facility tritium emissions monitoring

    International Nuclear Information System (INIS)

    Dunn, D.L.

    1991-01-01

    An Environmental Protection Agency (EPA) approved sampling and analysis protocol was developed and executed to verify atmospheric emissions compliance for the new Savannah River Site (SRS) F/H area Effluent Treatment Facility. Sampling equipment was fabricated, installed, and tested at stack monitoring points for filtrable particulate radionuclides, radioactive iodine, and tritium. The only detectable anthropogenic radionuclides released from Effluent Treatment Facility stacks during monitoring were iodine-129 and tritium oxide. This paper only examines the collection and analysis of tritium oxide

  14. PIXE/RBS as a tool to study cementitious materials: Application to the dynamic leaching of concrete

    International Nuclear Information System (INIS)

    Llorente, I.; Castellote, M.; Gonzalez-Arrabal, R.; Ynsa, M.D.; Munoz-Martin, A.; Viedma, P.G. de; Castillo, A.; Martinez, I.; Andrade, C.; Zuloaga, P.; Ordonez, M.

    2009-01-01

    The suitability of the application of Ion Beam Analysis (IBA) techniques such as Particle Induced X-ray Emission spectrometry (PIXE) and Rutherford Backscattering Spectrometry (RBS) to elemental depth profiling in concrete is analysed, studying hardened samples of concrete prior to and after a dynamic leaching test. A calibration of the data has been done by comparing the results obtained by IBA techniques with those obtained by Chemical and Thermogravimetric Analysis (TG/DTA). From PIXE and RBS data relevant information about the migration of minor elements, within the concrete matrix after leaching is obtained.

  15. PIXE/RBS as a tool to study cementitious materials: Application to the dynamic leaching of concrete

    Energy Technology Data Exchange (ETDEWEB)

    Llorente, I., E-mail: irene@cenim.csic.e [Centro Nacional de Investigaciones Metalurgicas (CENIM-CSIC), Avda Gregorio del Amo, 8, 28040 Madrid (Spain); Castellote, M. [Instituto de Ciencias de la Construccion ' Eduardo Torroja' (IETcc-CSIC), Serrano Galvache, 4, 28033 Madrid (Spain); Gonzalez-Arrabal, R. [Parque Cientifico de Madrid, Campus de Cantoblanco, Einstein 13, 28049 Madrid (Spain); Ynsa, M.D.; Munoz-Martin, A. [Centro de Microanalisis de Materiales (CMAM), Universidad Autonoma de Madrid, Campus de Cantoblanco, 28049 Madrid (Spain); Viedma, P.G. de; Castillo, A.; Martinez, I.; Andrade, C. [Instituto de Ciencias de la Construccion ' Eduardo Torroja' (IETcc-CSIC), Serrano Galvache, 4, 28033 Madrid (Spain); Zuloaga, P.; Ordonez, M. [Empresa Nacional de Residuos Radiactivos, S.A. (ENRESA), Emilio Vargas, 7, 28043 Madrid (Spain)

    2009-12-15

    The suitability of the application of Ion Beam Analysis (IBA) techniques such as Particle Induced X-ray Emission spectrometry (PIXE) and Rutherford Backscattering Spectrometry (RBS) to elemental depth profiling in concrete is analysed, studying hardened samples of concrete prior to and after a dynamic leaching test. A calibration of the data has been done by comparing the results obtained by IBA techniques with those obtained by Chemical and Thermogravimetric Analysis (TG/DTA). From PIXE and RBS data relevant information about the migration of minor elements, within the concrete matrix after leaching is obtained.

  16. Facile green synthesis of graphene-Au nanorod nanoassembly for on-line extraction and sensitive stripping analysis of methyl parathion

    International Nuclear Information System (INIS)

    Zhu, Wenxin; Liu, Wei; Li, Tianbao; Yue, Xiaoyue; Liu, Tao; Zhang, Wentao; Yu, Shaoxuan; Zhang, Daohong; Wang, Jianlong

    2014-01-01

    Graphical abstract: Schematic illustration for the facile green fabrication of GN-AuNRs/GCE and its application for the extraction and electroanalysis of MP. - Highlights: • This paper described a facile green electrochemical approach to synthesize graphene-AuNRs nanocomposite. • The as-synthesized sensor shows low LOD and wide linear concentration range towards MP. • The sensor can be well used for the determination of MP in water and kiwi fruits samples. • This paper further enlarges the scope of facile green synthetic methods of GN-based hybrids. - Abstract: This paper described a facile green electrochemical approach to synthesize graphene-AuNRs nanocomposite (GN-AuNRs) onto glassy carbon electrode (GCE) for electrocatalytic analysis of methyl parathion (MP). This electrochemical synthesis of GN-AuNRs hybrid is environmentally friendly for not involving the chemical reduction of graphene oxide (GO) and facile for just on the basis of electrostatic interaction between GO and AuNRs, as well as electrochemical reduction of GO-AuNRs to GN-AuNRs. Combined the high conductivity, large surface area, good adsorption capacity towards aromatic rings and high catalytic ability of graphene with the excellent electronic properties and adsorption capacity of AuNRs, the high sensitive methyl parathion sensor was fabricated with the GN-AuNRs nanocomposite. The limit of detection (LOD) of the proposed sensor was calculated to be 0.82 ng/mL, which was lower than many previously reported enzyme or nonenzyme-based sensors. In the meantime, the linear detection range of this sensor was from 10 to 500 ng/mL and 750 to 4000 ng/mL, which was also wider than many other enzyme or enzymeless sensors. Furthermore, the facile and green electrochemical reduction strategy provided here could also be used to construct more GN-based hybrids. And the GN-based hybrid might be a new and highly efficient SPE factor, which opens new opportunities for green, facile and sensitive analysis of

  17. OLDAPS: Obsidian Least Destructive Analysis Provenancing System

    Energy Technology Data Exchange (ETDEWEB)

    Eder, F.M.; Sterba, J.H.; Bichler, M. [Atominstitut, Vienna University of Technology, Vienna (Austria); Neelmeijer, C.; Merchel, S. [Helmholtz-Zentrum Dresden-Rossendorf (HZDR), Dresden (Germany); Pearce, N.J.G. [Institute of Geography and Earth Sciences, Aberystwyth University, Wales (United Kingdom)

    2013-07-01

    Full text: The natural volcanic glass obsidian is one of the classical objects of archaeometric analyses. Reliable provenancing by means of the highly specific chemical composition, the 'chemical fingerprint', can provide information about trading routes, extension of territory, long-distance contacts and the mobility of prehistoric people. Since the pioneer work of Cann and Renfrew in 1964 [1] various analytical methods have been employed on obsidian samples in order to locate their provenance. The existing data already offers important knowledge about long-distance interactions between prehistoric human populations. However, most applied techniques just show a small part of the element spectrum. Latest studies showed that published results gained by different analytical methods are not consistent due to systematic errors [2-3]. Therefore, the application of three complementary analytical techniques on the same set of raw material samples allows both a better characterization of obsidian sources and a comparison and validation of analytical results. The aim of this multi-methodical approach is to apply in particular: 1) lon Beam Analysis (IBA) comprising of Particle Induced X-ray Emission (PIXE) and Particle Induced Gamma-ray Emission (PIGE), 2) Instrumental Neutron Activation Analysis (INAA), 3) Laser Ablation-lnductively Coupled Plasma-Mass Spectrometry (LA-ICP-MS), to detect a maximum element spectrum and to compare element concentrations determined with at least two analytical techniques. This approach should check the accuracy and reliability of analytical results and should show a maximum of compositional differences between European obsidian sources to reveal the most characteristic 'chemical fingerprint' composed of more than 40 elements. These investigations are part of a new multi-methodical analytical database called the 'Obsidian Least Destructive Analysis Provenancing System' (OLDAPS). This novel scientific approach for

  18. 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.

  19. A cost effective approach for criticality accident analysis of a DOE SNF storage facility

    International Nuclear Information System (INIS)

    Garrett, R.L.; Couture, G.F.; Gough, S.T.

    1997-01-01

    This paper presents the methodologies used to derive criticality accident analyses for a spent nuclear fuel receipt, storage, handling, and shipping facility. Two criticality events are considered: process-induced and Natural Phenomena Hazards (NPH)-induced. The criticality analyses required the development of: (1) the frequency at which each sceanario occurred, (2) the estimated number of fissions for each scenario, and (3) the consequences associated with each criticality scenario. A fault tree analysis was performed to quantify the frequency of criticality due to process-induced events. For the frequency analysis of NPH-induced criticality, a probabilistic approach was employed. To estimate the consequences of a criticality event, the resulting fission yield was determined using a probabilistic approach. For estimating the source term, a 95% amount of overall conservatism was targeted. This methodology applied to the facility criticality scenarios indicated that: (1) the 95th percentile yield levels from the historical yield distributions are approximately 5 x 10 17 fissions and 5 x 10 18 fissions for internal event and NPH-induced criticality event, respectively; and (2) using probabilistic Latin Hypercube Sampling, the downwind 95th percentile dose to a receptor at the US DOE reservation boundary is 2.2 mrem. This estimate is compared to the bounding dose of 1.4 rem. 4 refs., 1 fig

  20. Multi-criteria analysis of potential recovery facilities in a reverse supply chain

    Science.gov (United States)

    Nukala, Satish; Gupta, Surendra M.

    2005-11-01

    Analytic Hierarchy Process (AHP) has been employed by researchers for solving multi-criteria analysis problems. However, AHP is often criticized for its unbalanced scale of judgments and failure to precisely handle the inherent uncertainty and vagueness in carrying out the pair-wise comparisons. With an objective to address these drawbacks, in this paper, we employ a fuzzy approach in selecting potential recovery facilities in the strategic planning of a reverse supply chain network that addresses the decision maker's level of confidence in the fuzzy assessments and his/her attitude towards risk. A numerical example is considered to illustrate the methodology.