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Sample records for analysis iba facility

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

    Science.gov (United States)

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

    2016-03-01

    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.

  2. Instrumental developments at the IBA-AMS dating facility at the University of Lecce

    International Nuclear Information System (INIS)

    The accelerator mass spectrometry (AMS) radiocarbon dating facility at the University of Lecce, Italy is now fully operational and in the first year of operation more than 500 samples both organic and inorganic have been measured for applications in archaeology, history of art, geology and environmental sciences. The experimental capabilities of the facility have been recently significantly improved by the installation of an in vacuum and in air ion beam analysis (IBA) beam line. Investigations are routinely carried out in material science and cultural heritage diagnostics

  3. 4He2+ and H2+ ion beam separation on ''Sokol'' IBA facility

    International Nuclear Information System (INIS)

    Two separation methods of 4He2+ and H2+ ion beams have been tested on ''Sokol'' IBA facility of NSC KIPT: use of existing beam-bending magnet and electrostatic analyzer, dissociation of H2+ ions when the beam passes through the carbon film. It is shown that these methods allow to decrease essentially the H2+ ion content in the 4He2+ beam.

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

    Science.gov (United States)

    Ivošević, Tatjana; Mandić, Luka; Orlić, Ivica; Stelcer, Eduard; Cohen, David D.

    2014-10-01

    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 PM2.5 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.

  5. 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.

  6. A 3 MV tandem accelerator at Seville. The first IBA facility in Spain

    International Nuclear Information System (INIS)

    The first Spanish tandem accelerator, of the Pelletron type, has recently been installed at the University of Seville. The laboratory has been created with the aim to fulfill the increasing demand for ion beam analysis existing in Spain. The facility mainly consists of a 3 MV accelerator with two ion sources and a capacity of seven beam lines, which will be used for interdisciplinary studies such as material research and modification, arts, archaeology, biology, medicine, environmental sciences and so on. The laboratory and the first tests of the accelerator performance are described. (author)

  7. Recent trends in IBA for cultural heritage studies

    Energy Technology Data Exchange (ETDEWEB)

    Beck, Lucile, E-mail: lucile.beck@cea.fr

    2014-08-01

    Ion beam analysis (IBA) techniques play an important role in the field of cultural heritage. IBA was one of the first physical methods applied to archaeology in the 70s. 40 years later, more than 25 accelerator laboratories were or are involved in cultural heritage applications. The advantages of the IBA techniques match very well the requirements for the analysis of archaeological or museum objects: non destructiveness, major, minor and trace element analysis, information in depth, elemental mapping… Thanks to this collected information, IBA techniques can answer archaeological and conservation questions: provenance determination, ancient technologies (fabrication, transformation, recipes…) and conservation issues. In spite of the competition with portable devices and large facilities (such as synchrotron or neutron reactors), the IBA methods keep their interest due to the possibility of associating two or three of them according to the archaeological or art issue. In this article, some examples chosen for their original approach are presented: PIXE for X-radiography, provenance of prehistoric pigments and painting characterisation. They illustrate the useful versatility of IBA for cultural heritage studies. Perspectives for further improvements are also proposed.

  8. Recent trends in IBA for cultural heritage studies

    International Nuclear Information System (INIS)

    Ion beam analysis (IBA) techniques play an important role in the field of cultural heritage. IBA was one of the first physical methods applied to archaeology in the 70s. 40 years later, more than 25 accelerator laboratories were or are involved in cultural heritage applications. The advantages of the IBA techniques match very well the requirements for the analysis of archaeological or museum objects: non destructiveness, major, minor and trace element analysis, information in depth, elemental mapping… Thanks to this collected information, IBA techniques can answer archaeological and conservation questions: provenance determination, ancient technologies (fabrication, transformation, recipes…) and conservation issues. In spite of the competition with portable devices and large facilities (such as synchrotron or neutron reactors), the IBA methods keep their interest due to the possibility of associating two or three of them according to the archaeological or art issue. In this article, some examples chosen for their original approach are presented: PIXE for X-radiography, provenance of prehistoric pigments and painting characterisation. They illustrate the useful versatility of IBA for cultural heritage studies. Perspectives for further improvements are also proposed

  9. 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.

  10. On the Applications of IBA Techniques to Biological Samples Analysis: PIXE and RBS

    International Nuclear Information System (INIS)

    The analytical techniques based on ion beams or IBA techniques give quantitative information on elemental concentration in samples of a wide variety of nature. In this work, we focus on PIXE technique, analyzing thick target biological specimens (TTPIXE), using 3 MeV protons produced by an electrostatic accelerator. A nuclear microprobe was used performing PIXE and RBS simultaneously, in order to solve the uncertainties produced in the absolute PIXE quantifying. The advantages of using both techniques and a nuclear microprobe are discussed. Quantitative results are shown to illustrate the multielemental resolution of the PIXE technique; for this, a blood standard was used

  11. IBA apartment block

    Czech Academy of Sciences Publication Activity Database

    Hnídková, Vendula

    [Řevnice]: Arbor vitae, 2012 - (Švácha, R.), s. 182-185 ISBN 978-80-87164-87-7 Institutional support: RVO:68378033 Keywords : Czech architecture * SIAL * IBA Berlin Subject RIV: AL - Art, Architecture, Cultural Heritage

  12. 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.

  13. Le tecniche AMS e IBA del CEDAD per lo studio dei Beni Culturali, Ambientali e per la Scienza dei Materiali

    Directory of Open Access Journals (Sweden)

    Lucio Calcagnile

    2011-09-01

    Full Text Available ItGli acceleratori di particelle sono diventati un potente strumento per la diagnostica dei materiali in molti campi di ricerca. Questo articolo descrive la facility AMS-IBA installata presso il CEDAD – Centro di Datazione e Diagnostica dell’Università del Salento e riporta alcune applicazioni in Archeologia, Scienze ambientali e Scienza dei materiali.EnParticle accelerators have become a powerful tool for the diagnostics of materials in many research fields. This paper describes the AMS-IBA (Accelerator Mass Spectrometry – Ion Beam Analysis facility installed at CEDAD-Center for Dating and Diagnostics of the University of Salento, Italy and some applications in Archaeology, Environmental Sciences and Materials Science.

  14. Medical Image Analysis Facility

    Science.gov (United States)

    1978-01-01

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

  15. 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.

  16. Aerosol characterisation in Italian towns by IBA techniques

    International Nuclear Information System (INIS)

    The composition of particulate matter in the atmosphere of four major Italian towns (Florence, Genoa, Milan and Naples) has been studied with the extensive application of IBA techniques. The aerosol has been collected simultaneously in the four towns during the first weeks of year 2001, by two-stage continuous streaker samplers, which provide the separation of the particulate matter in two fractions. The concentrations in air of about 20 elements, and the total particulate mass, have been extracted in the PM2.5 and PM10 fractions with hourly resolution by PIXE, PIGE and optical analyses of about 2700 samples. IBA analyses have been performed at the 3 MeV external proton beam of the INFN accelerator facility at the University of Florence

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

    International Nuclear Information System (INIS)

    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.)

  18. 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...

  19. Data analysis facility at LAMPF

    International Nuclear Information System (INIS)

    This report documents the discussions and conclusions of a study held in July 1977 to develop the requirements for a data analysis facility to support the experimental program in medium-energy physics at the Clinton P. Anderson Meson Physics Facility (LAMPF). 2 tables

  20. Chemical Analysis Facility

    Data.gov (United States)

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

  1. Design and Analysis Facility

    Data.gov (United States)

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

  2. Le tecniche AMS e IBA del CEDAD per lo studio dei Beni Culturali, Ambientali e per la Scienza dei Materiali

    OpenAIRE

    Lucio Calcagnile

    2011-01-01

    ItGli acceleratori di particelle sono diventati un potente strumento per la diagnostica dei materiali in molti campi di ricerca. Questo articolo descrive la facility AMS-IBA installata presso il CEDAD – Centro di Datazione e Diagnostica dell’Università del Salento e riporta alcune applicazioni in Archeologia, Scienze ambientali e Scienza dei materiali.EnParticle accelerators have become a powerful tool for the diagnostics of materials in many research fields. This paper describes the AMS-IBA...

  3. A correspondence between IBA-1 and IBA-2 models and electromagnetic transitions in the decay of some erbium isotopes

    Indian Academy of Sciences (India)

    Harun Reşit Yazar; İhsan Uluer

    2005-09-01

    The interacting boson approximation IBA-1 model space, in which neutron and proton degrees of freedom are not distinguished, can be considered as a subspace of the IBA-2 model space. Using the microscopic background of the IBA-2 model, a correspondence can be established between IBA-1 and IBA-2 model space. Since the space of the IBA-1 model can be regarded as a subspace of the IBA-2 model there is a unique way to `Project' the operators of the IBA-2 model onto those of IBA-1. This projection can be carried out using the -spin formalism. In the IBA-2 model, the lowest states are indeed fully symmetric, and using the calculations with the help of this projection, we explore the energy levels and the electric quadrupole transition probabilities (2; → ) and -ray 2/1 mixing ratios for selected transitions of 162,164,166,168,170Er. Owing to admixtures of non-fully-symmetric states in IBA-2, we renormalized the parameters () and (). This is the first time we show that this projection can be applied to some heavier isotopes and the results obtained for 162,164,166,168,170Er isotopes are reasonably in good agreement with the previous experimental values.

  4. An open source package for the IBA data format IDF

    International Nuclear Information System (INIS)

    Highlights: •The IBA interchange data format is implemented as open source code. •A DLL is provided to read and write IDF files. •Routines available to the user are described. •The IDF definition and routines is given in (http://idf.schemas.itn.pt/). -- Abstract: Ion Beam Analysis (IBA) codes and laboratories implement various formats to store the spectral data and to describe the experimental conditions and simulation or fit parameters. These various data formats are isolated applications and generally incompatible – they are unable to “talk” to each other. The need for a universal IBA data format (IDF) has been recognised for many years to allow easy transfer of data and simulation parameters between codes, as well as between experimentalists and data analysts. A new standard data format, IDF, which is transparent, universal, and includes the most common features desired by both experimentalists who collect and archive data and by users who analyse the data was previously presented. However, its actual implementation has been left to each individual software developer, and the sheer size of the full IDF definition has prevented widespread implementation, with only a few codes using the IDF. Open source software was now developed to implement the IDF, and made available to the community in (http://idf.schemas.itn.pt/) both as source code and as a DLL that every code and lab can use to, finally, make data of different origins “talk” to each other. We report the main features of the open source IDF package developed

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

    International Nuclear Information System (INIS)

    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

  6. IBA calculations of multipole mixing ratios

    International Nuclear Information System (INIS)

    Multipole mixing ratios of gamma rays serve as a sensitive probe of nuclear structure. Directional measurements, mostly by γγ angular correlation and nuclear orientation, yield the mixing ratios delta with sign. Unfortunately the results are often double valued. Furthermore, comparison between experimental and theoretical conversion coefficients can give |delta|. The E2/M1 mixing ratio delta(E2/M1) is of special importance in studying collective phenomena and models for their description. Present study is carried out mostly in terms of IBA-1, which makes no distinction between proton and neutron bosons

  7. 25 years of IBA teaching experience at the National Institute for Nuclear Science and Technology, France

    International Nuclear Information System (INIS)

    The National Institute for Nuclear Science and Technology (INSTN) is an advanced education institution created within the Commissariat a l'Energie Atomique (CEA) in 1956 and placed under the joint supervision of the Ministry of National Education and the Ministry of Industry. The INSTN provides students with specialised training in all nuclear energy-related disciplines. Since 1978, courses have been developed focusing on ion beam analysis (IBA). We present here the various experiments carried out for university laboratory work [practicals]. Over the past few years, the laboratory has provided IBA users with training courses offering a combined theoretical and experimental approach

  8. IBA's state of art Proton Therapy System

    International Nuclear Information System (INIS)

    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)

  9. The Pacific Northwest story. [imagery analysis facilities

    Science.gov (United States)

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

    1981-01-01

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

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

    International Nuclear Information System (INIS)

    Main aspects are discussed concerning nuclear reaction cross-sections for PIGE analyses, especially referring to cultural heritage diagnostics, within the framework of ion beam analysis (IBA) methods, also reviewing main results from recent international Conferences on Nuclear Data for Science and Technology and from NEA-NSC meetings and IAEA initiatives on the matter. In particular, within the frame of an overall summary on nuclear data requirements for IBA applications, main needs are pointed out specifically referred to the PIGE diagnostics purposes of present interest. Particularly, nuclear data relevant to light element analysis in archaeo-metry are specifically considered and their impact on the knowledge and conservation of the cultural heritage is pointed out, especially discussing most significant examples concerning the beneficial use from the evaluated nuclear data on the results obtained by the application of this nuclear analytical technique. Consistently, relevant topics are discussed concerning the evaluation of the requested nuclear reaction data, on the basis of the existing experimental values and nuclear model calculations, according to the appropriate parameterization and the consequent effects on the calculation results. Moreover, theoretical models on the nuclear structure and for estimation of the nuclear level densities are discussed, such as the modern algebraic models and the microscopic superfluid models, with emphasis on their influence on the calculations of photon production data, especially referring to the effects on the semi-empirical level density formula normally adopted in cross-section calculations, mainly to the parity-breaking effects and to the dependence of the most crucial level density parameter on the nuclear excitation energy. Accordingly, recent results are presented as obtained for (p,x) reaction data, by comparing critically selected experimental data and the relevant model calculations, with regard to significant

  11. Cold Vacuum Drying Facility hazard analysis report

    International Nuclear Information System (INIS)

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

  12. CUTBA (Cleaning Up the Tower of Babel of Acronyms) in IBA

    Science.gov (United States)

    Amsel, G.

    1996-09-01

    The various techniques used in ion beam analysis (IBA) are referred to by names that are often abbreviated into acronyms. While some contractions like RBS, NRA or PIXE are well established, one observes in recent literature an increasing trend to introduce new ad hoc acronyms for specific applications or techniques, although names already exist that may be adapted to correspond rather accurately to the concept. In the present situation even people well informed of this field have more and more difficulties to understand what is meant by, for example, ESS, PES, HIRBS, CERDA, CCM or CSTIM. This is especially true when the acronyms are used in titles or abstracts, without definition. To deal with this situation a list of acronyms encountered in recent literature was submitted by electronic mail consultation to a large panel of physicists active in the IBA field. The outcome of this electronic forum was discussed at a workshop held at the IBA-12 conference. Useful recommendations have been worked out to facilitate understanding of IBA-related acronyms, a consensus having been reached to lay down some not overly rigid guidelines.

  13. Calibration of a new experimental chamber for PIXE analysis at the Accelerator Facilities Division of Atomic Energy Centre Dhaka (AECD)

    International Nuclear Information System (INIS)

    A new experimental chamber has been installed at the 3 MV Van de Graaff Accelerator Facilities Division in the Atomic Energy Centre, Dhaka, to perform different Ion Beam Analysis (IBA) techniques. The calibration of this new setup for Particle Induced X-ray Emission (PIXE) technique has been done using a set of thin MicroMatter standards and GUPIX (PIXE spectrum analysis software), which is explicated in this paper. The effective thicknesses of the beryllium window of the X-ray detector and of the different absorbers used were determined. For standardization, the so called instrumental constant H (product of detector solid angle and the correction factor for the setup) as function of X-ray energy were determined and stored inside the GUPIX library for further PIXE analysis

  14. Calibration of a new experimental chamber for PIXE analysis at the Accelerator Facilities Division of Atomic Energy Centre Dhaka (AECD)

    Energy Technology Data Exchange (ETDEWEB)

    Hassan, Md. Taufique, E-mail: thassan@tulane.edu [Department of Physics, University of Dhaka (Bangladesh); Shariff, Md. Asad [Tandem Accelerator Facilities division, INST, AERE, Savar (Bangladesh); Hossein, Amzad; Abedin, Md. Joynal [Accelerator Facilities division, AECD (Bangladesh); Fazlul Hoque, A.K.M. [Daffodil International University, Dhaka (Bangladesh); Chowdhuri, M.S. [Department of Physics, University of Dhaka (Bangladesh)

    2015-05-01

    A new experimental chamber has been installed at the 3 MV Van de Graaff Accelerator Facilities Division in the Atomic Energy Centre, Dhaka, to perform different Ion Beam Analysis (IBA) techniques. The calibration of this new setup for Particle Induced X-ray Emission (PIXE) technique has been done using a set of thin MicroMatter standards and GUPIX (PIXE spectrum analysis software), which is explicated in this paper. The effective thicknesses of the beryllium window of the X-ray detector and of the different absorbers used were determined. For standardization, the so called instrumental constant H (product of detector solid angle and the correction factor for the setup) as function of X-ray energy were determined and stored inside the GUPIX library for further PIXE analysis.

  15. 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.

  16. Operating procedures: Fusion Experiments Analysis Facility

    International Nuclear Information System (INIS)

    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

  17. SRMAFTE facility checkout model flow field analysis

    Science.gov (United States)

    Dill, Richard A.; Whitesides, Harold R.

    1992-07-01

    The Solid Rocket Motor Air Flow Equipment (SRMAFTE) facility was constructed for the purpose of evaluating the internal propellant, insulation, and nozzle configurations of solid propellant rocket motor designs. This makes the characterization of the facility internal flow field very important in assuring that no facility induced flow field features exist which would corrupt the model related measurements. In order to verify the design and operation of the facility, a three-dimensional computational flow field analysis was performed on the facility checkout model setup. The checkout model measurement data, one-dimensional and three-dimensional estimates were compared, and the design and proper operation of the facility was verified. The proper operation of the metering nozzles, adapter chamber transition, model nozzle, and diffuser were verified. The one-dimensional and three-dimensional flow field estimates along with the available measurement data are compared.

  18. Ion beam analysis with external beams: Recent set-up improvements

    International Nuclear Information System (INIS)

    Accelerator-based analytical techniques using external beams are ideally fitted to the study of works of art because of their fully non-destructive character. However, accurate quantitative analysis is not straightforward, due in particular to difficult beam monitoring. Significant improvements have been progressively made on the external beam line of the IBA facility of the Louvre museum in order to increase the accuracy and to conduct combined analyses with different IBA techniques

  19. Ion beam analysis facility at the Institute of Geological and Nuclear Sciences

    International Nuclear Information System (INIS)

    Includes: Introduction to ion beam analysis; IBA techniques, including PIXE (particle induced x-ray emission), PIGE (particle induced gamma-ray emission), RBS (Rutherford backscattering spectrometry), ERD (elastic recoil detection) and NRA (nuclear reaction analysis); experimental details; and a case study on geothermal processes and fluid inclusions. Refs., 11 figs

  20. High-capacity neutron activation analysis facility

    International Nuclear Information System (INIS)

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

  1. Hazard analysis in uranium hexafluoride production facility

    International Nuclear Information System (INIS)

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

  2. A new mini gas ionization chamber for IBA applications

    International Nuclear Information System (INIS)

    Novel prototypes of high resolution gas ionization chambers (GIC) were designed with increased compactness and simplicity of the setup. They have no Frisch-grid and a simple anode wire. Under certain operating conditions these mini detectors have an energy resolution comparable with that of state-of-the-art GICs of much higher complexity. They can be operated both under vacuum and atmospheric pressure. First measurements were made with protons in the energy range of 0.3–1.0 MeV. For protons at 0.3 MeV an energy resolution of about 12 keV was achieved. With a 72 MeV 129Xe beam a relative resolution of 1.4% was obtained. Due to their versatility and reduced size the detectors can easily be applied in the field of ion beam analysis (IBA) and accelerator mass spectrometry (AMS). Since they are almost completely insensitive to radiation damage they are especially suited for use in high fluence applications such as scanning transmission ion microscopy (STIM). A comparison of the radiation hardness of the mini GIC with a Si PIN diode was therefore performed. The GIC showed no peak shift or change in energy resolution at all after collecting 1015 protons per cm2 while the performance of the Si detector clearly started to degrade at 1012 particles per cm2.

  3. A new mini gas ionization chamber for IBA applications

    Science.gov (United States)

    Müller, A. M.; Cassimi, A.; Döbeli, M.; Mallepell, M.; Monnet, I.; Simon, M. J.; Suter, M.; Synal, H.-A.

    2011-12-01

    Novel prototypes of high resolution gas ionization chambers ( GIC) were designed with increased compactness and simplicity of the setup. They have no Frisch-grid and a simple anode wire. Under certain operating conditions these mini detectors have an energy resolution comparable with that of state-of-the-art GICs of much higher complexity. They can be operated both under vacuum and atmospheric pressure. First measurements were made with protons in the energy range of 0.3-1.0 MeV. For protons at 0.3 MeV an energy resolution of about 12 keV was achieved. With a 72 MeV 129Xe beam a relative resolution of 1.4% was obtained. Due to their versatility and reduced size the detectors can easily be applied in the field of ion beam analysis ( IBA) and accelerator mass spectrometry ( AMS) . Since they are almost completely insensitive to radiation damage they are especially suited for use in high fluence applications such as scanning transmission ion microscopy ( STIM). A comparison of the radiation hardness of the mini GIC with a Si PIN diode was therefore performed. The GIC showed no peak shift or change in energy resolution at all after collecting 10 15 protons per cm 2 while the performance of the Si detector clearly started to degrade at 10 12 particles per cm 2.

  4. 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.

  5. 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.

  6. Hot Cell Facility (HCF) Safety Analysis Report

    International Nuclear Information System (INIS)

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

  7. Nuclear fuel cycle facility accident analysis handbook

    International Nuclear Information System (INIS)

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

  8. KFUPM fast neutron activation analysis facility

    International Nuclear Information System (INIS)

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

  9. Production Facility System Reliability Analysis Report

    Energy Technology Data Exchange (ETDEWEB)

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

    2015-10-06

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

  10. Determination of the angular dependence of the detector matrix Matrix X-evolution of IBA

    International Nuclear Information System (INIS)

    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).

  11. Computational analysis of PARAMETR facility experiments

    International Nuclear Information System (INIS)

    Full text of publication follows: Results of calculation of PARAMETR experiments are given in the paper. The PARAMETR facility is designed to research the phenomena relevant to typical LOCA scenarios (including severe accident) of VVER type reactors. The investigations at PARAMETR facility are directed to experimental research of fuel rods and core materials behavior, hydrogen generation processes, melting and interaction of core materials during severe accidents. The main facility components are rod bundle of 1250 mm heated length (up to 37 rods can be used), electrical power source, steam and water supply systems and instrumentation. The bundle is a mix of fresh fuel rods and electrically heated rods with uranium tablets and tungsten heater inside. The main objectives of calculations are analysis of computer code capability, in particular, RELAP/SCDAPSIM, to model severe accidents, identification of major parameter impact on calculation results and thus accident analysis improvements. RELAP/SCDAPSIM calculations were used to choose key parameters of experiments. Analysis of influence of thermal insulation properties, uncertainties of heater geometry, insulation thermal conductivity was done. Conditions and parameters needed to burn up intensive zirconium reaction were investigated. As a whole, calculation results showed good agreement with experiments. Some key points were observed such as essential impact of preheating phase, importance of thermal insulation material properties. Proper modeling of particular processes during preheating phase was very important since this phase defined bundle temperature level at the heating phase. There were some difficulties here. For instance, overestimation of temperatures had been observed until axial profiling of thermal conductivity was introduced. Some more proper models were used to reach the better agreement with experiments. The work done can be used in safety analysis of VVER type reactors and allow improving of

  12. Arabidopsis iba response5 Suppressors Separate Responses to Various Hormones

    OpenAIRE

    Strader, Lucia C.; Monroe-Augustus, Melanie; Rogers, Kristen C.; Lin, Grace L.; Bartel, Bonnie

    2008-01-01

    Auxin controls numerous plant growth processes by directing cell division and expansion. Auxin-response mutants, including iba response5 (ibr5), exhibit a long root and decreased lateral root production in response to exogenous auxins. ibr5 also displays resistance to the phytohormone abscisic acid (ABA). We found that the sar3 suppressor of auxin resistant1 (axr1) mutant does not suppress ibr5 auxin-response defects, suggesting that screening for ibr5 suppressors might reveal new components ...

  13. Europlanet Research Infrastructure: Planetary Sample Analysis Facilities

    Science.gov (United States)

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

    2008-09-01

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

  14. Radiochemical analysis of military nuclear facilities

    International Nuclear Information System (INIS)

    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

  15. Exploratory Studies Facility Subsurface Fire Hazards Analysis

    International Nuclear Information System (INIS)

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

  16. The data analysis facilities that astronomers want

    International Nuclear Information System (INIS)

    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

  17. Exploratory Studies Facility Subsurface Fire Hazards Analysis

    International Nuclear Information System (INIS)

    The primary objective of this Fire Hazard Analysis (FHA) is to confirm the requirements for a comprehensive fire and related hazards protection program for the Exploratory Studies Facility (ESF) are sufficient to minimize the potential for: 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

  18. 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.

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

    International Nuclear Information System (INIS)

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

  20. Mission analysis report - deactivation facilities at Hanford

    Energy Technology Data Exchange (ETDEWEB)

    Lund, D.P.

    1996-09-27

    This document examines the portion of the Hanford Site Cleanup Mission that deals with facility deactivation. How facilities get identified for deactivation, how they enter EM-60 for deactivation, programmatic alternatives to perform facility deactivation, the deactivation process itself, key requirements and objectives associated with the deactivation process, and deactivation planning are discussed.

  1. Waste sampling and characterization facility complex safety analysis

    Energy Technology Data Exchange (ETDEWEB)

    Meloy, R.T., Westinghouse Hanford

    1996-06-04

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

  2. Criticality safety analysis for mockup facility

    International Nuclear Information System (INIS)

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

  3. 300 Area fuel supply facilities deactivation mission analysis report

    International Nuclear Information System (INIS)

    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

  4. Recent developments in the air particulate research capability at the New Zealand ion beam analysis facility

    International Nuclear Information System (INIS)

    The New Zealand capability in Ion Beam Analysis of air particulate samples has been upgraded in recent years. The main equipment change has been the introduction of the ability to analyse samples taken using the Streaker (PIXE International Corporation) sampling system. This is an automated sampler which allows for great flexibility in monitoring programmes by collecting particulates for up to about 70 sampling periods which can range in collection times from seconds to many hours. The IBA analysis for hydrogen on standard filters and for PIXE multi-elemental analysis of the Streaker filters has also been studied with a view to optimising analytical methods. (author)

  5. 340 Waste handling Facility Hazard Categorization and Safety Analysis

    International Nuclear Information System (INIS)

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

  6. Cold vacuum drying facility final hazard analysis report

    Energy Technology Data Exchange (ETDEWEB)

    POWERS, T.B.

    1999-06-07

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

  7. Cold vacuum drying facility final hazard analysis report

    International Nuclear Information System (INIS)

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

  8. Cold Vacuum Drying (CVD) Facility Final Hazard Analysis Report

    International Nuclear Information System (INIS)

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

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

    Energy Technology Data Exchange (ETDEWEB)

    CROWE, R.D.

    2000-08-07

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

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

    International Nuclear Information System (INIS)

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

  11. Environmental analysis of biomass-ethanol facilities

    Energy Technology Data Exchange (ETDEWEB)

    Corbus, D.; Putsche, V.

    1995-12-01

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

  12. Developing the IBA equipment to increase the versatility of the CNA

    International Nuclear Information System (INIS)

    The Centro Nacional de Aceleradores (CNA) in Sevilla-Spain currently contains three accelerators: two tandems and a compact 18/9 cyclotron. Next year, a 60Co irradiation system will also be installed. This equipment will expand the range of irradiation experiments in the Centre using both charged particles as well as gamma-ray photons. Originally, based on the 3 MV tandem accelerator, the CNA was considered as a multidisciplinary research Centre devoted basically to the materials characterization by IBA techniques. Nowadays, the validity of our low-energy accelerators has been verified not only to perform analysis but also for irradiation testing, a very promising field of work since radiation effects are aggravated with the technology decreasing scales. In this work, the last innovations and modifications of our laboratory will be briefly described, emphasizing with respect to high energy PIXE experiments and its versatility to carry out irradiation tests.

  13. Developing the IBA equipment to increase the versatility of the CNA

    Energy Technology Data Exchange (ETDEWEB)

    Morilla, Y., E-mail: ymorilla@us.es [Centro Nacional de Aceleradores, Universidad de Sevilla, Thomas Alva Edison 7, E-41092 Sevilla (Spain); Jimenez-Ramos, M.C., E-mail: mcyjr@us.es [Centro Nacional de Aceleradores, Universidad de Sevilla, Thomas Alva Edison 7, E-41092 Sevilla (Spain); Garcia Lopez, J., E-mail: fjgl@us.es [Centro Nacional de Aceleradores, Universidad de Sevilla, Thomas Alva Edison 7, E-41092 Sevilla (Spain); Labrador, J.A., E-mail: labrador@us.es [Centro Nacional de Aceleradores, Universidad de Sevilla, Thomas Alva Edison 7, E-41092 Sevilla (Spain); Palomo, F.R., E-mail: rogelio@gte.esi.us.es [Departamento de Ingenieria Electronica, Escuela Superior de Ingenieros, Universidad de Sevilla, Descubrimientos s/n, E-41092 Sevilla (Spain); Ortega-Feliu, I., E-mail: iofeliu@us.es [Centro Nacional de Aceleradores, Universidad de Sevilla, Thomas Alva Edison 7, E-41092 Sevilla (Spain)

    2012-02-15

    The Centro Nacional de Aceleradores (CNA) in Sevilla-Spain currently contains three accelerators: two tandems and a compact 18/9 cyclotron. Next year, a {sup 60}Co irradiation system will also be installed. This equipment will expand the range of irradiation experiments in the Centre using both charged particles as well as gamma-ray photons. Originally, based on the 3 MV tandem accelerator, the CNA was considered as a multidisciplinary research Centre devoted basically to the materials characterization by IBA techniques. Nowadays, the validity of our low-energy accelerators has been verified not only to perform analysis but also for irradiation testing, a very promising field of work since radiation effects are aggravated with the technology decreasing scales. In this work, the last innovations and modifications of our laboratory will be briefly described, emphasizing with respect to high energy PIXE experiments and its versatility to carry out irradiation tests.

  14. IBA characterisation of glasses from the archaeological site of 'La Alcazaba', Almeria (Spain)

    International Nuclear Information System (INIS)

    'La Alcazaba de Almeria' is one of the most impressive mediaeval remains in Al-Andalus. It was the sea port of the Cordoba Caliphate and, afterwards, the capital of a 'Taifa' kingdom. In the course of recent excavations in this monumental area, several glass remains were found in the access to its palace and were dated back to the XIII-XV centuries, during the so-called 'Nazari' period. We have made PIGE and PIXE analysis of different fragments of these glasses in order to identify their composition versus the different colours and shapes. These analyses have been complemented with other techniques, like SEM in order to learn about the corrosion process suffered by these glasses during their long burial period. Also a comparison with ICP-OES has been made to check the validity of the IBA results in this case where we are dealing with corroded samples

  15. Establishment of rabbit radiation facility for neutron activation analysis

    International Nuclear Information System (INIS)

    The transfer principle and the composition of a rabbit radiation facility for neutron activation analysis in a reactor were introduced. The functions and security designs of the pneumatic transfer system and automatic control system in the irradiation device were studied. By the testing,the transfer speed of the facility is 7.0 m/s. The facility has advantages of steady transmission, simple operation, easy maintenance, etc. The facility satisfies the demand of the neutron activation analysis for short half-life nuclides. (authors)

  16. IBA for novice experimentalists. I. Introduction to IBA: mostly symmetries. II. Tests in even-even nuclei: mostly transitional systems. III. Supersymmetries: theory and experiment

    International Nuclear Information System (INIS)

    The report contains the notes from a series of lectures on the Interacting Boson Approximation (IBA) model. The lectures were presented at Lawrence Livermore National Laboratory on July 28, 30 and August 1, 1982 by Jolie A. Cizewski from Yale University. The IBA was developed by F. Iachello and A. Arima starting about seven years ago to understand collective quadrupole excitations in medium and heavy mass nuclei away from closed shells. Since then the formalism has been extended to odd-mass nuclei and considerable work has gone into understanding the microscopic construction of the bosons in this model. The IBA has been applied to nuclei as light as Zn and Ge and as heavy as U and Pu; to nuclei near closed shells, such as Mo and Hg; to stable nuclei and nuclei far from stability. The present lectures were designed to give the experimentalist an introduction to the IBA and to give specific examples of how it could be applied to understand the structure of heavy even and odd mass nuclei. Much of the emphasis was on the symmetries (and supersymmetries) of the model and how the use of symmetries enabled the relatively straightforward understanding of empirical systems as deviations from these symmetries. The richness of possible applications of the IBA to understanding collective phenomena in nuclei was not fully explored, but rather a few illustrative examples were selected and described in detail. The references, accumulated at the end of this report, provide a more comprehensive, although not complete, list of tests of the IBA in even mass nuclei and the new symmetries in odd mass nuclei. The references also list the main theoretical papers which provide the details of the IBA formalism

  17. 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.

  18. Integration of facility modeling capabilities for nuclear nonproliferation analysis

    International Nuclear Information System (INIS)

    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.

  19. Integration Of Facility Modeling Capabilities For Nuclear Nonproliferation Analysis

    International Nuclear Information System (INIS)

    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.

  20. Integration of Facility Modeling Capabilities for Nuclear Nonproliferation Analysis

    International Nuclear Information System (INIS)

    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.

  1. Cold Vacuum Drying Facility Design Basis Accident Analysis Documentation

    International Nuclear Information System (INIS)

    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

  2. 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.

  3. M1 transitions in even-even deformed nuclei and the IBA

    International Nuclear Information System (INIS)

    It is shown that the Interacting Boson Approximation can produce essentially identical results for M1 transitions in deformed even-even nuclei as can be obtained from the geometrical approach, and many comparisons with experiment are already available for the latter in the literature. Since no physical constants are involved in the IBA-1 formalism, it would be useful to use the similarity of the two approaches to obtain a physical description of the IBA constants. Use of the IBA-2 approach might also prove illuminating, since it should identify the contributions of the neutron and proton degrees of freedom, analogous to the method of Greiner

  4. CANISTER HANDLING FACILITY - VENTILATION CONFINEMENT ZONING ANALYSIS

    International Nuclear Information System (INIS)

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

  5. Financial Analysis of a Health-Care Facility

    OpenAIRE

    Bezděková, Pavla

    2009-01-01

    The aim of this work is carried out using selected methods the financial analysis of a Health-Care facility of the nature a hospital, an assessment of its financial health, its operation and financing.

  6. In-beam activation analysis facility at MLZ, Garching

    Energy Technology Data Exchange (ETDEWEB)

    Révay, Zs., E-mail: zsolt.revay@frm2.tum.de [Heinz Maier-Leibniz Zentrum (MLZ), Technische Universität München, 85748 Garching (Germany); Kudějová, P.; Kleszcz, K.; Söllradl, S. [Heinz Maier-Leibniz Zentrum (MLZ), Technische Universität München, 85748 Garching (Germany); Genreith, Christoph [Heinz Maier-Leibniz Zentrum (MLZ), Technische Universität München, 85748 Garching (Germany); Institute of Energy and Climate Research, IEK-6: Nuclear Waste and Reactor Safety Fuel Cycle, Forschungszentrum Jülich GmbH in der Helmholtz-Gemeinschaft, 52428 Jülich (Germany)

    2015-11-01

    The reconstruction of the prompt gamma activation analysis facility and the construction of the new low-background counting chamber at MLZ, Garching is presented. The improvement of the shielding and its effect on the radiation background is shown. The setting up and the fine-tuning of the electronics and their characterization are also discussed. The upgraded facility has been demonstrated to be applicable for both PGAA and neutron activation analysis using in-beam activation and decay counting in the low-background counting chamber. - Highlights: • Radiation background at the PGAA facility was efficiently reduced. • In-beam irradiation facility in the strongest neutron beam. • The best signal-to-background ratio at a PGAA facility was achieved.

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

    Science.gov (United States)

    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.

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

    International Nuclear Information System (INIS)

    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

  9. 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)

    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)

  10. A new PIXE/PIGME analysis facility

    International Nuclear Information System (INIS)

    A new PIXE/PIGME ion beam facility is being developed for use on the 3MeV Van de Graaff accelerator. It will be used to analyse geological samples prepared on microscope slides. The samples will be movable in the X and Y axis using remote or computer controlled motorised micrometers. Other features of the rig include remote selection of X-ray detector filters and beam defining apertures. Beam current monitoring is by backscattering, whilst target positions are determined optically using a variable gain borescope. The rig will be a useful tool when analysing very small targets or when target scanning is necessary

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

    Science.gov (United States)

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

    2004-09-01

    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 ®. 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.

  12. Risk Analysis for the Radioactive Waste Management Facility

    International Nuclear Information System (INIS)

    Method of PSA has been applied to nuclear reactor for power reactor or research reactor. As IAEA recommendation, PSA could be used on non-reactor nuclear facility. In this paper, PSA method has been applied for the radioactive waste management facility. Purpose of this method is to determine the risk that is combination of probability and consequence. In these cases, discharge of radioactive material and chemical substance and overexposure are as consequence. Analysis is carried out by two stages, firstly it determines initiating event and secondly, it makes accident sequence modeling. Analysis has been done for 5 group of initiating events. Initiating event frequency is adopted from facility condition and NUREG data. As component reliability data is used from data of IAEA-TECDOC-478 and NUREG. Result of analysis, probability of consequence is about 10-10 per year to 10-5 per year. The radioactive waste management facility is safe enough because probability of consequence is very small

  13. Nuclear fuel cycle facility accident analysis handbook

    International Nuclear Information System (INIS)

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

  14. Nuclear fuel cycle facility accident analysis handbook

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-03-01

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

  15. Analysis - The new legislation for nuclear facilities

    International Nuclear Information System (INIS)

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

  16. IBA-Europhysics Prize in Applied Nuclear Science and Nuclear Methods in Medicine

    Science.gov (United States)

    MacGregor, I. J. Douglas

    2014-03-01

    The Nuclear Physics Board of the European Physical Society is pleased to announce that the 2013 IBA-Europhysics Prize in Applied Nuclear Science and Nuclear Methods in Medicine is awarded to Prof. Marco Durante, Director of the Biophysics Department at GSI Helmholtz Center (Darmstadt, Germany); Professor at the Technical University of Darmstadt (Germany) and Adjunct Professor at the Temple University, Philadelphia, USA. The prize was presented in the closing Session of the INPC 2013 conference by Mr. Thomas Servais, R&D Manager for Accelerator Development at the IBA group, who sponsor the IBA Europhysics Prize. The Prize Diploma was presented by Dr. I J Douglas MacGregor, Chair-elect of the EPS Nuclear Physics Division and Chair of the IBA Prize committee.

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

    International Nuclear Information System (INIS)

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

  18. 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.

  19. The IBA state-of-the-art proton therapy system, performances and recent results

    International Nuclear Information System (INIS)

    In recent years IBA has continued its development of state-of-the-art systems for Proton Therapy. While the machine performance at the NPTC is such that all clinical specifications are met, IBA has continued to improve the proposed equipment to set even higher standards. Improvements in the ion source control, gantries, and patient alignment systems will be addressed in the oral presentation and the first results obtained with the Pencil Beam Scanning algorithm will be presented

  20. Effects of IBA and Putrescine on Root Formation of Olive Cuttings

    OpenAIRE

    Elham Aslmoshtaghi; Ali Reza Shahsavar; Mohammad Reza Taslimpour

    2014-01-01

    Semi-hardwood cuttings of olive cv. ‘Tokhmkabki’ (low rooting ability) and cv. ‘Roghani’ (high rooting ability) were obtained from 1-year-old shoots. Cuttings were dipped in 2000, 4000, and 6000 mg L-1 IBA, 150 or 300 mg L-1 putrescine and their combination before rooting in greenhouse equipped with an automatic mist system. Rooting ability was evaluated four months after planting for each treatment. Satisfactory rooting occurred when IBA was applied with putrescine,...

  1. Neutronics analysis of the Laboratory Microfusion Facility

    International Nuclear Information System (INIS)

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

  2. Radioisotope Power System Facility shielding analysis

    International Nuclear Information System (INIS)

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

  3. Neutronics analysis of the laboratory microfusion facility

    International Nuclear Information System (INIS)

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

  4. Seismic analysis of the MFTF facility

    International Nuclear Information System (INIS)

    Seismic analyses were performed on the Mirror Fusion Test Facility (MFTF-B) located at the Lawrence Livermore National Laboratory, Livermore, CA. The three major structures studied were the vacuum vessel, the concrete shielding vault, and the steel frame enclosure building. The analyses performed on these structures ranged from fixed-base response spectrum analyses to soil-structure interaction analyses including the effects of structure-to-structure interaction and foundation flexibility. The results of these studies showed that the presence of the vault significantly affects the response of the vessel; that modeling the flexibility of the vault footing is important when studying forces near the base of the wall; and that the vault had very little effect on the building response. (orig.)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2001-07-01

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

  6. Fault tree analysis for red oil explosion in reprocessing facility

    International Nuclear Information System (INIS)

    Almost all spent fuel reprocessing facilities have adopted Purex process. The red oil explosion is a great concern in safety study of spent fuel reprocessing facilities adopting Purex process. The event tree and fault tree analysis was performed for the red oil explosion of a medium level radioactive waste liquid evaporator for the collective decontamination and separation cycle segment in a representative reprocessing facility in this paper. The results show that the occurrence frequency of a red oil explosion is extremely low, and human errors and common cause failures are major causes to a red oil explosion. Therefore, some relevant measures should be taken to prevent such accidents. (authors)

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

    International Nuclear Information System (INIS)

    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

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

    International Nuclear Information System (INIS)

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

  9. 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.

  10. 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.

  11. ESF [Exploratory Shaft Facility] flexibility analysis

    International Nuclear Information System (INIS)

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

  12. Analysis of personnel error occurrence reports across Defense Program facilities

    Energy Technology Data Exchange (ETDEWEB)

    Stock, D.A.; Shurberg, D.A.; O`Brien, J.N.

    1994-05-01

    More than 2,000 reports from the Occurrence Reporting and Processing System (ORPS) database were examined in order to identify weaknesses in the implementation of the guidance for the Conduct of Operations (DOE Order 5480.19) at Defense Program (DP) facilities. The analysis revealed recurrent problems involving procedures, training of employees, the occurrence of accidents, planning and scheduling of daily operations, and communications. Changes to DOE 5480.19 and modifications of the Occurrence Reporting and Processing System are recommended to reduce the frequency of these problems. The primary tool used in this analysis was a coding scheme based on the guidelines in 5480.19, which was used to classify the textual content of occurrence reports. The occurrence reports selected for analysis came from across all DP facilities, and listed personnel error as a cause of the event. A number of additional reports, specifically from the Plutonium Processing and Handling Facility (TA55), and the Chemistry and Metallurgy Research Facility (CMR), at Los Alamos National Laboratory, were analyzed separately as a case study. In total, 2070 occurrence reports were examined for this analysis. A number of core issues were consistently found in all analyses conducted, and all subsets of data examined. When individual DP sites were analyzed, including some sites which have since been transferred, only minor variations were found in the importance of these core issues. The same issues also appeared in different time periods, in different types of reports, and at the two Los Alamos facilities selected for the case study.

  13. Safety analysis of the existing 851 Firing Facility

    International Nuclear Information System (INIS)

    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

  14. Safety analysis of the existing 850 Firing Facility

    International Nuclear Information System (INIS)

    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

  15. Ecotoxicity studies of antifungal metabolites of Bacillus sp. IBA 33.

    Directory of Open Access Journals (Sweden)

    MA Gordillo

    2015-01-01

    Full Text Available El incremento de enfermedade s de plantas causado por la proliferación de patógenos resis tentes a fungicidas intensificó la investigación de nuevos metabo litos activos contra ellos. El es tudio de métodos biológicos como una a lternativa al control químico h a alcanzado relevancia en años r ecientes. Se ha sugerido que el u so de metabolitos de Bacillus , es una alternativa o un método suplementario a la protección química de las plantas, siempre y cuando ellos no sean tóxicos para los consumidores y sean amiga bles para el medio ambiente. Se ha ev aluado la toxicidad de diferent es concentraciones de metabolito s antifúngicos producidos por Bacillus sp. IBA33. Se investigó su capacidad para inducir efectos citotóxicos mediante diferentes tests como hemólisis e inmovilización de Artemia salina y Allium cepa L. Con 2.56 mg/ml de metabolitos antifúngicos la hemólisis alcanzó 24.07%, para 1 .28 mg/ml fue 14%. La HC 50 fue 10.41 mg/ml. Nauplios de Artemia salina expuestos a 3.2; 1.6 y 0.8 mg/ml de metabolitos antifúngicos mostraron 80; 20 y 10% de morta lidad respectivamente después d e 24 h de tratamiento; la LD 50 fue 2.24 mg/ml. En el test de Allium cepa L después de 72 h de tratamien to, la longitud de las raíces fueron 8.75; 10.35 y 23.75 mm con 3.2; 1.6 y 0.8 mg/ml de metabolitos antifúngicos respectivamente, con una EC 50 de 0.078 mg/ml. Después de 144 h la EC 50 fue 4.11 mg/ml. Solamente con 3.2 mg/ml de metabolitos fue ron observadas aberraciones cromosómicas, vacualización y descentralización de los núcleos en las células de Allium cepa L. No se observaron micronúcleos. Bajo las condiciones experimentales, las concentraciones de metaboli tos antifúngicos ensayadas son consideradas no tóxicas.

  16. Analysis of the zone approach for plutonium facilities

    International Nuclear Information System (INIS)

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

  17. Use of Iba Techniques to Characterize High Velocity Thermal Spray Coatings

    Science.gov (United States)

    Trompetter, W.; Markwitz, A.; Hyland, M.

    Spray coatings are being used in an increasingly wide range of industries to improve the abrasive, erosive and sliding wear of machine components. Over the past decade industries have moved to the application of supersonic high velocity thermal spray techniques. These coating techniques produce superior coating quality in comparison to other traditional techniques such as plasma spraying. To date the knowledge of the bonding processes and the structure of the particles within thermal spray coatings is very subjective. The aim of this research is to improve our understanding of these materials through the use of IBA techniques in conjunction with other materials analysis techniques. Samples were prepared by spraying a widely used commercial NiCr powder onto substrates using a HVAF (high velocity air fuel) thermal spraying technique. Detailed analysis of the composition and structure of the power particles revealed two distinct types of particles. The majority was NiCr particles with a significant minority of particles composing of SiO2/CrO3. When the particles were investigated both as raw powder and in the sprayed coating, it was surprising to find that the composition of the coating meterial remained unchanged during the coating process despite the high velocity application.

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

    International Nuclear Information System (INIS)

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

  19. Insider threat to secure facilities: data analysis

    International Nuclear Information System (INIS)

    Three data sets drawn from industries that have experienced internal security breaches are analyzed. The industries and the insider security breaches are considered analogous in one or more respects to insider threats potentially confronting managers in the nuclear industry. The three data sets are: bank fraud and embezzlement (BF and E), computer-related crime, and drug theft from drug manufacturers and distributors. A careful analysis by both descriptive and formal statistical techniques permits certain general conclusions on the internal threat to secure industries to be drawn. These conclusions are discussed and related to the potential insider threat in the nuclear industry. 49 tabs

  20. Insider threat to secure facilities: data analysis

    Energy Technology Data Exchange (ETDEWEB)

    1979-12-07

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

  1. Inhomogeneous distribution of Iba-1 characterizes microglial pathology in Alzheimer's disease.

    Science.gov (United States)

    Tischer, Jasmin; Krueger, Martin; Mueller, Wolf; Staszewski, Ori; Prinz, Marco; Streit, Wolfgang J; Bechmann, Ingo

    2016-09-01

    Microglial dystrophy has recently been described as a morphological phenotype of microglia that differs from resting and activated states by spheroid formation and cytorrhexis. In thick sections immunolabeled for HLA-DR or Iba-1 dystrophic microglial processes lose their typical, homogeneous staining pattern and appear to be fragmented or clustered. In this study, we performed double immunofluorescence and electron microscopy to determine if this labeling pattern indeed reflects complete separation of microglial processes from the soma. Using Iba-1/CD68 and Iba-1/MHC class II, as microglial markers, we observed that isolated Iba-1 fragments were still connected to each other by segments of the microglial process immune positive for CD68 or MHC class II. Ultrathin serial sections of two Iba-1 fragments which appeared to be disconnected from each other at the light microscopical level revealed a still existing "bridge" with a diameter of around 0.182 µm. Therefore, microglial dystrophy may reflect alterations of the cytoskeleton ultimately leading to slow cytorrhexis. GLIA 2016;64:1562-1572. PMID:27404378

  2. 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).

  3. 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).

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

    International Nuclear Information System (INIS)

    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.

  5. 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.

  6. A systems analysis approach to nuclear facility siting

    International Nuclear Information System (INIS)

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

  7. 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.

  8. Cold Vacuum Drying facility design basis accident analysis documentation

    International Nuclear Information System (INIS)

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

  11. 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.

  12. Comprehensive safety analysis for pressure and cryogenic systems facilities

    International Nuclear Information System (INIS)

    There have been many instances where serious injuries and fatalities have resulted from over-pressurization, thermal stress, asphyxiation and other potential hazards associated with testing, handling and storage of compressed gases and cryogenic liquids at numerous production and research facilities. These hazards are major issues that should be addressed in system design and in materials selection appropriate for high pressure or cryogenic temperature applications. Potential hazards may be mitigated through system analysis and design process which are the major factors in preventing thermal/pressure hazards caused by possible leaks and fragmentation, in the case of rupture. This paper presents a conceptual model and framework for developing a comprehensive safety analysis which will reduce potential hazards, accidents and legal liabilities. The proposed in-depth system Safety Analysis Report (SAR) is a proven systematic approach to identify hazards and influence design to provide timely documentation of potential hazards and risks associated with systems, facilities, and equipment. As a result of this hazard analysis process, provisions and actions for hazard prevention, elimination, mitigation, and control have been put in place, and all identifiable potential hazards have been reduced to a low risk level. These methods are demonstrated in the example of comprehensive safety analysis of Cryogenic Subsystem of Accelerator String Test facilities (ASST) at Superconducting Super Collider Laboratory by developing Safety Analysis Report (SSC Laboratory, 1992)

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

    Energy Technology Data Exchange (ETDEWEB)

    Linderoth, C.E.

    1984-03-01

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

  14. Preliminary safety analysis report for the Waste Characterization Facility

    International Nuclear Information System (INIS)

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

  15. 303-K Storage facility sampling and analysis plan

    Energy Technology Data Exchange (ETDEWEB)

    Adler, J.G.

    1997-07-01

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

  16. Fault Tree Analysis of an Accident Probability for Pyroprocessing Facility

    International Nuclear Information System (INIS)

    The pyroprocessing technology is one of the spent fuel recycling technologies. Korea Atomic Energy Research Institute(KAERI) started the R and D about the pyroprocessing technology in 1997. The physical protection system requirements based on the VAI should be prepared for applying the pyroprocessing facility in Korea. In this study, we have arranged the accidents which can be happened in pyroprocessing facility. Then, we have obtained the accident path according to the hazards. We can expect that this study will be taken to the VAI as a basic data. The fault tree is not complete yet. The fault tree for an accident probability of pyroprocessing facility is being made according to the hot cell area and each process. Conclusions will be handled after finishing the fault tree analysis

  17. 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...

  18. Integration of facility modeling capabilities for nuclear nonproliferation analysis

    International Nuclear Information System (INIS)

    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.

  19. PROMPT DOSE ANALYSIS FOR THE NATIONAL IGNITION FACILITY

    Energy Technology Data Exchange (ETDEWEB)

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

    2008-09-23

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

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

    International Nuclear Information System (INIS)

    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

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

    International Nuclear Information System (INIS)

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1996-03-01

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

  4. Safeguardability analysis for an engineering scale pyroprocess facility

    International Nuclear Information System (INIS)

    A qualitative safeguardability analysis was undertaken to investigate the safeguards system and draw recommendations for enhancing the performance of the safeguards system for an engineering-scale pyroprocess model facility. The analysis utilized INPRO proliferation resistance (PR) assessment methodologies including diversion pathway analysis. Uranium and transuranic metal (U/TRU) products emit high neutrons and gamma-rays, which are strong enough to be detected by the passive nondestructive assay (NDA) measurements and the hot-cells can role as inherently robust containments. Even though the product materials could be attractive, the abrupt diversion of U/TRU ingots through the selected pathway from the model facility will be reasonably difficult and detectable by applying the appropriate safeguards measures. For the design features to support safeguards implementation of the facility, more effective utilization of the inherent containment and enhancement of portal monitoring as well as focusing on the accounting material flow into and out of the system will make it possible to satisfy the safeguards goal. (author)

  5. The scanning microbeam PIXE analysis facility at NIRS

    International Nuclear Information System (INIS)

    In March 1999, a HVEE Tandetron was installed in the Electrostatic Accelerator Building of National Institute of Radiological Sciences (NIRS) for particle induced X-ray emission (PIXE) analysis. The specifications of the Tandetron accelerator system operating at NIRS are as follows: the accelerating voltage is 0.4-1.7 MV, and the maximum beam current is 500 nA at 3.4 MeV. The accelerator facility incorporates three beam lines for conventional, in-air and microbeam PIXE analysis. The scanning microbeam PIXE analysis line is based around an Oxford Microbeams OM2000 nuclear microscope end stage. This system provides the ability of multi-elemental mapping over sample areas up to 2 x 2 mm area with spatial resolutions routinely at 1 x 1 μm. The scheduled operation of this facility started in April 2000 and is controlled by the Division of Technical Service and Development. The result of beam resolution tests carried out in 2001 are as follows: for scanning transmission ion microscopy, the estimated beam size is 100 x 200 nm, measured using a 2.6 MeV proton beam scanned over a 12.7 μm repeat distance copper grid. For PIXE operation at 50 pA beam current the estimated best spot size is 0.4 x 0.6 μm. The microbeam facility is being used for research into the elemental distribution of small biological samples such as biological cells and tissue

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

    International Nuclear Information System (INIS)

    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

  7. Analysis of occupational doses in radioactive and nuclear facilities

    International Nuclear Information System (INIS)

    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

  8. BUSTED BUTTE TEST FACILITY GROUND SUPPORT CONFIRMATION ANALYSIS

    International Nuclear Information System (INIS)

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

  9. Effects of IBA and Putrescine on Root Formation of Olive Cuttings

    Directory of Open Access Journals (Sweden)

    Elham Aslmoshtaghi

    2014-11-01

    Full Text Available 800x600 Normal 0 false false false EN-US X-NONE AR-SA MicrosoftInternetExplorer4 /* Style Definitions */ table.MsoNormalTable {mso-style-name:"Table Normal"; mso-tstyle-rowband-size:0; mso-tstyle-colband-size:0; mso-style-noshow:yes; mso-style-priority:99; mso-style-parent:""; mso-padding-alt:0cm 5.4pt 0cm 5.4pt; mso-para-margin:0cm; mso-para-margin-bottom:.0001pt; mso-pagination:widow-orphan; font-size:10.0pt; font-family:"Times New Roman","serif";} Normal 0 21 false false false HR X-NONE X-NONE MicrosoftInternetExplorer4 Semi-hardwood cuttings of olive cv. ‘Tokhmkabki’ (low rooting ability and cv. ‘Roghani’ (high rooting ability were obtained from 1-year-old shoots. Cuttings were dipped in 2000, 4000, and 6000 mg L-1 IBA, 150 or 300 mg L-1 putrescine and their combination before rooting in greenhouse equipped with an automatic mist system. Rooting ability was evaluated four months after planting for each treatment. Satisfactory rooting occurred when IBA was applied with putrescine, whereas cuttings treated with IBA or putrescine alone showed a limited capacity of rooting in both cultivars. The greatest rooting percentage for cv. ‘Roghani’ was detected when IBA at 4000 mg∙L-1 + putrescine 300 at mg∙L-1, IBA at 4000 mg∙L-1 + putrescine at 150 mg∙L-1 were applied. For cv. ‘Tokhmkabki’ the most successful treatments were IBA at 6000 mg∙L-1 + putrescine at 150 mg∙L-1 and IBA at 6000 mg∙L-1 + putrescine at 300 mg L-1. The current findings confirm that putrescine can be a useful substance for increasing rooting percentage and root quality in cuttings of olive cultivars. Normal 0 21 false false false HR X-NONE X-NONE A decision analysis of an exploratory studies facility

    International Nuclear Information System (INIS)

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

  10. Adventitious rhizogenesis in Bambusa nutans and Bambusa tulda: Influence of seasonal variation, IBA and cutting type

    Institute of Scientific and Technical Information of China (English)

    S. Singh; S. Yadav; P. K. Patel; S.A.Ansari

    2011-01-01

    The influence of seasonal variation,indole-3-butyric acid (IBA) and type of cuttings wasexamined on induction and growth of adventitious roots in Bambusa nutans Wall.and Bambusa tulda Roxb.Singlenode culm and culm-branch cuttings from the mature culms were provided with immersion treatment for 24 h of either water (control) or 2 mM IBA in four different seasons,i.e.,spring (mid February),summer (mid May),rainy (mid July),and winter (mid November) and maintained for two months in the mist chamber at the relative humidity of (70±5)%and the temperature of (30±2)℃.In B.nutans,adventitious rooting occuffed in both types of cuttings in all the seasons with the best rooting in the summer season i.e.,May (88% in culm cuttings) and the least in winter.On the contrary,adventitious rooting was recorded only in culm cuttings in spring and summer season in B.tulda.IBA treatment significantly enhanced rooting,root number and root length; registering 14 to 17 times improvement over control in the best rooting season.Three factor- interactions (season × cutting type × IBA treatment) were significant for rooting in B.nutans and all characteristics,except sprouting in B.tulda.Thus,single-node culm and culm-branch cuttings in B.nutans and culm cuttings in B.tulda treated with 2 mM IBA during spring (February)to summer (May) season are recommended for their clonal multiplication.

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

    International Nuclear Information System (INIS)

    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)

  12. Radiation analysis for a generic centralized interim storage facility

    International Nuclear Information System (INIS)

    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

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

  15. Cold Vacuum Drying (CVD) Facility Sampling and Analysis Plan

    International Nuclear Information System (INIS)

    The Cold Vacuum Drying (CVD) Facility provides the required process systems, supporting equipment, and facilities needed for the conditioning of spent nuclear fuel (SNF) from the Hanford K-Basins prior to storage at the Canister Storage Building (CSB). The process water conditioning (PWC) system collects and treats the selected liquid effluent streams generated by the CVD process. The PWC system uses ion exchange modules (IXMs) and filtration to remove radioactive ions and particulate from CVD effluent streams. Water treated by the PWC is collected in a 5000-gallon storage tank prior to shipment to an on-site facility for additional treatment and disposal. The purpose of this sampling and analysis plan is to document the basis for achieving the following data quality objectives: (1) Measurement of the radionuclide content of the water transferred from the multi-canister overpack (MCO), vacuum purge system (VPS) condensate tank, MCO/Cask annulus and deionized water flushes to the PWC system receiver tanks. (2) Trending the radionuclide inventory of IXMs to assure that they do not exceed the limits prescribed in HNF-2760, Rev. 0-D, ''Safety Analysis Report for Packaging (Onsite) Ion Exchange Modules,'' and HNF-EP-0063 Rev. 5, ''Hanford Site Solid Waste Acceptance Criteria'' for Category 3, non-TRU, low level waste (LLW). (3) Determining the radionuclide content of the PWC system bulk water storage tank to assure that it meets the limits set forth in HNF-3 172, Rev. 0, ''Hanford Site Liquid Waste Acceptance Criteria,'' to permit transfer and disposal at the Effluent Treatment Facility (ETF) located at the 200 East Area

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

    Energy Technology Data Exchange (ETDEWEB)

    Charlton, William S

    1999-09-01

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

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

    International Nuclear Information System (INIS)

    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

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

    International Nuclear Information System (INIS)

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

  19. Criticality analysis for uranium-scrap recycling facilities

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

  2. Waste Encapsulation and Storage Facility mission analysis report

    International Nuclear Information System (INIS)

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

  3. Inventory difference analysis at Los Alamos Plutonium Facility

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

  5. 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.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2004-06-16

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

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

    International Nuclear Information System (INIS)

    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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1977-09-01

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

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

    OpenAIRE

    Martinović Nataša; Delibašić Boris

    2014-01-01

    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 t...

  10. IBA methods for characterisation of fine particulate atmospheric pollution: a local, regional and global research problem

    International Nuclear Information System (INIS)

    The IBA techniques of PIXE, PIGE, RBS and PESA have been used simultaneously to analyse fine particle pollution collected on Teflon filters. This provided a suite of 23 elements from hydrogen to lead which can be used to characterisation and fingerprint pollution sources and estimate their contributions to the total mass loading. These methods have been demonstrated to be applicable for aerosol pollution studies on a local, regional and even globe scale on time frames from a few days to decades

  11. Quantitative risk analysis of oil storage facilities in seismic areas.

    Science.gov (United States)

    Fabbrocino, Giovanni; Iervolino, Iunio; Orlando, Francesca; Salzano, Ernesto

    2005-08-31

    Quantitative risk analysis (QRA) of industrial facilities has to take into account multiple hazards threatening critical equipment. Nevertheless, engineering procedures able to evaluate quantitatively the effect of seismic action are not well established. Indeed, relevant industrial accidents may be triggered by loss of containment following ground shaking or other relevant natural hazards, either directly or through cascade effects ('domino effects'). The issue of integrating structural seismic risk into quantitative probabilistic seismic risk analysis (QpsRA) is addressed in this paper by a representative study case regarding an oil storage plant with a number of atmospheric steel tanks containing flammable substances. Empirical seismic fragility curves and probit functions, properly defined both for building-like and non building-like industrial components, have been crossed with outcomes of probabilistic seismic hazard analysis (PSHA) for a test site located in south Italy. Once the seismic failure probabilities have been quantified, consequence analysis has been performed for those events which may be triggered by the loss of containment following seismic action. Results are combined by means of a specific developed code in terms of local risk contour plots, i.e. the contour line for the probability of fatal injures at any point (x, y) in the analysed area. Finally, a comparison with QRA obtained by considering only process-related top events is reported for reference. PMID:15908107

  12. A description of the BNL active surface analysis facility

    International Nuclear Information System (INIS)

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

  13. Radiation Shielding Analysis of Electron Beam Accelerator Facility

    International Nuclear Information System (INIS)

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

  14. Surface Fire Hazards Analysis Technical Report-Constructor Facilities

    International Nuclear Information System (INIS)

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

  15. 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.

  16. National Ignition Facility Shot Data Analysis Module Guidelines

    Energy Technology Data Exchange (ETDEWEB)

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

    2007-10-03

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

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

    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

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

    OpenAIRE

    Nykänen, Arja; Canali, Stefano

    2006-01-01

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

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

    Science.gov (United States)

    Snoj, Luka; Zerovnik, Gašper; Trkov, Andrej

    2012-03-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    Hutton, Matthew S., E-mail: hutton1@llnl.gov [Lawrence Livermore National Laboratory, Livermore, CA (United States); Azevedo, Stephen; Beeler, Richard; Bettenhausen, Rita; Bond, Essex; Casey, Allan; Liebman, Judith; Marsh, Amber; Pannell, Thomas; Warrick, Abbie [Lawrence Livermore National Laboratory, Livermore, CA (United States)

    2012-12-15

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

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

    International Nuclear Information System (INIS)

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

  3. Low temperature, IBA concentrations and optimal time for adventitious rooting of Eucalyptus benthamii mini-cuttings

    Institute of Scientific and Technical Information of China (English)

    Gilvano Ebling Brondani; Francisco José Benedini Baccarin; Heron Wilhelmus de Wit Ondas; José Luiz Stape; Antonio Natal Gon(c)alves; Marcilio de Almeida

    2012-01-01

    Eucalyptus benthamii is a forest species of economic interest that has difficulty with seed production and also is considered to have difficulty with adventitious rooting using propagation techniques,such as cutting or mini-cutting.We aimed to assess the adventitious rooting percentage under different storage times in low temperatures and at various IBA (indole-3-butyric acid) concentrations to determine the optimal time of permanence for rooting Eucalyptus benthamii minicuttings in a greenhouse.Shoots collected from mini-stumps cultivated in a semi-hydroponic system were used to obtain the mini-cuttings.For the first experiment,the mini-cuttings were stored at 4℃ for 0 (immediate planting),24,48,72,96 and 120 h.The second experiment evaluated the rooting dynamic to determine the optimal time of permanence for minicuttings in a greenhouse.The basal region of the mini-cutting was treated with various 1BA solutions:0 (free of IBA),1,000,2,000,3,000 and 4,000 mg·L-1.Every seven days (0 (immediate planting),7,14,21 and 28days),destructive sampling of the mini-cuttings was performed to evaluate the histology of the adventitious rooting.Eucalyptus benthamii minicuttings should be rooted immediately after the collection of the shoots.The 2,000 mg·L-1 IBA concentration induced a greater speed and percentage of adventitious rooting,and an interval of 35 to 42 days was indicated for permanence of the mini-cuttings in the greenhouse.Exposure to low temperature induced adventitious root formation with diffuse vascular connections.

  4. Instrument Systems Analysis and Verification Facility (ISAVF) users guide

    Science.gov (United States)

    Davis, J. F.; Thomason, J. O.; Wolfgang, J. L.

    1985-01-01

    The ISAVF facility is primarily an interconnected system of computers, special purpose real time hardware, and associated generalized software systems, which will permit the Instrument System Analysts, Design Engineers and Instrument Scientists, to perform trade off studies, specification development, instrument modeling, and verification of the instrument, hardware performance. It is not the intent of the ISAVF to duplicate or replace existing special purpose facilities such as the Code 710 Optical Laboratories or the Code 750 Test and Evaluation facilities. The ISAVF will provide data acquisition and control services for these facilities, as needed, using remote computer stations attached to the main ISAVF computers via dedicated communication lines.

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

    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 m3 of air over a 24 hour period, this together with IBA's sensitivity means that concentrations down to 1 ng/m3 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

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

    International Nuclear Information System (INIS)

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

  8. Calibration Report for the WRAP Facility Gamma Energy Analysis System

    International Nuclear Information System (INIS)

    The Waste Receiving And Processing facility (WRAP) adheres to providing gamma-ray spectroscopy instrument calibrations traceable to the National Institute for Standards and Technology (NIST) standards. The detectors are used to produce quantitative results for the Waste Isolation Pilot Plant (WIPP) and must meet calibration programmatic calibration goals. Instruments must meet portions of ANSI N42.14, 1978 guide for Germanium detectors. The Non-Destructive Assay (NDA) Gamma Energy Analysis (GEA) utilizes NIST traceable line source standards for the detector system calibrations. The counting configuration is a series of drums containing the line sources and different density filler matrices. The drums are used to develop system efficiencies with respect to density. The efficiency and density correction factors are required for the processing of drummed waste materials of similar densities. The calibration verification is carried out after the calibration is deemed final, by counting a second drum of NIST traceable sources. Three in-depth calibrations have been completed on one of the two systems to date, the first being the system acceptance plan. This report has a secondary function; that being the development of the instrument calibration errors which are to be folded into the Total Instrument Uncertainty document, HNF-4050

  9. Calibration Report for the WRAP Facility Gamma Energy Analysis System

    International Nuclear Information System (INIS)

    The Waste Receiving And Processing facility (WRAP) adheres to providing gamma-ray spectroscopy instrument calibrations traceable to the National Institute for Standards and Technology (NIST) standard(4). The detectors are used to produce quantitative results for the Waste Isolation Pilot Plant (WIPP) and must meet calibration programmatic calibration goals. Instruments must meet portions of ANSI N42.14, 1978 guide for Germanium detectors. The Non-Destructive Assay (NDA) Gamma Energy Analysis (GEA) utilizes NIST traceable line source standards for the detector system calibrations. The counting configuration is a series of drums containing the line sources and different density filler matrices. The drums are used to develop system efficiencies with respect to density. The efficiency and density correction factors are required for the processing of drummed waste materials of similar densities. The calibration verification is carried out after the calibration is deemed final, by counting a second drum of NIST traceable sources. Three in-depth calibrations have been completed on one of the two systems to date, the first being the system acceptance plan. This report has a secondary function; that being the development of the instrument calibration errors which are to be folded into the Total Instrument Uncertainty document, HNF-4050

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

    International Nuclear Information System (INIS)

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

  11. 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.

  12. 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.

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

    Energy Technology Data Exchange (ETDEWEB)

    Burducea, I.; Straticiuc, M. [Horia Hulubei National Institute of Physics and Nuclear Engineering, IFIN-HH, Măgurele 077125 (Romania); Ghiță, D.G., E-mail: dan.ghita@nipne.ro [Horia Hulubei National Institute of Physics and Nuclear Engineering, IFIN-HH, Măgurele 077125 (Romania); Moșu, D.V.; Călinescu, C.I. [Horia Hulubei National Institute of Physics and Nuclear Engineering, IFIN-HH, Măgurele 077125 (Romania); Podaru, N.C.; Mous, D.J.W. [High Voltage Engineering Europa B.V., P.O. Box 99, 3800AB Amersfoort (Netherlands); Ursu, I.; Zamfir, N.V. [Horia Hulubei National Institute of Physics and Nuclear Engineering, IFIN-HH, Măgurele 077125 (Romania)

    2015-09-15

    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{sup −} 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.

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

    International Nuclear Information System (INIS)

    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

  15. 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.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2011-10-10

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

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

    International Nuclear Information System (INIS)

    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

  18. PIXE and ion beam analysis in forensics

    International Nuclear Information System (INIS)

    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)

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

    International Nuclear Information System (INIS)

    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), 11/2 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 11000F is reached

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

  2. IBA e carboidratos no enraizamento de brotações procedentes de estacas radiciais de Rubus Spp.

    OpenAIRE

    João Paulo Tadeu Dias; Elizabeth Orika Ono; João Domingos Rodrigues

    2011-01-01

    Este trabalho objetivou verificar o efeito do ácido indol-3-butírico (IBA) e o teor de carboidratos na promoção do enraizamento em estacas de brotações de amoreira-preta. O experimento foi conduzido de junho a agosto de 2010, na UNESP de Botucatu - SP, sendo o delineamento em blocos casualizados, com seis concentrações de IBA e seis repetições, com a parcela constituída por 12 brotações. Os tratamentos constaram de seis concentrações de IBA, na forma de solução: T1= 0 mg L-1; T2= 250 mg L-1; ...

  3. GAS MIXING ANALYSIS IN A LARGE-SCALED SALTSTONE FACILITY

    Energy Technology Data Exchange (ETDEWEB)

    Lee, S

    2008-05-28

    Computational fluid dynamics (CFD) methods have been used to estimate the flow patterns mainly driven by temperature gradients inside vapor space in a large-scaled Saltstone vault facility at Savannah River site (SRS). The purpose of this work is to examine the gas motions inside the vapor space under the current vault configurations by taking a three-dimensional transient momentum-energy coupled approach for the vapor space domain of the vault. The modeling calculations were based on prototypic vault geometry and expected normal operating conditions as defined by Waste Solidification Engineering. The modeling analysis was focused on the air flow patterns near the ventilated corner zones of the vapor space inside the Saltstone vault. The turbulence behavior and natural convection mechanism used in the present model were benchmarked against the literature information and theoretical results. The verified model was applied to the Saltstone vault geometry for the transient assessment of the air flow patterns inside the vapor space of the vault region using the potential operating conditions. The baseline model considered two cases for the estimations of the flow patterns within the vapor space. One is the reference nominal case. The other is for the negative temperature gradient between the roof inner and top grout surface temperatures intended for the potential bounding condition. The flow patterns of the vapor space calculated by the CFD model demonstrate that the ambient air comes into the vapor space of the vault through the lower-end ventilation hole, and it gets heated up by the Benard-cell type circulation before leaving the vault via the higher-end ventilation hole. The calculated results are consistent with the literature information. Detailed results and the cases considered in the calculations will be discussed here.

  4. Safety analysis of the Los Alamos critical experiments facility

    International Nuclear Information System (INIS)

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

  5. 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.

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

    Energy Technology Data Exchange (ETDEWEB)

    MELOY, R.T.

    2002-04-01

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

  7. Modeling and analysis of inertial-confinement-fusion facilities

    International Nuclear Information System (INIS)

    Approximate analytic models are used to explore relations among technical and economic characteristics of Inertial Confinement Fusion (ICF) facilities. Presented are attainable pulse rates for different reactor cavities and dependencies of the unit production cost of electricity on ICF driver pulse energy and repetition rate and on the facility size and the performance of the driver-pellet combination. The results indicate that economic electricity production with ICF reactors may require repetition rates of approx. 15 Hz or 20 Hz but that it may be achieved with values of the driver efficiency-pellet gain product as low as approx. 3 or 4

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

    International Nuclear Information System (INIS)

    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)

  9. Higher Education Facilities Systems Building Analysis. Summary Report.

    Science.gov (United States)

    Texas A and M Univ., College Station. Coll. of Architecture and Environmental Design.

    This document is an extract of EA 004 095 which reports a yearlong study of possible benefits in cost, time, and facility utilization of a systems building approach for Texas college and university construction. (Photographs on pages 7,8,9, and 13 may reproduce poorly.) (Author)

  10. Higher Education Facilities: Systems Building Analysis. Documentary Work Report.

    Science.gov (United States)

    Trost, F. J.

    This document reports a yearlong study of possible benefits in cost, time, and facility utilization of a systems building approach for Texas college and university construction. The first part of the report deals with trends and needs in higher education and the related architectural implications. A subsequent discussion of alternative building…

  11. GRB 021219: the first Gamma-Ray Burst localized in real time with IBAS

    CERN Document Server

    Mereghetti, S; Beckmann, V; Von Kienlin, A; Ubertini, P; Bazzano, A; Foschini, L; Malaguti, G

    2003-01-01

    On December 19, 2002, during the Performance and Verification Phase of INTEGRAL, a Gamma-Ray Burst (GRB) has been detected and localized in real time with the INTEGRAL Burst Alert System (IBAS). Here we present the results obtained with the IBIS and SPI instruments. The burst had a time profile with a single peak lasting about 6 s. The peak spectrum can be described by a single power law with photon index $\\Gamma$=1.6$\\pm$0.1 and flux $\\sim$3.7 photons cm$^{-2}$ s$^{-1}$ (20 - 200 keV). The fluence in the same energy range is 9$\\times10^{-7}$ erg cm$^{-2}$. Time resolved spectroscopy performed with IBIS/ISGRI shows a clear hard to soft evolution of the spectrum.

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

    International Nuclear Information System (INIS)

    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

  13. 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.

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

    International Nuclear Information System (INIS)

    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

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

    Institute of Scientific and Technical Information of China (English)

    2011-01-01

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

  16. 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.

  17. 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.

  18. Ion beams and material science facilities using high current low energy 3.0 MV particle accelerator at NCAR, Bilaspur

    International Nuclear Information System (INIS)

    The national facility for interdisciplinary research using ion beams based on 3.0 MV Pelletron accelerator (9SDH, NEC) with high current TORVIS (for H, He ions) and SNICS (for heavy ions) sources, and two beam lines for ion beam analysis (IBA) and ion implantation/irradiation have been successfully commissioned at NCAR, Department of Pure and Applied Physics, Guru Ghasidas Vishwavidyalaya, Bilaspur. The accelerator conditioning was done over a period of time to achieve desired level of terminal voltage and vacuum in the accelerator tank, 3.0 MV terminal voltage was achieved with chain currents 120 A and an applied charging voltage of 13 kV. The vacuum without beam acceleration was lower 10-8 torr on both sides of the Pelletron tank. Finally, the first beam demonstration was achieved when a proton beam accelerated with terminal potential of 0.965 MV was seen at the Au target in Ion Beam analysis (IBA) chamber, the energy at the Faraday cup (FC) just before the chamber was 0.5 eA. Details of the facilities tested and the results obtained so far will be discussed in the paper

  19. 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.

  20. Preclosure radiological safety analysis for the exploratory shaft facilities

    International Nuclear Information System (INIS)

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2012-08-01

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

  2. Beam positioning stability analysis on large laser facilities

    Institute of Scientific and Technical Information of China (English)

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

    2013-01-01

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

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

    International Nuclear Information System (INIS)

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

  4. Analysis for cover design of a near surface disposal facility

    International Nuclear Information System (INIS)

    Model Simulation based on NETEC concept design of disposal facility was performed by using HELP Code and the infiltration rate through cover system was estimated with method of water budget. The final leakage through bottom of bentonite mixed layer estimated lower than 1.0mm/year. But long term integrity of geomembrane and asphalt as engineered barrier is not guaranteed yet. So assuming that these two barrier lost their function, the final leakage will be increased to 35 mm/year

  5. Lunar Mission Analysis for a Wallops Flight Facility Launch

    OpenAIRE

    Dolan, John Martin

    2008-01-01

    Recently there is an increase in interest in the Moon as a destination for space missions. This increased interest is in the composition and geography of the Moon as well as using the Moon to travel beyond the Earth to other planets in the solar system. This thesis explores the mechanics behind a lunar mission and the costs and benefits of different approaches. To constrain this problem, the launch criteria are those of Wallops Flight Facility (WFF), which has expressed interest in launching...

  6. BUDAPEST, BRATISLAVA AND VIENNA CONFERENCE FACILITIES, COMPARATIVE ANALYSIS

    OpenAIRE

    Endre György Bártfai

    2011-01-01

    The aim of this study is to give an overview of conference facilities in three capital cities in the Central European area, along the Danube, analyse and compare their possibilities and venues. The utilized data within the study was collected from different sources, like websites of the Hungarian, Slovakian and Austrian Convention Bureaus, books dealing with convention and event management and statistics, ICCA publications. Budapest is highly ranked between cities transacting conferences for ...

  7. Experimental facility for analysis of biomass combustion characteristics

    Directory of Open Access Journals (Sweden)

    Miljković Biljana M.

    2015-01-01

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

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

    This document provides information on waste management practices, occupational safety, and a site characterization of the Lawrence Livermore National Laboratory. A facility description, safety engineering analysis, mixed waste processing techniques, and auxiliary support systems are included

  10. 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.

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

    Energy Technology Data Exchange (ETDEWEB)

    Gmuer, N.F.; Thomlinson, W.

    1990-02-01

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

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

    OpenAIRE

    Govindasamy, Ramu; Nayga, Rodolfo M.

    1997-01-01

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

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

    OpenAIRE

    Ibrahim, Imtiaz

    2012-01-01

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

  14. Development of boron concentration analysis system and techniques for testing performance of BNCT facility

    Energy Technology Data Exchange (ETDEWEB)

    Choi, Hee Dong; Kim, Chang Shuk; Byun, Soo Hyun; Lee, Jae Yun; Sun, Gwang Min; Kim, Suk Kwon [Seoul National University, (Korea)

    2000-04-01

    I. Objectives and Necessity of the Project. Development of a boron concentration analysis system used for BNCT. Development of test techniques for BNCT facility. II. Contents and Scopes of the Project. (1) Design of a boron concentration analysis system at HANARO. (2) Component machining and instruments purchase, performance test. (3) Calculation and measurement of diffracted polychromatic beam quality. (4) Test procedures for boron concentration analysis system and BNCT facility. III. Result of the Project (1) Diffracted neutron beam quality for boron concentration analysis. (neutron flux: 1.2 * 10{sup 8} n/cm{sup 2}s, Cd-ratio : 1,600) (2) Components and instruments of the boron concentration analysis system. (3) Diffracted neutron spectrum and flux. (4) Test procedures for boron concentration analysis system and BNCT facility. 69 refs., 44 figs., 14 tabs. (Author)

  15. Thermal performance analysis of an MHD simulation test facility

    International Nuclear Information System (INIS)

    To evaluate the performance of the downstream components of a coal-fired, baseline, open cycle MHD power plant, Mississippi State University has set up a simulation test facility. Reduced thermal data from this test stand for steady-state operating conditions are presented in the paper. A thermal model to predict the variation of important thermal parameters in the test stand is shown. Results from the reduced experimental data and the predictive thermal model are compared. In addition, results for calibration runs and from recent secondary combustion tests are discussed. 7 refs

  16. Seismic fragility analysis of structural components for HFBR facilities

    International Nuclear Information System (INIS)

    The paper presents a summary of recently completed seismic fragility analyses of the HFBR facilities. Based on a detailed review of past PRA studies, various refinements were made regarding the strength and ductility evaluation of structural components. Available laboratory test data were analysed to evaluate the formulations used to predict the ultimate strength and deformation capacities of steel, reinforced concrete and masonry structures. The biasness and uncertainties were evaluated within the framework of the fragility evaluation methods widely accepted in the nuclear industry. A few examples of fragility calculations are also included to illustrate the use of the presented formulations

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

    International Nuclear Information System (INIS)

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

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

    DEFF Research Database (Denmark)

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

    2015-01-01

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

  19. Decision support and analysis tool for planning in a semiconductor manufacturing facility

    Science.gov (United States)

    Fargher, Hugh E.; Smith, Richard A.

    1994-03-01

    As part of the recently completed Microelectronics Manufacturing Science and Technology (MMST) project, a decision support and analysis tool for planning in a semiconductor manufacturing facility has been developed. Design of the planning system uses an object- oriented approach, and implementation is performed in the Smalltalk programming environment. The system continually maintains a plan for wafer release into a facility, and predicts processing completion dates. The system has been built to run in a distributed environment, allowing simultaneous users in different parts of the facility. The system also provides several types of what-if analysis, both on the existing production plan and on production data. Production plan analysis is used to assist in making operational decisions related to the facility in its current state, such as determining the least disruptive time to take a piece of equipment down for maintenance. Production data analysis, which can be performed independent of the production plan, determines information such as equipment throughput rates to achieve given product cycle-times. All planning is performed using artificial intelligence search techniques, and is based on a time-phased capacity model of the facility. Uncertainty inherent in production data, such as cycle-times, is modeled using fuzzy arithmetic. This tool was used during the final 1000 wafer demonstration for MMST, and is currently being installed in other semiconductor manufacturing facilities. This paper describes the main goals of the planning system, the overall approach to planning and analysis, and a brief description of the current status.

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

    International Nuclear Information System (INIS)

    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.)

  1. Bubble-condenser experimental qualification at EREC test facility. Analysis with ATHLET code

    International Nuclear Information System (INIS)

    In the framework of PHARE/TACIS project No. PH 2.13/95 the experimental test facility for bubble condenser experimental qualification is under construction at Electrogorsk Research and Engineering Centre. The test facility will contain high pressure system, compartments upstream of the bubble condenser and a section of the bubble condenser system. The scaling of the test facility is 1:100. The high pressure system consists of five vessels to appropriately model the leak functions (mass flow rate and enthalpy) during the loss of coolant accidents postulated in the design of VVER-440/V213. Pre-test analysis has been carried out with ATHLET code in order to properly design the high pressure system of the test facility. ATHLET code was applied to the NPP and to the test facility configuration and for both geometries the selected accidents were calculated. (author)

  2. 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.

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

    International Nuclear Information System (INIS)

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

  4. Battery Test Facility- Electrochemical Analysis and Diagnostics Laboratory

    Data.gov (United States)

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

  5. Analysis of RA-8 critical facility core in some configurations

    International Nuclear Information System (INIS)

    The RA-8 critical facility was designated and built to be used in the experimental plan of the 'CAREM' Project but is, in itself, very versatile and adequate to perform many types of other experiments. The present paper includes calculated estimates of some critical configurations and comparisons with experimental results obtained during its start up. Results for Core 1 with homogeneous arrangement of rods containing 1.8 % enriched uranium, showed very good agreement. In fact, an experimentally critical configuration was reached with 1.300 rods and calculated values were: 1.310 using the WIMS code and 1.148 from the CONDOR code. Moreover, it was verified that the estimated number of 3.4% enriched uranium rods to be fabricated is enough to build a heterogeneous core or even a homogeneous core with this enrichment. The replacement of 3.4 % enriched uranium by 3.6 % will not present problems related with the original plan. (author)

  6. 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.

  7. Improved Methodology Application for 12-Rad Analysis in a Shielded Facility at SRS

    International Nuclear Information System (INIS)

    The DOE Order 420.1 requires establishing 12-rad evacuation zone boundaries and installing Criticality Accident Alarm System (CAAS) per ANS-8.3 standard for facilities having a probability of criticality greater than 10-6 per year. The H-Canyon at the Savannah River Site (SRS) is one of the reprocessing facilities where SRS reactor fuels, research reactor fuels, and other fissile materials are processed and purified using a modified Purex process called H-Modified or HM Process. This paper discusses an improved methodology for 12-rad zone analysis and its implementation within this large shielded facility that has a large variety of criticality sources and scenarios

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

    International Nuclear Information System (INIS)

    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

  9. The role of neutron activation analysis technique Ex Industrial applications using the egyptian research reactor facilities

    International Nuclear Information System (INIS)

    This report covers several papers which deal with the industrial applications of the Neutron Activation Analysis Technique (NAAT) in Egypt. The applications include: exploration, mining, industrial environment and multielemental analysis of different materials, just for quality control, optimization, safety uses and help in improving the efficiency and economic evaluation. The technique principles, instrumentation, neutron irradiation facilities and experience of analysis are reviewed. Also, the current research activities using the ET-RR-1 facilities as well as a proposal for cold neutron applications in this field on the ET-RR-2 are given

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

    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

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

    OpenAIRE

    Brooks, Derek

    2014-01-01

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

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

    OpenAIRE

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

    2008-01-01

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

  14. 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.

  15. Analysis of marketing communications in the selected accommodation facilities

    OpenAIRE

    UHROVÁ, Pavlína

    2010-01-01

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

  16. Analysis of Operational and Management Cybersecurity Controls for Nuclear Facilities

    International Nuclear Information System (INIS)

    U.S. NRC developed this RG 5.71 by tailoring the baseline security controls described in NIST Special Publication 800-53 'Recommended Security Controls for Federal Information Systems and Organizations' to provide an acceptable method to comply with the 10 CFR 73.54. The purpose of this publication is to provide guidelines for selecting and specifying security controls for information systems. In this paper, we are going to analyze and compare the NRC RG 5.71 and the NIST SP800-53, in particular, for operational security controls and management security controls. If RG 5.71 omits the specific security control that is included in SP800-53, we would review that omitting is adequate or not. If RG 5.71 includes the specific security control that is not included in SP800-53, we would also review the rationale. And we are going to consider some security controls to strengthen cybersecurity of nuclear facilities

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

    International Nuclear Information System (INIS)

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

  18. 77 FR 48107 - Workshop on Performance Assessments of Near-Surface Disposal Facilities: FEPs Analysis, Scenario...

    Science.gov (United States)

    2012-08-13

    ...-Surface Disposal Facilities: FEPs Analysis, Scenario and Conceptual Model Development, and Code Selection... Radioactive Waste.'' These regulations were published in the Federal Register on December 27, 1982 (47 FR... on three aspects of a performance assessment: (1) Features, Events, and Processes (FEPs) analysis,...

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

    International Nuclear Information System (INIS)

    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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2010-07-01

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

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

    International Nuclear Information System (INIS)

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

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

    CERN Document Server

    Courtois, C; Brusasco, C; Colin, J; Cussol, D; Fontbonne, J M; Marchand, B; Mertens, T; De Neuter, S; Peronnel, J

    2013-01-01

    Every radiotherapy center has to be equipped with real-time beam monitoring devices. In 2008, the medical application group from the Laboratory of Corpuscular Physics (LPC Caen) developed an Ionization Chamber in collaboration with the company IBA (Ion Beam Applications). This monitoring device called IC2/3 was developed to be used in IBAs universal irradiation head for Pencil Beam Scanning (PBS). The objectives presented in this article are to characterize the IC2/3 monitor in the energy and ux ranges used in protontherapy. The equipment has been tested with an IBAs cyclotronable 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 initials speci cations needed for PBS purposes. The detector measures the dose with a relative precision better than 1% in the rang...

  3. ENRAIZAMENTO DE MELALEUCA: INFLUÊNCIA DA ALTURA DE COLETA DAS ESTACAS E APLICAÇÃO DE IBA

    Directory of Open Access Journals (Sweden)

    Carlos André Stuepp

    2013-06-01

    Full Text Available Melaleuca alternifolia Cheel is an economically important medicinal plant. Its chemical constitution is well known, being rich in terpinen-4-ol, which is the main responsible for its medicinal properties. However, in this species is difficult to obtain good seedlings from seed germination, what makes the vegetative propagation benefic to its commercialization, maintaining the productive characteristics and quality of extracted oil. This study aimed to evaluate the rooting of tea tree cuttings, collected in the apical, middle and basal portions of the stock plant branches, and treated with different concentrations of indolebutyric acid (IBA. Cuttings with a length of 6 cm, with one third of the apex leaves and a bevel cutting on the base, were treated with hydroalcoholic solutions of IBA (0, 1500 and 3000 mg L-1 immersing the base for 10 seconds. In the sequence cuttings were planted in tubes containing vermiculite and placed in a greenhouse. After 91 days, the rooting percentage, number of roots, average length of roots, callus percentage, survival and mortality were evaluated. Percentage of rooting cuttings was less than 43.8%, and it was not influenced by the branch type or by tested IBA concentrations.

  4. Acquisition Path Analysis for a SFR Fuel Manufacturing Facility

    Energy Technology Data Exchange (ETDEWEB)

    Chang, H. L.; Kwon, E. H.; Ahn, S. K.; Ko, W. I.; Kim, H. D. [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2014-05-15

    The coarse acquisition path analysis does not claim to be complete, but it identifies plausible acquisition paths detailed enough to show that the acquisition path analysis can provide reasonable insights regarding the safeguardability assessment, and demonstrates the availability of safeguards tools and measures, although not complete, required for the implementation of effective and efficient safeguards, including the coverage of the nuclear energy system (NES) by multiple intrinsic features and extrinsic measures. It also identifies strengths, weaknesses and gaps of a system in the area of proliferation resistance in a generally understandable form. The acquisition path analysis demonstrates that all acceptance limits for the safeguardability, in principle, are met although the acceptance limit for the efficiency of the IAEA safeguards can be answered only at the end of the Safeguards-by-Design process, including interaction with IAEA operations. However, procedures for destructive assay (DA) for the verification by the IAEA are not defined. Target values for non-destructive assay (NDA) for this type of nuclear material are also not defined. Therefore, there is a need to finish demonstrations of NDA measurements on novel material types and material flows. The acquisition path analysis also shows some concerns that need to be assured in the system design process: e. g., the ID number of all storage containers in all storage positions can be read or checked without moving the storage container, transfer of TRU fuel and heel/scrap (product stream) should be strictly separated from transfer routes for waste, to make the transfer of TRU fuel and heel/scrap into waste container impossible, etc.

  5. Software for a measuring facility for activation analysis

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

  7. 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.

  8. CFB gasification of biomass. An analysis of available and necessary research facilities

    International Nuclear Information System (INIS)

    The aim of the title analysis is to inventorize the required and available Dutch laboratory facilities for research on Circulating Fluidized Beds (CFB) gasification of biomass. A literature study has been carried to assess the international state-of-the-art of the technology and research. Based on the results the required research facilities could be determined. Next, interviews were held with researchers at relevant Dutch research institutes and information was collected to compile an overview of available Dutch facilities. It appears that the introduction of CFB gasification technologies can take place under good conditions, although coordination of future research activities is desired, while knowledge and facilities are spread over several research institutes. 16 figs., 43 refs., 1 appendix

  9. 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.

  10. 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.

  11. Safety analysis report for the 238PuO2 fuel form facility

    International Nuclear Information System (INIS)

    The Plutonium Fuel Form (PuFF) Facility has been constructed at the Savannah River Plant to manufacture 30 to 60 kg/yr of 238Pu fuel forms for space power applications. This facility is located in the existing Building 235-F near the geographical center of the Savannah River Plant (SRP) site. Pilot production is scheduled to begin in July 1977, with full-scale production in April 1978. The process line of the facility consists of nine separate, interconnected shielded cells; five shielded wing cabinets or glove boxes; three hoods; and contained auxiliary equipment. These process enclosures will be, for the most part, under an atmosphere of recirculating inert gas. The products of the facility will be dense fuel forms manufactured from PuO2 powder with a nominal isotopic composition of 80% 238Pu-20% 239Pu. This powder, made from calcined oxalate, has been produced safely at a rate of about 20 kg 238Pu/yr in the H-Area B-Line in Building 221-H for approximately ten years. This report describes design objectives, nature of operations, potential hazards and limiting factors, facility response to postulated accidents and failures, and environmental effects. The results of the analyses described in this report indicate that the facility has the capacity to prevent or sufficiently reduce accidents that represent potential risks to health and safety. The safety analysis in conjunction with process requirements provides the bases for Technical Standards for operation. The analysis also documents the degree of conformance of the facility design with the General Design Criteria - Plutonium Facilities and the Environmental Statement

  12. Criticality safety analysis of WWER spent fuel facilities

    International Nuclear Information System (INIS)

    Criticality safety analysis of the WWER transport casks as well as of WWER wet spent fuel storage at the Kozloduy NPP site is performed under conservative assumptions. For criticality calculations the methodology based on the modular code system SCALE4.4 and MCNP code has been applied. The criticality parameters for WWER-440 and WWER-1000 transport casks, and for WWER wet spent fuel storage have been calculated by SCALE. The verification of the results has been carried out based on the comparison with the MCNP results. This comparison shows good coincidence of the results, calculated by SCALE and MCNP, in the uncertainty margins. The results presented lead to the conclusion that the criticality safety criteria Keff<0.95 for WWER transport casks and WWER wet spent fuel storage are satisfied quite well under conservative assumptions

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

    International Nuclear Information System (INIS)

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

  14. Computational Tools and Facilities for the Next-Generation Analysis and Design Environment

    Science.gov (United States)

    Noor, Ahmed K. (Compiler); Malone, John B. (Compiler)

    1997-01-01

    This document contains presentations from the joint UVA/NASA Workshop on Computational Tools and Facilities for the Next-Generation Analysis and Design Environment held at the Virginia Consortium of Engineering and Science Universities in Hampton, Virginia on September 17-18, 1996. The presentations focused on the computational tools and facilities for analysis and design of engineering systems, including, real-time simulations, immersive systems, collaborative engineering environment, Web-based tools and interactive media for technical training. Workshop attendees represented NASA, commercial software developers, the aerospace industry, government labs, and academia. The workshop objectives were to assess the level of maturity of a number of computational tools and facilities and their potential for application to the next-generation integrated design environment.

  15. Who Enters Campus Recreation Facilities: A Demographic Analysis

    Directory of Open Access Journals (Sweden)

    Paul Rohe Milton

    2011-06-01

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

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

    CERN Document Server

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

    2008-01-01

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

  17. 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.

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

    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

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

    International Nuclear Information System (INIS)

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

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

    Science.gov (United States)

    Congiardo, Jared F.

    2007-01-01

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

  3. 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.

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

    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 3.9x1013-1.6x1014 n/cm2·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)

  9. 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

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

    International Nuclear Information System (INIS)

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

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

    Energy Technology Data Exchange (ETDEWEB)

    BISHOP, G.E.

    2000-04-04

    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.

  12. Coopération Sud-Sud et lutte contre la pauvreté : le cas du forum IBAS (South-South Cooperation and the Fight against Poverty: The Case of the IBAS Forum

    Directory of Open Access Journals (Sweden)

    Folashadé A. Soulé-Kohndou

    2012-01-01

    Full Text Available Malgré la montée en puissance de l'Inde, du Brésil et de l'Afrique du Sud sur la scène internationale, et de leur catégorisation comme puissances émergentes, la lutte contre la pauvreté reste une priorité nationale dans chacun de ces pays. Dans ce cadre, plusieurs politiques et initiatives sont mises en oeuvre à la fois au niveau national et international : le forum IBSA qui regroupe ces trois émergents en est un exemple. Né en 2003, cette nouvelle coopération Sud-Sud (Inde, Brésil, Afrique du Sud se fait le relais des priorités nationales et des intérêts communs de ses membres pour la résorption de la pauvreté au niveau interne mais aussi international. Leur coopération passe par des échanges trilatéraux et la conduite de projets de développement communs dans d'autres pays en développement via le fonds IBAS pour la lutte contre la faim et la pauvreté. Malgré ses limites, elle participe à l'affirmation et à la quête d'autonomie et à la légitimation de ses membres comme nouvelles puissances.(Despite the increasing power of India, Brazil and South Africa on the international scene and their categorization as emerging powers, the fight against poverty remains a national priority in all three countries. Several policies and initiatives have been put in place at the national and international level simultaneously: the IBAS forum which unites the three is one example. Created in 2003, this new South-South cooperation (India, Brazil, South Africa links national priorities with the common interests of its members to reduce poverty at the national and international level. Cooperation includes trilateral trade and jointly managing development projects in other developing countries via IBAS poverty and hunger reduction funds. Despite its limitations, the IBAS forum contributes to the legitimization of its members as new global powers.

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

    International Nuclear Information System (INIS)

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

  14. Pre-test analysis for the KNGR DVI performance test facility using FLUENT

    International Nuclear Information System (INIS)

    Pre-test analysis using a FLUENT code has been performed for the KGNR(Korean Next Generation Reactor) DVI(Direct Vessel Injection) performance test facility which is a full height and 1/24.3 volume scaled separate effect test facility. The ideal gas discharge condition is considered to simulation a steam discharge condition. The scale effects on the flow pattern, pressure distribution, and similarity for scaled model are numerically tested. From the various results for the scale effects, it was found that the similarity of hydraulics is founded

  15. IBA techniques: Examples of useful combinations for the characterisation of cultural heritage materials

    International Nuclear Information System (INIS)

    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.

  16. IBA techniques: Examples of useful combinations for the characterisation of cultural heritage materials

    Energy Technology Data Exchange (ETDEWEB)

    Beck, L., E-mail: lucile.beck@cea.fr [Centre de Recherche et de Restauration des Musees de France (C2RMF), CNRS-UMR 171, Palais du Louvre, 14 quai Francois Mitterrand, 75001 Paris (France); INSTN, CEA Saclay, 91120 Gif sur Yvette (France); Pichon, L.; Moignard, B.; Guillou, T.; Walter, P. [Centre de Recherche et de Restauration des Musees de France (C2RMF), CNRS-UMR 171, Palais du Louvre, 14 quai Francois Mitterrand, 75001 Paris (France)

    2011-12-15

    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 (Accelerateur Grand Louvre d'Analyse Elementaire) 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.

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

    International Nuclear Information System (INIS)

    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

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

    International Nuclear Information System (INIS)

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

  19. 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.

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

    International Nuclear Information System (INIS)

    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)

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

    International Nuclear Information System (INIS)

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

  2. 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.

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

    Energy Technology Data Exchange (ETDEWEB)

    Lancker, Marc van E-mail: vanlancker@iba.be; Herer, Arnold; Cleland, Marshall R.; Jongen, Yves; Abs, Michel

    1999-05-02

    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.

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

    International Nuclear Information System (INIS)

    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

  5. Mode of action of metabolites from Bacillus sp. strain IBA 33 on Geotrichum citri-aurantii arthroconidia.

    Science.gov (United States)

    Gordillo, María Antonieta; Navarro, Antonio R; Maldonado, María Cristina

    2015-11-01

    Geotrichum citri-aurantii is a postharvest phytopathogenic fungus of lemons. We studied the mode of action of antifungal metabolites from Bacillus sp. strain IBA 33 on arthroconidia of G. citri-aurantii. These metabolites are lipopeptides belonging to the iturin family. Membrane permeabilization of G. citri-aurantii was analyzed and mitochondrial respiratory rate was evaluated. Disturbance of the plasma membrane promotes the leakage of many cellular components into the surrounding media, and mitochondrial membrane disorganization promotes the inhibition of the respiratory rate. Our findings provide insights into the ability of lipopeptides to suppress plant fungal pathogens and their possible agronomical applications. PMID:26394707

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

    International Nuclear Information System (INIS)

    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)

  7. Do provisions to advance chemical facility safety also advance chemical facility security? An analysis of possible synergies

    DEFF Research Database (Denmark)

    Hedlund, Frank Huess

    The European Commission has launched a study on the applicability of existing chemical industry safety provisions to enhancing security of chemical facilities covering the situation in 18 EU Member States. This paper reports some preliminary analytical findings regarding the extent to which...... exist at the mitigation level. At the strategic policy level, synergies are obvious. The security of chemical facilities is important. First, facilities with large inventories of toxic materials could be attractive targets for terrorists. The concern is sabotage causing an intentional release that could...

  8. Using uncertainty analysis to guide and evaluate modifications of a boundary layer heat transfer test facility

    International Nuclear Information System (INIS)

    A case study is presented on the use of uncertainty analysis to guide the modification of an existing, mature experimental facility with well known characteristics and to insure that the results obtained with the modified facility will meet the new requirements. The existing facility's test surface was composed of 24 individually heated 0.1 m wide test plates. This facility was to be used to conduct a set of experiments to investigate the effect of a step change in surface roughness from a rough to a smooth surface on the heat transfer in the turbulent boundary layer. Of particular interest was the Stanton number distribution immediately downstream of the rough-to-smooth interface. The existing 0.1 m wide test plates could not provide the desired resolution; so, narrower plates were needed in this region. Unfortunately as the plates are made narrower, the uncertainty in Stanton number becomes larger. This paper presents and discusses the use of uncertainty analysis to guide this modification, to set up the experimental procedures and test limits, and to reduce the actual data. Sample Stanton number results are included

  9. Development of environmental sample analysis technique in KAERI. Bulk analysis and establishment of clean laboratory facility (CLASS)

    International Nuclear Information System (INIS)

    The development of analytical methods for environmental samples in Korea Atomic Energy Research Institute (KAERI) is discussed. An analysis scheme for environmental samples has been established with an MCICP-MS based bulk analysis with adopting UTEVA resin for chemical separation and a particle analysis using FTTIMS and SIMS. A clean laboratory facility called CLASS (class 100∼ class 1000) was also established in order to prevent any cross contamination of the samples. The amount of U and Pu in the process blank sample prepared in the CLASS facility was estimated as 20 pg and less than 0.005 pg, respectively. The control chart of the analytical performance for the uranium standard sample of 100 ppt (NBL U030) indicated that the analytical performance of KAERI in CLASS is within 5 % of the certified values. (author)

  10. IMPACT OF CASE STUDY METHOD OF TEACHING ON THE JOB PERFORMANCE OF BUSINESS GRADUATES, IN THE CASE OF BUSINESS ADMINISTRATION DEPARTMENT IBA-UNIVERSITY OF SINDH-JAMSHORO

    Directory of Open Access Journals (Sweden)

    Anwar Ali Shah G.Syed

    2011-09-01

    Full Text Available The study was conducted on business graduates of IBA-University of Sindh-Jamshoro. A complementary survey was conducted from 50 organizations in Sindh province by using simple random technique, and 200 sample size were selected from student data set. The results showed that case analysis method increasing the vision and understanding the subject as well as practical exposure of the different organizations and it also impact on the personal development of the student when they are solving they different cases in different situations for firm or organization. From last couple of years this method is pretty popular among the students, and they applied all the case studies in local environment and teachers are importing the quality of the education by employing different case studies and their practical touches of different cases. It also helps the graduates when they are going for the jobs, and it has the positive relationship with the job performance. Case studies improving the vision of the business students.

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

    International Nuclear Information System (INIS)

    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

  12. Documented Safety Analysis Addendum for the Neutron Radiography Reactor Facility Core Conversion

    Energy Technology Data Exchange (ETDEWEB)

    Boyd D. Christensen

    2009-05-01

    The Neutron Radiography Reactor Facility (NRAD) is a Training, Research, Isotope Production, General Atomics (TRIGA) reactor which was installed in the Idaho National Laboratory (INL) Hot Fuels Examination Facility (HFEF) at the Materials and Fuels Complex (MFC) in the mid 1970s. The facility provides researchers the capability to examine both irradiated and non-irradiated materials in support of reactor fuel and components programs through non-destructive neutron radiography examination. The facility has been used in the past as one facet of a suite of reactor fuels and component examination facilities available to researchers at the INL and throughout the DOE complex. The facility has also served various commercial research activities in addition to the DOE research and development support. The reactor was initially constructed using Fuel Lifetime Improvement Program (FLIP)- type highly enriched uranium (HEU) fuel obtained from the dismantled Puerto Rico Nuclear Center (PRNC) reactor. In accordance with international non-proliferation agreements, the NRAD core will be converted to a low enriched uranium (LEU) fuel and will continue to utilize the PRNC control rods, control rod drives, startup source, and instrument console as was previously used with the HEU core. The existing NRAD Safety Analysis Report (SAR) was created and maintained in the preferred format of the day, combining sections of both DOE-STD-3009 and Nuclear Regulatory Commission Regulatory Guide 1.70. An addendum was developed to cover the refueling and reactor operation with the LEU core. This addendum follows the existing SAR format combining required formats from both the DOE and NRC. This paper discusses the project to successfully write a compliant and approved addendum to the existing safety basis documents.

  13. 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.

  14. Determining Rooting Ability of Ennobled Blueberry Wood Pieces (Vaccinium corymbosum L. with Presence of Growth Regulators IBA and NAA

    Directory of Open Access Journals (Sweden)

    SABRI BRAHA

    2015-12-01

    Full Text Available Ennobled blueberry (V. Corymbosum L. has many specific requirements for optimal growth, therefore, the increase of cultivated areas is limited. It requires acidic soils (pH 4,3-4,8, well drained, with full aeration and a constant moderate amount of moisture. The successful technique of asexual propagation will be necessary for rapid clonal propagation of selected cultivars. The objective of this experiment was to identify an efficient way to improve rooting with the help of growth regulators in the ‘Bluecrop’ cultivar using well-lignified one-year old wood pieces, collected at the end of winter, end of March prior to bud swelling. Treatments with various concentrations (1500, 3000, 4500 mg/l, show that treatment with IBA at 3000 mg/l has the highest rooting percentage in comparison to NAA. Whilst the torf-perlite substrate (at a 2:1 ratio, has produced a higher rooting percentage compared to the torf-only substrate, and the crucial factor for successful rooting is the time of collecting wood pieces. Treatment results have promoted higher rooting of wooden pieces compared to the control (untreated wooden pieces. The most efficient promotor in all concentrations was IBA.

  15. Tritium Facility effluent measurements: statistical analysis for 52 periods in 1981

    International Nuclear Information System (INIS)

    A statistical comparison has been made of Tritium Facility effluents for 52 periods in 1981, as measured by continuous sampling from two ventilation exhaust stacks. Pulse-counter data, recorded on 15-minute intervals, have been summed over approximately weekly periods and compared with adsorption apparatus data. A by-product of the analysis is a calibration of pulse counters in terms of adsorption data which are believed to be more reliable

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

    International Nuclear Information System (INIS)

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

  17. 200 Area Treated Effluent Disposal Facility (TEDF) Effluent Sampling and Analysis Plan

    Energy Technology Data Exchange (ETDEWEB)

    BROWN, M.J.

    2000-05-18

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

  18. Fermilab Central Computing Facility: Energy conservation report and mechanical systems design optimization and cost analysis study

    Energy Technology Data Exchange (ETDEWEB)

    Krstulovich, S.F.

    1986-11-12

    This report is developed as part of the Fermilab Central Computing Facility Project Title II Design Documentation Update under the provisions of DOE Document 6430.1, Chapter XIII-21, Section 14, paragraph a. As such, it concentrates primarily on HVAC mechanical systems design optimization and cost analysis and should be considered as a supplement to the Title I Design Report date March 1986 wherein energy related issues are discussed pertaining to building envelope and orientation as well as electrical systems design.

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

    Science.gov (United States)

    Vroman, G. A.

    1974-01-01

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

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

    International Nuclear Information System (INIS)

    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 UO2 fuel fabrication facility

  1. The Prompt Gamma Neutron Activation Analysis Facility at ICN—Pitesti

    Science.gov (United States)

    Bǎrbos, D.; Pǎunoiu, C.; Mladin, M.; Cosma, C.

    2008-08-01

    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 performace of INAA method. A facility has been developed at Institute for Nuclear Research—Piteşti 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: φscd = 1.106 n/cm2/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° 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.

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

    Science.gov (United States)

    Haupt, Andreas; Kemp, Yves; Nowak, Friederike

    2014-06-01

    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.

  3. 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.

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

    Science.gov (United States)

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

    2015-12-01

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

  5. High level process shielded line (CBP) and high level analysis shielded line (CBA): two of the newest facilities of ATALANTE facility

    International Nuclear Information System (INIS)

    The two newest facilities in the ATALANTE complex, a high-level shielded process line (CBP) and high-level shielded analysis line (CBA), are described and their work programs detailed, notably the dissolution in CBP of 15 kg of spent fuel to demonstrate the technological feasibility of partitioning the minor actinides. The analytical support role of CBA is also discussed. (authors)

  6. Light interception, utilisation and conversion efficiencies and yield performance of sweet potato, Ipomoea batatas, grown from IBA-treated basal and untreated terminal vine cuttings

    International Nuclear Information System (INIS)

    Sweet potatoes grown from IBA-treated basal vines produced a significantly higher total yield of 28.99 t ha-1 and marketable tubers 23.54 t ha-1, than those grown from untreated terminal vine cuttings which produced 22.43 and 17.46 t ha-1 of total and marketable tubers respectively. Field measurements indicated that IBA-treated basal vine plants were significantly less efficient in light interception, yet this treatment produced a higher proportion (31.20%) of large tubers, compared with untreated terminal vine plants (14.64%). Untreated terminal vine plants intercepted 95% of the incident solar radiation three weeks earlier than IBA-treated basal vine plants. However, the treatment increased the efficiency of converting light energy to chemical energy (Ec%) and of utilising this chemical energy to produce plant dry matter (Eu%) through an increased 'sink' demand. The practical implications of the results and future research are outlined

  7. Risk analysis of the aqueous fast reactor fuel cycle facility in the conceptual design stage

    International Nuclear Information System (INIS)

    This paper describes the radioactive release risk of the advanced aqueous reprocessing and fabrication facility for the fast reactor fuel cycle. Because this advanced facility is still in the conceptual design stage, the risk analysis aims at grasping the entire risk comprehensively as simple as possible. As a potential hazard, it was shown that the main process in the reprocessing and fuel fabrication facilities involved only an order of 10-3 of radioactivity in the single reactor core of large scale. Abnormal phenomena related to radioactive solution that can cause radioactive release from the facility to the environmental atmosphere in a large quantity were identified as follows: in-vessel boiling caused by loss of cooling system, a leak and fire of inflammable organic solvent in a cell, in-vessel boiling due to criticality accident, an explosion. Simplified estimation about the quantitative risk of radioactive release showed that in-vessel boiling due to loss of cooling system had the largest contribution to the non-volatile radioactive substance release in a large quantity and that criticality accidents initiated from incomplete extraction stripping of Pu nuclides were dominant in the release risk of radioactive iodine and noble gas with a short-half-life. (author)

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

    International Nuclear Information System (INIS)

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

  9. Do provisions to advance chemical facility safety also advance chemical facility security? An analysis of possible synergies

    DEFF Research Database (Denmark)

    Hedlund, Frank Huess

    2012-01-01

    The European Commission has launched a study on the applicability of existing chemical industry safety provisions to enhancing security of chemical facilities covering the situation in 18 EU Member States. This paper reports some preliminary analytical findings regarding the extent to which...... Infrastructures (ECI Directive) addresses facility security but does not cover the chemical sector. Chemical facility safety at EU level is addressed by way of the Seveso-II Directive. Preliminary estimates by the chemical industry suggest that perhaps 80% of the existing safety measures under Seveso-II would...... existing provisions that have been put into existence to advance safety objectives due to synergy effects could be expected advance security objectives as well. The paper provides a conceptual definition of safety and security and presents a framework of their essential components. Key differences are...

  10. Safeguarding uranium enrichment facilities. Review and analysis of the status of safeguards technology for uranium enrichment facilities

    International Nuclear Information System (INIS)

    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

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

    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

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

  16. Spent nuclear fuel project, Cold Vacuum Drying Facility human factors engineering (HFE) analysis: Results and findings

    International Nuclear Information System (INIS)

    This report presents the background, methodology, and findings of a human factors engineering (HFE) analysis performed in May, 1998, of the Spent Nuclear Fuels (SNF) Project Cold Vacuum Drying Facility (CVDF), to support its Preliminary Safety Analysis Report (PSAR), in responding to the requirements of Department of Energy (DOE) Order 5480.23 (DOE 1992a) and drafted to DOE-STD-3009-94 format. This HFE analysis focused on general environment, physical and computer workstations, and handling devices involved in or directly supporting the technical operations of the facility. This report makes no attempt to interpret or evaluate the safety significance of the HFE analysis findings. The HFE findings presented in this report, along with the results of the CVDF PSAR Chapter 3, Hazards and Accident Analyses, provide the technical basis for preparing the CVDF PSAR Chapter 13, Human Factors Engineering, including interpretation and disposition of findings. The findings presented in this report allow the PSAR Chapter 13 to fully respond to HFE requirements established in DOE Order 5480.23. DOE 5480.23, Nuclear Safety Analysis Reports, Section 8b(3)(n) and Attachment 1, Section-M, require that HFE be analyzed in the PSAR for the adequacy of the current design and planned construction for internal and external communications, operational aids, instrumentation and controls, environmental factors such as heat, light, and noise and that an assessment of human performance under abnormal and emergency conditions be performed (DOE 1992a)

  17. 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)

    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

  18. Pretest analysis of containment studies facility model for simulated loss of coolant accident conditions

    International Nuclear Information System (INIS)

    An experimental facility called Containment Studies Facility (CSF) has been constructed at Bhabha Atomic Research Centre (BARC), Trombay for the purpose of research and development in the area of nuclear reactor containment thermal hydraulics. The facility consists of reinforced concrete containment structural model and a Primary Heat Transport Model (PHTM) vessel. The containment model is approximately 1:250 volumetrically scaled down model of a 220 MWe Indian Pressurized Heavy Water Reactor (IPHWR) containment system and the PHTM represents the primary heat transport system of the prototype reactor. The PHTM with a pressure vessel and associated pump and piping system is designed for simulating the Loss of Coolant Accident (LOCA) or Main Steam Line Break (MSLB) conditions within the containment model. As part of CSF project thermal hydraulic analysis, a pretest analysis was carried out for simulated LOCA conditions. Blow down mass and energy discharge data were obtained using Relap/MOD3.2 code for different blow down conditions and were used as inputs to CONTRAN code for simulating LOCA or main steam line break (MSLB) conditions in the containment model. Pressure and temperature transients in the CSF model for different blow down conditions and a number of parametric studies were conducted to assess the influence of a large number of thermodynamic and geometrical parameters which are known to affect the transients and alter the peak pressure and temperature values. (author)

  19. Life-cycle cost analysis 200-West Weather Enclosure: Multi-function Waste Tank Facility

    International Nuclear Information System (INIS)

    The Multi-Function Waste Tank Facility (MWTF)will provide environmentally safe and acceptable storage capacity for handling wastes resulting from the remediation of existing single-shell and double-shell tanks on the Hanford Site. The MWTF will construct two tank farm facilities at two separate locations. A four-tank complex will be constructed in the 200-East Area of the Hanford Site; a two-tank complex will be constructed in the 200-West Area. This report documents the results of a life-cycle cost analysis performed by ICF Kaiser Hanford Company (ICF KH) for the Weather Enclosure proposed to be constructed over the 200-West tanks. Currently, all tank farm operations on the Hanford Site are conducted in an open environment, with weather often affecting tank farm maintenance activities. The Weather Enclosure is being proposed to allow year-round tank farm operation and maintenance activities unconstrained by weather conditions. Elimination of weather-related delays at the MWTF and associated facilities will reduce operational costs. The life-cycle cost analysis contained in this report analyzes potential cost savings based on historical weather information, operational and maintenance costs, construction cost estimates, and other various assumptions

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

    Science.gov (United States)

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

    2015-12-01

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

  1. Abbreviated sampling and analysis plan for planning decontamination and decommissioning at Test Reactor Area (TRA) facilities

    International Nuclear Information System (INIS)

    The objective is to sample and analyze for the presence of gamma emitting isotopes and hazardous constituents within certain areas of the Test Reactor Area (TRA), prior to D and D activities. The TRA is composed of three major reactor facilities and three smaller reactors built in support of programs studying the performance of reactor materials and components under high neutron flux conditions. The Materials Testing Reactor (MTR) and Engineering Test Reactor (ETR) facilities are currently pending D/D. Work consists of pre-D and D sampling of designated TRA (primarily ETR) process areas. This report addresses only a limited subset of the samples which will eventually be required to characterize MTR and ETR and plan their D and D. Sampling which is addressed in this document is intended to support planned D and D work which is funded at the present time. Biased samples, based on process knowledge and plant configuration, are to be performed. The multiple process areas which may be potentially sampled will be initially characterized by obtaining data for upstream source areas which, based on facility configuration, would affect downstream and as yet unsampled, process areas. Sampling and analysis will be conducted to determine the level of gamma emitting isotopes and hazardous constituents present in designated areas within buildings TRA-612, 642, 643, 644, 645, 647, 648, 663; and in the soils surrounding Facility TRA-611. These data will be used to plan the D and D and help determine disposition of material by D and D personnel. Both MTR and ETR facilities will eventually be decommissioned by total dismantlement so that the area can be restored to its original condition

  2. Abbreviated sampling and analysis plan for planning decontamination and decommissioning at Test Reactor Area (TRA) facilities

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1994-10-01

    The objective is to sample and analyze for the presence of gamma emitting isotopes and hazardous constituents within certain areas of the Test Reactor Area (TRA), prior to D and D activities. The TRA is composed of three major reactor facilities and three smaller reactors built in support of programs studying the performance of reactor materials and components under high neutron flux conditions. The Materials Testing Reactor (MTR) and Engineering Test Reactor (ETR) facilities are currently pending D/D. Work consists of pre-D and D sampling of designated TRA (primarily ETR) process areas. This report addresses only a limited subset of the samples which will eventually be required to characterize MTR and ETR and plan their D and D. Sampling which is addressed in this document is intended to support planned D and D work which is funded at the present time. Biased samples, based on process knowledge and plant configuration, are to be performed. The multiple process areas which may be potentially sampled will be initially characterized by obtaining data for upstream source areas which, based on facility configuration, would affect downstream and as yet unsampled, process areas. Sampling and analysis will be conducted to determine the level of gamma emitting isotopes and hazardous constituents present in designated areas within buildings TRA-612, 642, 643, 644, 645, 647, 648, 663; and in the soils surrounding Facility TRA-611. These data will be used to plan the D and D and help determine disposition of material by D and D personnel. Both MTR and ETR facilities will eventually be decommissioned by total dismantlement so that the area can be restored to its original condition.

  3. Integration of XRF spectrometer for simultaneous and/or complementary use with PIXE at the external ion beam analysis setup

    International Nuclear Information System (INIS)

    Full text: The Rudjer Boskovic Institute Tandem Accelerator Facility is equipped with a number of end-stations dedicated to ion beam analysis (IBA), modification of materials and nuclear physics experiments. IBA is performed at the: (1) nuclear microbeam, (2) broad-beam in-vacuum and (3) external beam end-stations. Several lBA techniques can be used simultaneously, Particle Induced X-ray Emission (PIXE) and Particle Induced Gamma-ray Emission (PIGE) at the external beam end-station, and additionally Rutherford Backscattering Spectroscopy (RBS) at the in-vacuum end-station. X-ray fluorescence (XRF) analysis is a technique complementary to PIXE. Both techniques offer high analytical potential for multi-elemental investigations and material characterization. Due to different excitation mechanisms, PIXE generally exhibits higher sensitivity for lighter elements and XRF for heavier, whereas they also have different in-sample depth sensitivities. Although they use different excitation sources, both techniques can use the same data acquisition modules. With the development of miniature, low power and lightweight X-ray tubes it is possible to incorporate an X-ray source within the IBA setup and combine the two techniques for simultaneous use. In this work, the unification of the PIXE and XRF techniques at the RBI external ion beam analysis setup has been investigated and the results are discussed. This has been done by installing a transmission miniature X-ray tube at the end-station. The tube has been properly positioned in order to irradiate the same spot on the sample as the ion beam used for PIXE/PIGE measurements. Our home made data acquisition system SPECTOR, used regularly for the IBA measurements, has been also used to acquire the XRF spectra. At first, the X-ray tube has been installed at the in-vacuum IBA station, and then to the external beam end-station. Test measurements have been carried out on various standard reference materials using both systems and the

  4. Integration of XRF spectrometer for simultaneous and/or complementary use with PIXE at the external ion beam analysis setup

    Energy Technology Data Exchange (ETDEWEB)

    Fazinic, S.; Cosic, D.; Jaksic, M. [Laboratory for lon Beam Interactions, Division of Experimental Physics, Rudjer Boskovic Institute, Zagreb (Croatia); Migliori, A.; Karydas, A.G. [Nuclear Spectrometry and Applications Laboratory, International Atomic Energy Agency (IAEA), Vienna (Austria); Desnica, V. [Laboratory for Science and Technology in Art, Academy of Fine Arts in Zagreb, Zagreb (Croatia); Mudronja, D. [Natural Science Laboratory, Croatian Conservation Institute, Zagreb (Croatia)

    2013-07-01

    Full text: The Rudjer Boskovic Institute Tandem Accelerator Facility is equipped with a number of end-stations dedicated to ion beam analysis (IBA), modification of materials and nuclear physics experiments. IBA is performed at the: (1) nuclear microbeam, (2) broad-beam in-vacuum and (3) external beam end-stations. Several lBA techniques can be used simultaneously, Particle Induced X-ray Emission (PIXE) and Particle Induced Gamma-ray Emission (PIGE) at the external beam end-station, and additionally Rutherford Backscattering Spectroscopy (RBS) at the in-vacuum end-station. X-ray fluorescence (XRF) analysis is a technique complementary to PIXE. Both techniques offer high analytical potential for multi-elemental investigations and material characterization. Due to different excitation mechanisms, PIXE generally exhibits higher sensitivity for lighter elements and XRF for heavier, whereas they also have different in-sample depth sensitivities. Although they use different excitation sources, both techniques can use the same data acquisition modules. With the development of miniature, low power and lightweight X-ray tubes it is possible to incorporate an X-ray source within the IBA setup and combine the two techniques for simultaneous use. In this work, the unification of the PIXE and XRF techniques at the RBI external ion beam analysis setup has been investigated and the results are discussed. This has been done by installing a transmission miniature X-ray tube at the end-station. The tube has been properly positioned in order to irradiate the same spot on the sample as the ion beam used for PIXE/PIGE measurements. Our home made data acquisition system SPECTOR, used regularly for the IBA measurements, has been also used to acquire the XRF spectra. At first, the X-ray tube has been installed at the in-vacuum IBA station, and then to the external beam end-station. Test measurements have been carried out on various standard reference materials using both systems and the

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

    CERN Document Server

    Wendt, M; Gössel, A

    2003-01-01

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

  6. Actinide isotopic analysis system for Los Alamos Plutonium-Handling Facility

    International Nuclear Information System (INIS)

    This paper reports that inventory measurement of a sample's total plutonium and other actinides content by non-destructive assay is an important component of safeguarding special nuclear material. Gamma-ray spectromety measurements of relative isotopic abundances, coupled with a calorimetry measurement, can determine sample SNM content for inventory measurement. The Actinide Isotopic Analysis System (AIAS) is a newly developed two-detector gamma-ray spectrometry-based system that will determine isotopic ratios of Pu and U, Np, and Am abundances relative to plutonium for the Nuclear Material Storage Facility at Los Alamos National Laboratory. spectral analysis is performed using Multiple Group analysis (MGA) program or a customized version of the Group Analysis (GRPANL) computer program. The system can measure samples containing reactor grade plutonium, weapons grade plutonium, and plutonium enriched in either 238Pu or 242Pu (>50%). Software that controls the system is driven by a user-friendly menu of options

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

    International Nuclear Information System (INIS)

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

  8. Establishment of prompt gamma neutron activation analysis facility at PARR-1

    International Nuclear Information System (INIS)

    Prompt gamma neutron activation analysis facility at through tube of upgraded PARR-1 reactor has been established. The salient features of the facility have been described. The in-pile as well as external collimators, beam shutter, target assembly and beam catcher were designed and fabricated indigenously. The flux at target position is 1.8x10/sup 10/ neutrons/cm/sup 2/sec and the cadmium ratio is about 10 Anti-Compton/pair spectrometer has been installed at 90 deg. to the incident beam. The measurements of the prompt gamma rays from thermal neutron capture in chlorine, nitrogen and chromium were carried out to calibrate HPGe detector up to 10 MeV. The set-up will be used in the determination of non-metals that form the elements of geological and biological materials or other trace elements with high thermal capture cross sections with improved peak/compton ratio of the spectrometer. (author)

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

    Energy Technology Data Exchange (ETDEWEB)

    TRINER, G.C.

    1999-11-01

    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.

  10. Cost benefit analysis for the establishment of food irradiation facilities in some egyptian export sites

    International Nuclear Information System (INIS)

    The present study discusses the economic aspects of the establishment of food irradiation facility that serves the Egyptian export sites such as Safaga and Suez and the effect of various parameters on the unit processing costs. The study is concerned with carrying out an economic evaluation for the application of irradiation for food exports from Safaga and Suez harbours. The study was carried out according to the approach applied in the evaluation of economic projects and also considering the requirements of technology projects for food preservation. The study comprises the determination of the commodity mix for the Egyptian food commodities that are proposed for irradiation and export from Safaga and Suez. The commodity mix is distributed for the full utilization of the working capacity and the evaluation of the type of the irradiation facility and also the radiation source strength. The financial analysis for such an irradiation facility is also carried out. It provides a model for calculating the specific unit processing costs by correlating known capital costs with annual operation cost and annual throughputs. The study had analyzed the cost-benefit of the proposed food irradiation facility. The study took into account the cost of the capital investment, operation cost and other additional parameters. The investment criteria utilized for commercial evaluation were internal rate of return (IRR) and pay back period (PBP). The irradiation cost and the additional income were also discussed. The results of this analysis showed that the installation of an irradiation unit for food irradiation that serves Safaga and Suez harbours would be economically feasible

  11. Status of post-quake reconstruction project and scheduled introduction of the 6 MV tandem accelerator at the multi tandem accelerator facility, the University of Tsukuba

    International Nuclear Information System (INIS)

    The 12UD Pelletron tandem accelerator with a history of over 35 years at the University of Tsukuba was destroyed by the Great East Japan Earthquake on 11 March 2011. We have mapped out a strategy for the post-quake reconstruction project. At present, we are planning to install a new middle-sized tandem accelerator at the 2nd experimental room instead of the broken 12UD Pelletron tandem accelerator. A new accelerator system will consist of a horizontal type 6 MV Pelletron tandem accelerator, new 4 ion sources and the polarized ion source which will be moved from the 9th floor to a new experimental booth on the ground, an accelerator mass spectrometry system and an ion beam analysis system. High energy beam transport line will be connected from the 2nd experimental room to the present experimental facilities at the 1st experimental room. The new AMS system will be capable of measuring environmental levels for long-lived radioisotopes of 10Be, 14C, 26Al, 36Cl, 41Ca and 129I. The new IBA system will be equipped with a high-precision five-axis goniometer. The 6 MV tandem accelerator will mainly be applied for AMS, IBA, heavy ion irradiation and nuclear physics. The beam delivery will start on September 2014. (author)

  12. Scoping analysis of toxic metal performance in DOE low-level waste disposal facilities

    International Nuclear Information System (INIS)

    This study provides a scoping safety assessment for disposal of toxic metals contained in Department of Energy (DOE) mixed low-level waste (MLLW) at six DOE sites that currently have low-level waste (LLW) disposal facilities--Savannah River Site, Oak Ridge Reservation, Los Alamos National Laboratory, Hanford Reservation, Nevada Test Site, and Idaho National Engineering Laboratory. The study has focused on the groundwater contaminant pathway, which is considered to be the dominant human exposure pathway from shallow land MLLW disposal. A simple and conservative transport analysis has been performed using site hydrological data to calculate site-specific ''permissible'' concentrations of toxic metals in grout-immobilized waste. These concentrations are calculated such that, when toxic metals are leached from the disposal facility by infiltrating water and attenuated in local ground-water system the toxic metal concentrations in groundwater below the disposal facility do not exceed the Maximum Contaminant Levels as stated in the National Primary Drinking Water Regulation. The analysis shows that and sites allow about I00 times higher toxic metal concentrations in stabilized waste leachate than humid sites. From the limited available data on toxic metal concentrations in DOE MLLW, a margin of protection appears to exist in most cases when stabilized wastes containing toxic metals are disposed of at the DOE sites under analysis. Possible exceptions to this conclusion are arsenic, chromium selenium, and mercury when disposed of at some humid sites such as the Oak Ridge Reservation. This analysis also demonstrates that the US Environmental Protection Agency's prescriptive regulatory approach that defines rigid waste treatment standards does not inherently account for the variety of disposal environments encountered nationwide and may result in either underprotection of groundwater resources (at humid sites) or an excessive margin of protection (at and sites)

  13. 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)

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

    International Nuclear Information System (INIS)

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

  15. Wound center facility billing: A retrospective analysis of time, wound size, and acuity scoring for determining facility level of service.

    Science.gov (United States)

    Fife, Caroline E; Walker, David; Farrow, Wade; Otto, Gordon

    2007-01-01

    Outpatient wound center facility reimbursement for Medicare beneficiaries can be a challenge to determine and obtain. To compare methods of calculating facility service levels for outpatient wound centers and to demonstrate the advantages of an acuity-based billing system (one that incorporates components of facility work that is non-reimbursable by procedure codes and that represents an activity-based costing approach to medical billing), a retrospective study of 5,098 patient encounters contained in a wound care-specific electronic medical record database was conducted. Approximately 500 patient visits to the outpatient wound center of a Texas regional hospital between April 2003 and November 2004 were categorized by service level in documentation and facility management software. Visits previously billed using a time-based system were compared to the Centers for Medicare and Medicaid Services' proposed three-tiered wound size-based system. The time-based system also was compared to an acuity-based scoring system. The Pearson correlation coefficient between billed level of service by time and estimated level of service by acuity was 0.442 and the majority of follow-up visits were billed as Level 3 and above (on a time level of 1 to 5) , confirming that time is not a surrogate for actual work performed. Wound size also was found to be unrelated to service level (Pearson correlation = 0.017) and 97% of wound areas were based scoring system produced a near-normal distribution of results, producing more mid-range billings than extremes; no other method produced this distribution. Hospital-based outpatient wound centers should develop, review, and refine acuity score-based models on which to determine billed level of service. PMID:17264354

  16. Thermal-hydraulic analysis of the International Fusion Materials Irradiation Facility

    International Nuclear Information System (INIS)

    Since 1994 the International Fusion Materials Irradiation Facility is under development. Up till now only design activities have been performed aimed at providing a reference design, evaluating remaining design uncertainty, reducing the costs and the key technology risk factors to reach the specified requirements with sufficient availability and reliability. From the beginning ENEA is engaged in the design of all the systems. In particular for the Lithium Target System, its activities are mainly focused on risk analysis, transient analysis, thermal-hydraulics and stability of lithium jet. This paper deals with the analysis of the behaviour of the Lithium Target System under normal and incident conditions, performed with a version of the RELAP5/Mod3.2 code modified to allow for specific features of the system itself (Lithium and organic oil as cooling fluids).(author)

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

    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

  20. Meteorological guide line to safety analysis for nuclear power generating facilities

    International Nuclear Information System (INIS)

    In this guide line, the meteorological observation procedures, the statistical processing of observed data, and the method of analyzing atmospheric diffusion are determined, which are necessary for estimating the diffusion conditions of radioactive materials in the air, when evaluating exposure dose in the assumed accidents (maximum credible and hypothetical accidents) and in the normal operating of nuclear power generating facilities. The ''meteorological guide to reactor safety analysis'' determined by the Atomic Energy Commission of Japan in 1965 has been applied to such analysis so far. The new guide line was determined from the updated standpoint as well as by reviewing the previous guide, in consideration of the development of meteorological analysis investigation and the accumulation of experiences for the construction and operation of reactor facilities. The guide line also describes about the effective height of the source releasing radioactive materials and wind-tunnel experiment. The major theme of the guide line is the calculation of radioactive material concentration in the air at the ground surface in case that gaseous radioactive material is diffused over several kilometers around the source. Detailed explanations on the above described items and the additional note including measures for the time being for the problems not stated clearly in the guide are added. (Wakatsuki, Y.)

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

    International Nuclear Information System (INIS)

    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)

  2. CFD Analysis of Flexible Thermal Protection System Shear Configuration Testing in the LCAT Facility

    Science.gov (United States)

    Ferlemann, Paul G.

    2014-01-01

    This paper documents results of computational analysis performed after flexible thermal protection system shear configuration testing in the LCAT facility. The primary objectives were to predict the shear force on the sample and the sensitivity of all surface properties to the shape of the sample. Bumps of 0.05, 0.10,and 0.15 inches were created to approximate the shape of some fabric samples during testing. A large amount of information was extracted from the CFD solutions for comparison between runs and also current or future flight simulations.

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

    Science.gov (United States)

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

    2016-06-01

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

  4. Wind Atlas Analysis and Application Program: WAsP 11 Help Facility

    DEFF Research Database (Denmark)

    2014-01-01

    The Wind Atlas Analysis and Application Program (WAsP) is a PC-program for horizontal and vertical extrapolation of wind climates. The program contains a complete set of models to calculate the effects on the wind of sheltering obstacles, surface roughness changes and terrain height variations. The...... specific wind turbines and wind farms. The WAsP Help Facility includes a Quick Start Tutorial, a User's Guide and a Technical Reference. It further includes descriptions of the Observed Wind Climate Wizard, the WAsP Climate Analyst, the WAsP Map Editor tool, the WAsP Turbine Editor tool, the Air Density...

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

    CERN Document Server

    Mönch, Lars; Mason, Scott J

    2012-01-01

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

  6. Effects of the time of cuttings collection and IBA concentration on the rooting of softwood cuttings from elite trees of Cornelian cherry (Cornus mas L. in Belgrade area

    Directory of Open Access Journals (Sweden)

    Marković Marija

    2014-01-01

    Full Text Available In this study, the effect of concentration of indole-3-butyric acid (IBA (powder dip, cutting type as well as the time of taking cuttings on the rooting of softwood cuttings of cornelian cherry was examined. Four types of cuttings were used: basal cuttings, terminal cuttings, basal cuttings with 2-year-old wood and terminal cuttings with 2-year-old wood. The obtained results showed that IBA concentration, cutting type and time of collecting have significant effect on rooting. The best results were obtained using 1% IBA and cuttings collected in the second term (in mid-July had a higher rooting percentage. Terminal cuttings treated with 1% IBA (powder dip should be used for optimum results. In that case the rooting percentage was very high (over 90% in both terms of cuttings collection. [Projekat Ministarstva nauke Republike Srbije, br. 43007: Istraživanje klimatskih promena na životnu sredinu: praćenje uticaja, adaptacija i ublažavanje

  7. Space Station Furnace Facility. Volume 2: Requirements definition and conceptual design study. Appendix 3: Environment analysis

    Science.gov (United States)

    1992-01-01

    A Preliminary Safety Analysis (PSA) is being accomplished as part of the Space Station Furnace Facility (SSFF) contract. This analysis is intended to support SSFF activities by analyzing concepts and designs as they mature to develop essential safety requirements for inclusion in the appropriate specifications, and designs, as early as possible. In addition, the analysis identifies significant safety concerns that may warrant specific trade studies or design definition, etc. The analysis activity to date concentrated on hazard and hazard cause identification and requirements development with the goal of developing a baseline set of detailed requirements to support trade study, specifications development, and preliminary design activities. The analysis activity will continue as the design and concepts mature. Section 2 defines what was analyzed, but it is likely that the SSFF definitions will undergo further changes. The safety analysis activity will reflect these changes as they occur. The analysis provides the foundation for later safety activities. The hazards identified will in most cases have Preliminary Design Review (PDR) applicability. The requirements and recommendations developed for each hazard will be tracked to ensure proper and early resolution of safety concerns.

  8. Criticality experiments: analysis, evaluation, and programs. 7. Program of Experimental Investigations on Critical Facilities at IPPE

    International Nuclear Information System (INIS)

    -scale) mockup of the BREST-300 reactor. The study of mockups of prospective BN-800 re actor cores with mixed nitride fuel will begin in 2001. One of the key features of this program is the study of the contribution of reaction (n, p) on nitrogen in neutron balance of the core. Future plans include the following work: 1. cores of fast and thermal reactors using fuel in an inert matrix (except earlier experiments on BFS-58). A series of assemblies, BFS-91, is planned in 2001 where the Doppler effect on plutonium will be investigated in addition to other neutron physical characteristics. 2. benchmarks that test neutron data on lead and bismuth (prolongation of a series of experiments on BFS-85 and BFS-87 assemblies carried out in 2000) and a study of accelerator-driven systems mockups with Pb and Pb-Bi targets; 3. experiments in substantiation of the hyper-thermal graphite reactor with plutonium fuel (together with the Kurchatov Institute-Moscow and OKBM-Nizhni Novgorod); 4. critical experiments on RF-GS on nuclear safety in storage of MOX fuel; 5. experiments of a different type on improvement of neutron data for minor actinides; 6. experiments on optimization of targets for the production of 37Ar and other isotopes on BN-800 at BFS-62 and BFS-66 assemblies; 7. study of temperature effects and other characteristics in prospective cores of VVER (MATR facility); 8. simulation of fast neutron reactor cores under the CEFR (China) and KALIMER (South Korea) projects. At present, several experimental programs are being carried out on the critical facilities at IPPE (Obninsk). The analysis of many of these experiments is being performed cooperatively with experts from the United States, Japan, France, the People's Republic of China, and the Republic of Korea. The IPPE critical facilities are open for international cooperation. (authors)

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

    Energy Technology Data Exchange (ETDEWEB)

    Hoskinson, R.L.

    1994-01-01

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

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

    International Nuclear Information System (INIS)

    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

  11. 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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2012-07-01

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

  13. Analysis of criticality accident alarm system coverage in the X-700, X-705, and X-720 facilities at the Portsmouth Gaseous Diffusion plant

    International Nuclear Information System (INIS)

    Additional services for the uranium enrichment cascade process, such as maintenance and decontamination operations, are provided by several ancillary facilities at the PORTS site. These facilities include the X-700 Maintenance Facility, the X-705 Decontamination Facility, and the X-720 Maintenance and Stores Facility. As uranium operations are performed within these facilities, the potential for a criticality accident exists. In the event of a criticality accident within one of these facilities at PORTS, a Criticality Accident Alarm System (CAAS) is in place to detect the criticality accident and sound an alarm. In this report, an analysis was performed to provide verification that the existing CAAS at PORTS provides complete criticality accident coverage in the X-700, X-705, and X-720 facilities. The analysis has determined that the X-705 and X-720 facilities have complete CAAS coverage; the X-700 facility has not been shown to have complete CAAS coverage at this time

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

    International Nuclear Information System (INIS)

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

  15. An in situ neutron irradiation facility for non-destructive elemental analysis

    International Nuclear Information System (INIS)

    Design and construction of an irradiation facility for nondestructive neutron activation analysis have been investigated. Two facilities have been constructed, using the available 5 Ci, Pu-Be, neutron sources and paraffin as modderator. The first unit has been designed mainly for neutron flux distribution studies. This unit consists of paraffin bricks of various sizes to facilitate placing the Dy, In and gold foils for flux maping. The second unit consists of a single paraffin block 50 x 50 x 50 cm3, having the same dimensions as the first unit. Two horizontal beam ports and one vertical were constructed in the paraffin moderator for sample irradiation. The maximum total absolute flux measured in the median plane was found to be about 1.32 x 104 n/cm2. Sec. at a distance of about 3.5 cm from the source surface. For test on geological sample of commercial interest gold sample were irradiated and measured. More than 10 elements have been clearly identified. Gold which is known to exist in this sample at about 10 parts per million was also clearly observed. This work is a part of joint programme with the international Atomic Energy Agency Research Contract No. 1697/RB. The title of this project is Elemental Activation Analysis with Decay and Prompt Gamma Ray Techniques, Using Isotopic Neutron Sources and Nuclear Research Reactors

  16. 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.

  17. Analysis of material recovery facilities for use in life-cycle assessment

    International Nuclear Information System (INIS)

    Highlights: • Life-cycle assessment of solid waste management relies on accurate process models. • Material recovery facility (MRF) processes were modeled with new primary data. • Single stream, dual stream, pre-sorted, and mixed waste MRFs were considered. • MRF electricity consumption ranges from 4.7 to 7.8 kW h per Mg input. • Total cost ranges from $19.8 to $24.9 per Mg input. - Abstract: Insights derived from life-cycle assessment of solid waste management strategies depend critically on assumptions, data, and modeling at the unit process level. Based on new primary data, a process model was developed to estimate the cost and energy use associated with material recovery facilities (MRFs), which are responsible for sorting recyclables into saleable streams and as such represent a key piece of recycling infrastructure. The model includes four modules, each with a different process flow, for separation of single-stream, dual-stream, pre-sorted recyclables, and mixed-waste. Each MRF type has a distinct combination of equipment and default input waste composition. Model results for total amortized costs from each MRF type ranged from $19.8 to $24.9 per Mg (1 Mg = 1 metric ton) of waste input. Electricity use ranged from 4.7 to 7.8 kW h per Mg of waste input. In a single-stream MRF, equipment required for glass separation consumes 28% of total facility electricity consumption, while all other pieces of material recovery equipment consume less than 10% of total electricity. The dual-stream and mixed-waste MRFs have similar electricity consumption to a single-stream MRF. Glass separation contributes a much larger fraction of electricity consumption in a pre-sorted MRF, due to lower overall facility electricity consumption. Parametric analysis revealed that reducing separation efficiency for each piece of equipment by 25% altered total facility electricity consumption by less than 4% in each case. When model results were compared with actual data for an

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

    International Nuclear Information System (INIS)

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

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

    CERN Document Server

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

    2012-01-01

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

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

    International Nuclear Information System (INIS)

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

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

    CERN Document Server

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

    2013-01-01

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

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

    International Nuclear Information System (INIS)

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

  3. 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.

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

    Science.gov (United States)

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

    2012-12-01

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

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

    International Nuclear Information System (INIS)

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

  6. Sampling based uncertainty analysis of station blackout in PSB VVER integral test facility

    International Nuclear Information System (INIS)

    Highlights: → SBO analysis in PSB VVER ITF has been carried out using RELAP5/MOD3.2. → Uncertainty and sensitivity analysis is carried out with sampling based approach (LHS). → Experimental/code calculated values are within the uncertainty band. → Linear regression analysis is carried out to get order of importance of input parameters. → This methodology can be used for transients of NPP with any best estimate system code. - Abstract: Best estimate accident analysis with uncertainty evaluation is being encouraged in the present licensing scenarios of nuclear power plants. This paper deals with uncertainty and sensitivity analysis for station blackout in PSB VVER integral test facility under the framework of coordinated research project of IAEA. Nodalization was developed using best estimate system code RELAP5/MOD3.2 and its steady state and transient level qualifications are achieved. Sampling based approaches are used to carry out uncertainty and sensitivity/importance analysis. The objective of the analysis is to get confidence for uncertainty methodology by comparing with the experimental results and extend its applicability to NPPs. Uncertainty analysis is carried out by selecting nine important input parameters with specified ranges and its uniform distributions. A design matrix of 45 x 9 is generated for variations of input parameters with the Latin Hypercube Sampling and 45 code runs were taken. Linear regression was also carried out to quantify the effect of each individual input parameter on output parameters in terms of standard rank regression coefficients. Uncertainty band in output parameters is defined between 95th and 5th percentile value. It is observed that most of the experimental values and code calculated reference values are lying within the uncertainty band. For most of the parameters, width of uncertainty band increases with transient progression time.

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

    International Nuclear Information System (INIS)

    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

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

    International Nuclear Information System (INIS)

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

  9. Nanostructural analysis network organisation: a new Australian major national research facility

    International Nuclear Information System (INIS)

    Full text: The Commonwealth of Australia recently announced that it would establish a new Major National Research Facility (MNRF) in nanostructural analysis. This initiative, to be managed through AusIndustry is an important national development for the microscopy and microanalysis community. The Nanostructural Analysis Network Organisation (NANO) will deliver new capabilities in atomic and molecular level imaging, analysis and manipulation to support and enable nanotechnology and biotechnology research. Specifically these capabilities include provision of an advanced atom probe, focused ion beam and secondary ion mass spectroscopy platforms for the characterisation and prototyping of nanomaterials, devices and conventional engineering materials. Provision of a state-of-the art platform for structural biology using transmission electron cryomicroscopy so as to characterise the structure, assembly, dynamics and interaction of macromolecules with substrates is also planned. The foundation partners of NANO include five Universities from four states, four state governments and three companies, NANO will be the peak-Australian facility for the characterisation of physical and biological materials. The aim of NANO is to establish new collaborative linkages through a network organisation for resource-sharing between a national grid of existing instrumentation in microscopy and microanalysis. The development of high quality telepresence capabilities in conjunction with the major national high speed computing network initiatives is a key component of NANO. In this paper, the operational structure and key processes of NANO will be explained. The opportunities for and mechanisms of collaboration with NANO will be discussed as will the plans to expand and diversity the network. Copyright (2002) Australian Society for Electron Microscopy Inc

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

    International Nuclear Information System (INIS)

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

  11. Efeito do estiolamento parcial e do ácido indolbutírico (IBA no enraizamento de estacas de ramos de goiabeira serrana (Feijoa sellowiana, Berg Efects of blanching and of indolbutyric acid (IBA in the rooting of Feijoa sellowiana, Berg. cuttings

    Directory of Open Access Journals (Sweden)

    S.L.B. Figueiredo

    1995-04-01

    Full Text Available Com o objetivo de verificar o efeito do estiolamento parcial dos ramos e do ácido indolbutírico (IBA, no enraizamento de estacas de Feijoa sellowiana, conduziu-se este trabalho de enraizamento em três épocas de estiolamento, utilizando-se câmara de nebulização. Antes das estacas serem retiradas efetuou-se o estiolamento dos ramos de diversas plantas, com uniformidade de tamanho e idade. Foram utilizadas estacas de ramos em três intervalos de estiolamento (zero, 40 e 60 dias, tratadas com Zero; 5000; 7000; 9000 e 11000 ppm de IBA, na formulação de pó. Foi avaliado o número de estacas enraizadas, determinando-se a percentagem de enraizamento. Os resultados mostraram que estiolamento parcial foi efetivo para o enraizamento, sendo que o melhor intervalo foi variável conforme a época de estiolamento dos ramos e o IBA teve efeito negativo sobre o enraizamento.With the aim of verifying branching and indolbutyric acid (IBA effects on the rootling of cuttings of feijoa, this work was carried out considering three different dates of blanching, in greenhouse. The branching of various plants with uniform size and age was performed prior to branch trimming. Branch cuttings obtained at three blanching times (Zero, 40 and 60 days; treated with Zero; 5000; 7000; 9000 and 11000 ppm of power IBA, were used. The number of rooted cuttings was evaluated in order to calculate percent rooting. The results showed that the blanching was effective in rooting and the best time was variable according to the date of branch blanching; the IBA showed negative effect on rooting.

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

  15. Enhanced computational infrastructure for data analysis at the DIII-D National Fusion Facility

    International Nuclear Information System (INIS)

    Recently a number of enhancements to the computer hardware infrastructure have been implemented at the DIII-D National Fusion Facility. Utilizing these improvements to the hardware infrastructure, software enhancements are focusing on streamlined analysis, automation, and graphical user interface (GUI) systems to enlarge the user base. The adoption of the load balancing software package LSF Suite by Platform Computing has dramatically increased the availability of CPU cycles and the efficiency of their use. Streamlined analysis has been aided by the adoption of the MDSplus system to provide a unified interface to analyzed DIII-D data. The majority of MDSplus data is made available in between pulses giving the researcher critical information before setting up the next pulse. Work on data viewing and analysis tools focuses on efficient GUI design with object-oriented programming (OOP) for maximum code flexibility. Work to enhance the computational infrastructure at DIII-D has included a significant effort to aid the remote collaborator since the DIII-D National Team consists of scientists from nine national laboratories, 19 foreign laboratories, 16 universities, and five industrial partnerships. As a result of this work, DIII-D data is available on a 24x7 basis from a set of viewing and analysis tools that can be run on either the collaborators' or DIII-D's computer systems. Additionally, a web based data and code documentation system has been created to aid the novice and expert user alike

  16. Introduction and preparation of the nuclear fuel cycle facility risk analysis code: STAR

    International Nuclear Information System (INIS)

    STAR code is a computer program, by which one can perform the probabilistic safety assessment (PSA) for the nuclear fuel cycle facility in both the normal and the accidental event of environmental radioactive material release. This code was originally developed by NUKEM GmbH in West Germany as a fruit of the PSE (Projekt Sicherheitsstudien Entsorgung) aiming at R and D of safety analysis methods for use in nuclear fuel cycle facilities such as reprocessing plants. In JAERI, efforts have been made to research and develop safety assessment methods applicable to the accidental situations assumed to happen in the reprocessing plants. In this line of objectives, the STAR code was introduced from NUKEM GmbH in 1986 and, since then, has been improved and prepared to add an ability to analyze public radiation exposure by released activities from the plants. At the first stage of this code preparation, the program conversion was made to adapt the STAR code, originally operative on IBM-compatible PC's and Hewlett Packard 7550A plotters, to NEC PC 9801RX and NEC PR 602R page printers installed in the Fuel Cycle Safety Assessment Laboratory of JAERI. This report describes calculational performances of the STAR code, results of the improvement and preparation works together with input/output data format in illustration of a sample HALW (High Activity Liquid Waste) tank PSA problem, thus making a users' manual for the STAR code. (author)

  17. Development of a component Monte Carlo program for accident sequence analysis to apply for reprocessing facility

    International Nuclear Information System (INIS)

    In consideration of application for reprocessing facility, where a variety of causal events such as equipment failure and human error might occur, and the event progression would take place with relatively substantial time delay before getting to the accident stage, a component Monte Carlo program for accident sequence analysis has been developed to pursue chronologically the probabilistic behavior of each component failure and repair in an exact manner. In comparison with analytical formulation and its calculated results, this Monte Carlo technique is shown to predict a reasonable result. Then, taking an example for a sample problem from a German reprocessing facility model, an accident sequence of red-oil explosion in a plutonium evaporator is analyzed to give a comprehensive interpretation about statistic variation range and computer time elapsed for random walk history calculations. Furthermore, to discuss about its applicability for the practical case of plant system with complex component constitution, a possibility of drastic speed-up of computation is shown by parallelization of the computer program. (author)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2015-02-25

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

  19. Conceptual design analysis of 4 K irradiation facility in Korean HANARO research reactor

    International Nuclear Information System (INIS)

    A conceptual design of a 4 K irradiation test facility has been conducted in support of the International Thermonuclear Experimental Reactor (ITER) magnet development program. A new research reactor designated as HANARO at the Korea Atomic Energy Research Institute has a Cold Neutron Source (CNS) port that is identified to be suitable for the fast neutron irradiation of metals and insulation materials for superconducting magnets at 4 K. A 40 hours of irradiation at full power will produce 2.5 x 1017 n/cm2 of the ITER magnet design neutron fluence with energy above 0.1 MeV. A material testing laboratory of Irradiated Materials Evaluation Facility (IMEF) that is located next to HANARO has been equipped with 77 K test machines and fracture analysis microscopes for radioactive specimens which can be upgraded for 4 K test without any intermediate warming. CNS radiation spectrum determined by Monte Carlo method is found to be more favorable for metal irradiation than for insulation materials with absorbed gamma dose that is 7-10 times the fast neutron dose. A lead-shielded irradiation capsule design with a 1 cm diameter specimen in 3 cm cold-bore diameter and 18 cm height will require about 120 watt cooling capacity at 4.6 K

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2016-02-19

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

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

    International Nuclear Information System (INIS)

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

  2. Operational safety analysis of the Olkiluoto encapsulation plant and disposal facility

    International Nuclear Information System (INIS)

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2012-11-15

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

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

    Science.gov (United States)

    Jackson, M. E.

    1995-01-01

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

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

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

    Science.gov (United States)

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

    2015-08-01

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

  8. EXPERIENCES FROM THE SOURCE-TERM ANALYSIS OF A LOW AND INTERMEDIATE LEVEL RADWASTE DISPOSAL FACILITY

    Energy Technology Data Exchange (ETDEWEB)

    Park,Jin Beak; Park, Joo-Wan; Lee, Eun-Young; Kim, Chang-Lak

    2003-02-27

    Enhancement of a computer code SAGE for evaluation of the Korean concept for a LILW waste disposal facility is discussed. Several features of source term analysis are embedded into SAGE to analyze: (1) effects of degradation mode of an engineered barrier, (2) effects of dispersion phenomena in the unsaturated zone and (3) effects of time dependent sorption coefficient in the unsaturated zone. IAEA's Vault Safety Case (VSC) approach is used to demonstrate the ability of this assessment code. Results of MASCOT are used for comparison purposes. These enhancements of the safety assessment code, SAGE, can contribute to realistic evaluation of the Korean concept of the LILW disposal project in the near future.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1994-01-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1979-06-01

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

  11. Dynamical analysis of a facility including the base and the equipment

    International Nuclear Information System (INIS)

    The paper presents a description of the methodology and the results from the dynamical calculations for a 'Phantom' aircraft impact on the reactor building and following calculations for the piping system in the same building after the aircraft fall. The response accelerograms from the dynamical analysis for the reactor building are used as initiating event. The calculations are made using the finite elements method. The mechanical model of the base uses the Foigt model (coils and dampers in parallel connection). The calculations are made for six different cases of the impact of the aircraft with the facility. The developed method permits to assess the stressed dynamical conditions of the system and stability in a dynamical system taking into account the spatial properties of construction and equipment as well as and susceptibility and inertial properties of the base grounds

  12. Analysis of the FIC detector data at the nTOF facility

    International Nuclear Information System (INIS)

    Fission cross-section measurements with the Fast Ionization Chamber (FIC) at the CERN nTOF facility were challenged by intense signals due to γ-rays and ultra-relativistic particles from the impact of the 20 GeV proton pulses on the neutron spallation target. A method for analyzing the data taken with Flash Analog to Digital Converters (FADC) was developed to treat these problems in an automated way to provide a reliable background subtraction and a fit routine for identifying fission events even at high energies. The analysis is illustrated at the example of the fission cross-section of 238U relative to that of 235U in the energy range from 40 keV to 300 MeV.

  13. Analysis of the FIC detector data at the n_TOF facility

    CERN Document Server

    Karadimos, D; Papachristodoulou, C; Vlachoudis, V; Assimakopoulos, P; Ioannides, K; Vlastou, R; Karamanis, D; Tsagas, N; Cennini, P; Konovalov, V; Ketlerov, V

    2010-01-01

    Fission cross-section measurements with the Fast Ionization Chamber (FIC) at the CERN n\\_TOF facility were challenged by intense signals due to gamma-rays and ultra-relativistic particles from the impact of the 20 GeV proton pulses on the neutron spallation target. A method for analyzing the data taken with Flash Analog to Digital Converters (FADC) was developed to treat these problems in an automated way to provide a reliable background subtraction and a fit routine for identifying fission events even at high energies. The analysis is illustrated at the example of the fission cross-section of U-238 relative to that of U-235 in the energy range from 40 key to 300 MeV. (C) 2010 Elsevier B.V. All rights reserved.

  14. Analysis of the FIC detector data at the n{sub T}OF facility

    Energy Technology Data Exchange (ETDEWEB)

    Karadimos, D., E-mail: dkaradim@gmail.co [University of Ioannina, PO Box 1186, Panepistimioupoli, GR-451 10 Ioannina (Greece); Democritus University of Thrace, University Campus, 69100 Komotini (Greece); Vlastou, R. [National Technical University of Athens, 9, Heroon Polytechneiou Street, GR-157 80 Athens (Greece); Ioannides, K.; Assimakopoulos, P. [University of Ioannina, PO Box 1186, Panepistimioupoli, GR-451 10 Ioannina (Greece); Tsagas, N. [Democritus University of Thrace, University Campus, 69100 Komotini (Greece); Pavlopoulos, P. [Paris, La Defense, 92 916 Paris La Defense Cedex (France); Karamanis, D.; Papachristodoulou, C.; Stamoulis, K. [University of Ioannina, PO Box 1186, Panepistimioupoli, GR-451 10 Ioannina (Greece); Vlachoudis, V.; Cennini, P. [CERN, CH-1211 Geneve 23, Geneva (Switzerland); Ketlerov, V. [Institute of Physics and Power Engineering, Federal State Unitary Enterprise ' SSC RF - IPPE' 249033, Obninsk, Kaluga region. Sq. Bondarenko, 1 (Russian Federation); Konovalov, V. [Joint Institute for Nuclear Research, 141980, Moskovskaya obl., Joliot-Curie st., 6, Dubna (Russian Federation)

    2010-08-15

    Fission cross-section measurements with the Fast Ionization Chamber (FIC) at the CERN n{sub T}OF facility were challenged by intense signals due to {gamma}-rays and ultra-relativistic particles from the impact of the 20 GeV proton pulses on the neutron spallation target. A method for analyzing the data taken with Flash Analog to Digital Converters (FADC) was developed to treat these problems in an automated way to provide a reliable background subtraction and a fit routine for identifying fission events even at high energies. The analysis is illustrated at the example of the fission cross-section of {sup 238}U relative to that of {sup 235}U in the energy range from 40 keV to 300 MeV.

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

    International Nuclear Information System (INIS)

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

  16. Combined ion micro probe and SEM analysis of strongly non uniform deposits in fusion devices

    Energy Technology Data Exchange (ETDEWEB)

    Bykov, I.; Bergsåker, H.; Petersson, P. [Division of Fusion Plasma Physics, Association EURATOM-VR, Royal Institute of Technology KTH (Sweden); Likonen, J. [Association EURATOM-TEKES, VTT, PO Box 1000, 02044 VTT, Espoo (Finland); Possnert, G. [Tandem Laboratory, Association EURATOM-VR, Uppsala Universitet, Box 256, Uppsala 75105 (Sweden); Widdowson, A. [CCFE, Culham Science Centre, Abingdon OX14 3DB (United Kingdom)

    2015-01-01

    Conventional ion beam analysis (IBA) of deposited layers from fusion devices may have insufficient accuracy due to strongly uneven appearance of the layers. Surface roughness and spatial variation of the matrix composition make interpretation of broad beam spectra complex and non obvious. We discuss complications of applied IBA arising for fusion-relevant surfaces and demonstrate how quantification can be improved by employing micro IBA methods. The analysis is bound to pre-defined regions on the sample surface and can be extended by employing beams of several types, scanning electron microscopy (SEM) and stereo SEM techniques.

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

    OpenAIRE

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

    2016-01-01

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

  18. 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....... 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 WiFi...... traces collected in the hospital’s WiFi infrastructure over two weeks observing around 18000 different devices recording more than a billion individual WiFi measurements. For the presented analysis methods we present quantitative performance results, e.g., demonstrating over 95% accuracy for correct...

  19. Oxygen deficiency hazard (ODH) analysis for pressure and cryogenic systems facilities

    International Nuclear Information System (INIS)

    The presence and use of pressure and cryogenic systems associated with storage, handling, and transfer of compressed and liquefied gases, and cryogenic liquids is commonplace at most industries, R and D and test facilities. The uncontrolled introduction of these materials into the workplace environment presents a hazard and increases the risk of asphyxiation or fatality from exposure to reduced atmospheric oxygen. This paper will generalize international experience gained by developing and establishing ODH control programs at Superconducting Super Collider Laboratory (SSCL), Fermi National Laboratory (FNL), and Cryogenic Co. ''KISLORODMASH'' (Ukraine). ODH Control program elements include quantitative ODH analysis and risk assessment, operations and ODH creating mechanisms study, ODH areas classification, ODH control measures, and personnel controls. This program involves analysis and basic calculations that show the quantity of the potential source in the area of assessment could or could not results in an ODH. This paper also includes some results of ODH analysis performed by the author at SSCL for the Linear Accelerator Building, Ion Source Low Energy Beam Lab, Vacuum R and D Lab, Ion Source Test Stand, and Corrector Magnets Test Pit

  20. The National Analysis Facility at DESY - status and use cases by the participating experiments

    International Nuclear Information System (INIS)

    The German National Analysis Facility (NAF) was set up at DESY, starting end of 2007 in the context of the Helmholtz Alliance 'Physics at the Terascale'. The NAF complements the DESY and the German Grid resources, and hence offers users from the German HEP institutes the best possible environment for data analysis. In the first part, the key aspects and components of the NAF are briefly presented with an emphasis on recent improvements. In the second part, the use cases of the three participating LHC experiments, ATLAS, CMS and LHCb, will be presented. Differences and commonalities in the usage of the NAF will be shown. Special emphasis will be placed on the usage of PROOF, whose usage on the NAF has been pioneered by CMS. It is now adapted by ATLAS. The third part will concentrate on how the NAF was used for detector optimisation studies in the preparation of one of the ILC Lol's (ILD 2009), as well as how CALICE uses the NAF for the analysis of their data taken in several test beam experiments performed for detector R and D. Finally, future developments of the NAF are presented.

  1. An enhanced aerobic bioremediation system at a central production facility -- system design and data analysis

    International Nuclear Information System (INIS)

    A successful field demonstration of the enhanced in-situ aerobic bioremediation with remarkable results took place during the period of August 1, 1991 through year-end 1992 at a central production facility in Michigan. The in-situ soil logging and groundwater sampling by the cone penetrometer/porous probe system provided a real-time definition of the groundwater flow ''channel'' and a clear delineation of the plume extent. That facilitated the design of the closed-loop bioremediation system, consisting of two downgradient pumping wells to completely capture the plume and two pairs of bi-level injection wells located upgradient of the plume. The purged groundwater from the two pumping wells after amending with dissolved oxygen is directly reinjected to the two pairs of upgradient bi-level injection wells. In addition, the performance of the system is monitored by 17 multilevel piezometers. Each piezometer consists of four vertical sampling levels, providing a total of 68 sampling points to fully define the three-dimensional characteristics of the BTEX and DO plumes. Based on a hydrograph analysis of the groundwater data, the closed-loop bioremediation system has been operating properly. In addition, a particle tracking analysis showed groundwater flowlines converge to the pumping wells demonstrating the effectiveness of the plume capture. The trend analysis showed a consistent decline of BTEX concentrations at all of the 68 sampling points

  2. The National Analysis Facility at DESY - status and use cases by the participating experiments

    Science.gov (United States)

    Aplin, S.; Ehrenfeld, W.; Haupt, A.; Kemp, Y.; Langenbruch, C.; Leffhalm, K.; Lucaci-Timoce, A.; Stadie, H.

    2011-12-01

    The German National Analysis Facility (NAF) was set up at DESY, starting end of 2007 in the context of the Helmholtz Alliance "Physics at the Terascale". The NAF complements the DESY and the German Grid resources, and hence offers users from the German HEP institutes the best possible environment for data analysis. In the first part, the key aspects and components of the NAF are briefly presented with an emphasis on recent improvements. In the second part, the use cases of the three participating LHC experiments, ATLAS, CMS and LHCb, will be presented. Differences and commonalities in the usage of the NAF will be shown. Special emphasis will be placed on the usage of PROOF, whose usage on the NAF has been pioneered by CMS. It is now adapted by ATLAS. The third part will concentrate on how the NAF was used for detector optimisation studies in the preparation of one of the ILC Lol's (ILD 2009), as well as how CALICE uses the NAF for the analysis of their data taken in several test beam experiments performed for detector R & D. Finally, future developments of the NAF are presented.

  3. SPECIAL ANALYSIS AIR PATHWAY MODELING OF E-AREA LOW-LEVEL WASTE FACILITY

    Energy Technology Data Exchange (ETDEWEB)

    Hiergesell, R.; Taylor, G.

    2011-08-30

    This Special Analysis (SA) was initiated to address a concern expressed by the Department of Energy's Low Level Waste Disposal Facility Federal Review Group (LFRG) Review Team during their review of the 2008 E-Area Performance Assessment (PA) (WSRC, 2008). Their concern was the potential for overlapping of atmospheric plumes, emanating from the soil surface above SRS LLW disposal facilities within the E-Area, to contribute to the dose received by a member of the public during the Institutional Control (IC) period. The implication of this concern was that the dose to the maximally-exposed individual (MEI) located at the SRS boundary might be underestimated during this time interval. To address this concern a re-analysis of the atmospheric pathway releases from E-Area was required. In the process of developing a new atmospheric release model (ARM) capable of addressing the LFRG plume overlap concern, it became obvious that new and better atmospheric pathway disposal limits should be developed for each of the E-Area disposal facilities using the new ARM. The scope of the SA was therefore expanded to include the generation of these new limits. The initial work conducted in this SA was to develop a new ARM using the GoldSim{reg_sign} program (GTG, 2009). The model simulates the subsurface vapor diffusion of volatile radionuclides as they release from E-Area disposal facility waste zones and migrate to the land surface. In the process of this work, many new features, including several new physical and chemical transport mechanisms, were incorporated into the model. One of the most important improvements was to incorporate a mechanism to partition volatile contaminants across the water-air interface within the partially saturated pore space of the engineered and natural materials through which vapor phase transport occurs. A second mechanism that was equally important was to incorporate a maximum concentration of 1.9E-07 Ci/m{sup 3} of {sup 14}CO{sub 2} in the air

  4. Use of Monte Carlo simulation for computational analysis of critical systems on IPPE's facility addressing needs of nuclear safety

    International Nuclear Information System (INIS)

    The critical facility BFS-1 critical facility was built at the Institute of Physics and Power Engineering (Obninsk, Russia) for full-scale modeling of fast-reactor cores, blankets, in-vessel shielding, and storage. Whereas BFS-1 is a fast-reactor assembly; however, it is a very flexible assembly that can easily be reconfigured to represent numerous other types of reactor designs. This paper describes specific problems with calculation of evaluation neutron physics characteristics of integral experiments performed on BFS facility. The analysis available integral experiments performed on different critical configuration of BFS facility were performed. Calculations of criticality, central reaction rate ratios, and fission rate distributions were carried out by the MCNP5 Monte-Carlo code with different files of evaluated nuclear data. MCNP calculations with multigroup library with 299 energy groups were also made for comparison with pointwise library calculations. (authors)

  5. Boil-off experiments with the EIR-NEPTUN Facility: Analysis and code assessment overview report

    International Nuclear Information System (INIS)

    The NEPTUN data discussed in this report are from core uncovery (boil-off) experiments designed to investigate the mixture level decrease and the heat up of the fuel rod simulators above the mixture level for conditions simulating core boil-off for a nuclear reactor under small break loss-of-coolant accident conditions. The first series of experiments performed in the NEPTUN test facility consisted of ten boil-off (uncovery) and one adiabatic heat-up tests. In these tests three parameters were varied: rod power, system pressure and initial coolant subcooling. The NEPTUN experiments showed that the external surface thermocouples do not cause a significant cooling influence in the rods to which they are attached under boil-off conditions. The reflooding tests performed later on indicated that the external surface thermocouples have some effect during reflooding for NEPTUN electrically heated rod bundle. Peak cladding temperatures are reduced by about 30--40C and quench times occur 20--70 seconds earlier than rods with embedded thermocouples. Additionally, the external surface-thermocouples give readings up to 20 K lower than those obtained with internal surface thermocouples (in the absence of external thermocouples) in the peak cladding temperature zone. Some of the boil-off data obtained from the NEPTUN test facility are used for the assessment of the thermal-hydraulic transient computer codes. These calculations were performed extensively using the frozen version of TRAC-BD1/MOD1 (version 22). A limited number of assessment calculations were done with RELAP5/MOD2 (version 36.02). In this report the main results and conclusions of these calculations are presented with the identification of problem areas in relation to models relevant to boil-off phenomena. On the basis of further analysis and calculations done, changing some of the models such as the bubbly/slug flow interfacial friction correlation which eliminate some of the problems are recommended

  6. Boil-off experiments with the EIR-NEPTUN Facility: Analysis and code assessment overview report

    Energy Technology Data Exchange (ETDEWEB)

    Aksan, S.N.; Stierli, F.; Analytis, G.T. [Paul Scherrer Inst. (PSI), Villigen (Switzerland). Lab. for Thermal-Hydraulics

    1992-03-01

    The NEPTUN data discussed in this report are from core uncovery (boil-off) experiments designed to investigate the mixture level decrease and the heat up of the fuel rod simulators above the mixture level for conditions simulating core boil-off for a nuclear reactor under small break loss-of-coolant accident conditions. The first series of experiments performed in the NEPTUN test facility consisted of ten boil-off (uncovery) and one adiabatic heat-up tests. In these tests three parameters were varied: rod power, system pressure and initial coolant subcooling. The NEPTUN experiments showed that the external surface thermocouples do not cause a significant cooling influence in the rods to which they are attached under boil-off conditions. The reflooding tests performed later on indicated that the external surface thermocouples have some effect during reflooding for NEPTUN electrically heated rod bundle. Peak cladding temperatures are reduced by about 30--40C and quench times occur 20--70 seconds earlier than rods with embedded thermocouples. Additionally, the external surface-thermocouples give readings up to 20 K lower than those obtained with internal surface thermocouples (in the absence of external thermocouples) in the peak cladding temperature zone. Some of the boil-off data obtained from the NEPTUN test facility are used for the assessment of the thermal-hydraulic transient computer codes. These calculations were performed extensively using the frozen version of TRAC-BD1/MOD1 (version 22). A limited number of assessment calculations were done with RELAP5/MOD2 (version 36.02). In this report the main results and conclusions of these calculations are presented with the identification of problem areas in relation to models relevant to boil-off phenomena. On the basis of further analysis and calculations done, changing some of the models such as the bubbly/slug flow interfacial friction correlation which eliminate some of the problems are recommended.

  7. Digitizer architecture analysis for target diagnostics on the National Ignition Facility

    Science.gov (United States)

    Carpenter, A. C.; Clancy, T. J.; Beeman, B.; Bell, P.

    2015-08-01

    This paper covers a systems engineering analysis of existing scope-based Target Diagnostics (TD) on the National Ignition Facility (NIF) at Lawrence Livermore National Laboratory (LLNL), for the purpose of selecting a standard digitizer architecture future diagnostics. Key performance criteria and a summary of test results are presented. Currently of the 60+ Target Diagnostics, at least fifteen use a type of high speed electrical signal data read-out device leading to over 200 digitization channels spread over six types of CRT and digital oscilloscopes, each with multiple models and versions. The proposed standard architecture discussed in this paper allows the NIF to efficiently and reliably operate digitizers that meet the required performance metrics for the lifetime of the NIF. The systems engineering analysis identifies key stakeholders for multiple subsets of scope-based diagnostics including but not limited to the nToFs (neutron Time of Flight), DANTE a broadband, time-resolved x-ray spectrometer, SPBT (South Pole Bang Time), GRH (Gamma Reaction History), and FFLEX (Filter Fluorescer Diagnostic). From these stakeholders, key performance metrics are derived and feed into test and evaluation criteria for different digitizers and architectures.

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

    CERN Document Server

    Byun, S H; Choi, H D

    2002-01-01

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

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

    International Nuclear Information System (INIS)

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

  10. Clustering Logistics Facilities in a Metropolitan Area via a Hot - Spot Analysis

    Directory of Open Access Journals (Sweden)

    İsmail Önden

    2014-12-01

    Full Text Available Hot spots can be described as the high attraction points. Defining the hot spots and clustering approaches in a metropolitan area helps to provide solutions for balancing the freight flows between the sub-areas in the city center. It also helps to provide solutions for secondary problems, such as traffic congestion and air pollution. The technique assists decision-makers in making inferences about the city’s future and taking precautions for sustainability. In this paper, a geographic information systems (GIS analysis tool, spatial statistics based on the Getis Ord* statistics, is used to illustrate which part of Istanbul has hot spots. The hot spot identification is based on logistics activities at the locations of the logistics facilities. The outputs of the analysis are discussed within the context of logistics costs and environmental effects.Anahtar Kelimeler: Mağaza yeri seçimi, delphi tekniği, makro analiz, mağaza yeri seçim kriterleri .

  11. Neutron activation analysis at the Californium User Facility for Neutron Science

    International Nuclear Information System (INIS)

    The Californium User Facility (CUF) for Neutron Science has been established to provide 252Cf-based neutron irradiation services and research capabilities including neutron activation analysis (NAA). A major advantage of the CUF is its accessibility and controlled experimental conditions compared with those of a reactor environment The CUF maintains the world's largest inventory of compact 252Cf neutron sources. Neutron source intensities of ≤ 1011 neutrons/s are available for irradiations within a contamination-free hot cell, capable of providing thermal and fast neutron fluxes exceeding 108 cm-2 s-1 at the sample. Total flux of ≥109 cm-2 s-1 is feasible for large-volume irradiation rabbits within the 252Cf storage pool. Neutron and gamma transport calculations have been performed using the Monte Carlo transport code MCNP to estimate irradiation fluxes available for sample activation within the hot cell and storage pool and to design and optimize a prompt gamma NAA (PGNAA) configuration for large sample volumes. Confirmatory NAA irradiations have been performed within the pool. Gamma spectroscopy capabilities including PGNAA are being established within the CUF for sample analysis

  12. Sextant: an expert system for transient analysis of nuclear reactors and integral test facilities

    International Nuclear Information System (INIS)

    Expert systems provide a new way of dealing with the computer-aided management of nuclear plants by combining several knowledge bases and reasoning modes together with a set of numerical models for real-time analysis of transients. New development tools are required together with metaknowledge bases handling temporal hypothetical reasoning and planning. They have to be efficient and robust because during a transient, neither measurements nor models, nor scenarios are hold as absolute references. SEXTANT is a general purpose physical analyzer intended to provide a pattern and avoid duplication of general tools and knowledge bases for similar applications. It combines several knowledge bases concerning measurements, models and qualitative behavior of PWR with a mechanism of conjecture-refutation and a set of simplified models matching the current physical state. A prototype is under assessment by dealing with integral test facility transients. For its development, SEXTANT requires a powerful shell. SPIRAL is such a toolkit, oriented towards online analysis of complex processes and already used in several applications

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

    Science.gov (United States)

    Byun, S. H.; Sun, G. M.; Choi, H. D.

    2002-07-01

    A prompt gamma activation analysis facility has recently been developed at Hanaro, the 24 MW research reactor in the Korea Atomic Energy Research Institute. Polychromatic thermal neutrons are extracted by setting pyrolytic graphite crystals at a Bragg angle of 45°. The detection system comprises a large single n-type HPGe detector, signal electronics and a fast ADC. Neutron beam characterization was performed both theoretically and experimentally. The neutron flux was measured to be 7.9×10 7 n/cm 2 s in a 1×1 cm 2 beam area at the sample position with a uniformity of 12%. The corresponding Cd-ratio for gold was found to be 266. The beam quality was compared with other representative thermal neutron prompt gamma activation analysis. The detection efficiency was calibrated up to 11 MeV using a set of radionuclides and the (n,γ) reactions of N and Cl. Finally, the sensitivities and the detection limits were obtained for several elements.

  14. Studying international fuel cycle robustness with the GENIUSv2 discrete facilities/materials fuel cycle systems analysis tool

    International Nuclear Information System (INIS)

    GENIUSv2 (Global Evaluation of Nuclear Infrastructure Utilization Scenarios, hereafter 'GENIUS') is a discrete-facilities/materials nuclear fuel cycle systems analysis tool currently under development at the University of Wisconsin-Madison. For a given scenario, it models nuclear fuel cycle facilities (reactors, fuel fabrication, enrichment, etc.), the institutions that own them (utilities and governments), and the regions in which those institutions operate (sub-national, national, and super-national entities). Facilities work together to provide each other with the materials they need. The results of each simulation include the electricity production in each region as well as operational histories of each facility and isotopic and facility histories of each material object. GENIUS users specify an initial condition and a facility deployment plan. The former describes each region and institution in the scenario as well as facilities that exist at the start. The latter specifies all the facilities that will be built over the course of the simulation (and by which institutions). Each region, institution, and facility can be assigned financial parameters such as tax and interest rates, and facilities also get assigned technical information about how they actually operate. Much of the power of the data model comes from the flexibility to model individual entities to a fine level of detail or to allow them to inherit region-, institution-, or facility-type-specific default parameters. Most importantly to the evaluation of regional, national, and international policies, users can also specify rules that define the affinity (or lack thereof) for trade of particular commodities between particular entities. For instance, these rules could dictate that a particular region or institution always buy a certain commodity (ore, enriched UF6, fabricated fuel, etc.) from a particular region or institution, never buy from that region, or merely have a certain likelihood to do so

  15. Potential of the Bucharest 3 MV Tandetron™ for IBA studies of deer antler mineralization

    Science.gov (United States)

    Gomez, S.; Garcia, A.; Landete-Castillejos, T.; Gallego, L.; Pantelica, D.; Pantelica, Ana; Preoteasa, E. A.; Scafes, Adela; Straticiuc, M.

    2016-03-01

    Combined PIXE and PIGE analysis was applied at the new Bucharest Tandetron to investigate biomineralization in two calcified tissues, deer antlers and femur bone. By annual loss and fast re-growth, antlers are a valuable model for bone as a dynamical system. Samples characterized by optical microscopy and histology were analyzed for P, Ca, F, Na, Mg, S, Cl, K, Zn, Sr by 3 MeV proton simultaneous PIXE and PIGE, using a hydroxyapatite standard and other reference materials. Good correlation between methods was found for P, and the concentrations were related to biological data. Antlers showed lower mineralization than femur, with the lowest values in the third antler beam. A power function of mineralization vs. "mineral age" of antlers was found. Thus combined PIXE and PIGE of antlers may bring highly relevant insights in biomineralization research.

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

    OpenAIRE

    2014-01-01

    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, ...

  17. The Choice of Park & Ride Facilities: An Analysis Using a Context-Dependent Hierarchical Choice Experiment

    OpenAIRE

    Bos, D.M.; R E C M van der Heijden; Molin, E.J.E.; H.J.P. Timmermans

    2004-01-01

    Park and Ride facilities have been proposed in several countries to alleviate the accessibility problems in cities. Despite growing accessibility problems, these facilities do not seem to attract the expected number of car drivers and are under-used. In an attempt to measure consumer evaluations of the attributes of Park and Ride facilities, a stated choice experiment, based on the method of hierarchical information integration, was conducted in the city of Nijmegen, The Netherlands. This pap...

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2016-01-01

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

  19. Shuttle landing facility cloud cover study: Climatological analysis and two tenths cloud cover rule evaluation

    Science.gov (United States)

    Atchison, Michael K.; Schumann, Robin; Taylor, Greg; Warburton, John; Wheeler, Mark; Yersavich, Ann

    1993-05-01

    The two-tenths cloud cover rule in effect for all End Of Mission (EOM) STS landings at the Kennedy Space Center (KSC) states: 'for scattered cloud layers below 10,000 feet, cloud cover must be observed to be less than or equal to 0.2 at the de-orbit burn go/no-go decision time (approximately 90 minutes before landing time)'. This rule was designed to protect against a ceiling (below 10,000 feet) developing unexpectedly within the next 90 minutes (i.e., after the de-orbit burn decision and before landing). The Applied Meteorological Unit (AMU) developed and analyzed a database of cloud cover amounts and weather conditions at the Shuttle Landing Facility for a five-year (1986-1990) period. The data indicate the best time to land the shuttle at KSC is during the summer while the worst time is during the winter. The analysis also shows the highest frequency of landing opportunities occurs for the 0100-0600 UTC and 1300-1600 UTC time periods. The worst time of the day to land a shuttle is near sunrise and during the afternoon. An evaluation of the two-tenths cloud cover rule for most data categorizations has shown that there is a significant difference in the proportions of weather violations one and two hours subsequent to initial conditions of 0.2 and 0.3 cloud cover. However, for May, Oct., 700 mb northerly wind category, 1500 UTC category, and 1600 UTC category there is some evidence that the 0.2 cloud cover rule may be overly conservative. This possibility requires further investigation. As a result of these analyses, the AMU developed nomograms to help the Spaceflight Meteorological Group (SMG) and the Cape Canaveral Forecast Facility (CCFF) forecast cloud cover for EOM and Return to Launch Site (RTLS) at KSC. Future work will include updating the two tenths database, further analysis of the data for several categorizations, and developing a proof of concept artificial neural network to provide forecast guidance of weather constraint violations for shuttle

  20. Elementary Analysis on the Technological Features of an Engineering Equipment Facile Diagnosis System

    Institute of Scientific and Technical Information of China (English)

    2001-01-01

    From the point of systemic engineering, the general properties of an engineering equipment fault diagnosis system and the studying object of diagnosis engineering were discussed. With the developing course of fault diagnosis technology, the relationship be-tween facile diagnosis system and diagnosis engineering were also discussed. The basic structure and feature of a facile diagnosis system were discussed, and the isomorphic of a facile diagnosis system and precise diagnosis system was presented. The facile diagnosis requires the perfection of method, pertinence and apriority of knowledge , adaptability of the object being diagnosed and the approach to the aim of the diagnosis result, as well as the outstanding of main functions.

  1. Design and safety analysis report of facilities for research and development of medical radioisotopes

    International Nuclear Information System (INIS)

    For production and research for practical use of radio-pharmaceuticals using for medical treatment and diagnosis, the complex facility offer shield and clean environment is basically required for protecting personnel from radiation, and the product from contamination. The facilities was designed for research and development of medical radioisotopes. This facility was designed to comply with GMP(Good Manufacturing Practice) requirements and safety requirements against radiation. In this technical report, technical requirements and design summary for construction of hot cell and clean room are described. And also, This facility will be utilized for production of Tc-99m generator and R and D of other radio-pharmaceuticals(Ho-166 etc.).

  2. 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.

  3. Mental Disorders among Adolescents in Juvenile Detention and Correctional Facilities: A Systematic Review and Metaregression Analysis of 25 Surveys

    Science.gov (United States)

    Fazel, Seena; Doll, Helen; Langstrom, Niklas

    2008-01-01

    The article presents a meta-analysis of all existing surveys on the prevalence of psychiatric morbidity in adolescents in juvenile detention and correctional facilities in order to assess the prevalence of mental disorders. Findings indicate adolescents in detention are 10 times more likely to suffer from psychosis than the general adolescent…

  4. EFEITO DA APLICAÇÃO PRÉVIA DE ETHEPHON EM AMEIXEIRA (Prunus salicina Lindl E DO IBA NO ENRAIZAMENTO DE SUAS ESTACAS

    Directory of Open Access Journals (Sweden)

    L.F. DUTRA

    1998-05-01

    Full Text Available O experimento foi realizado em casa de vegetação com nebulização intermitente com o objetivo de verificar o efeito do ethephon, aplicado às plantas, e do ácido indolbutírico no enraizamento de estacas de ramos das cultivares Frontier, Reubennel, Ace, Songold, Beauty e Roxa de Itaquera. As plantas foram pulverizadas com ethephon (ácido 2-cloroetil fosfônico nas concentrações de 0 (zero, 50 e 100 mg.l-1. Foram coletados ramos do ano e destes, retirou-se estacas medianas, com comprimento de 15cm e um par de folhas, as quais foram tratadas com ácido indolbutírico (IBA de formulação líquida nas concentrações de 0 (zero e 3000 mg.l-1, com tempo de imersão de 5 segundos. As estacas foram acondicionadas em sacos de polietileno contendo vermiculita como substrato. Observou-se que o ethephon aumentou o percentual de enraizamento da cultivar Beauty e o IBA aumentou o percentual de enraizamento das cultivares Roxa de Itaquera, Songold e Beauty. Concluiu-se ainda que existe diferença de potencial de enraizamento entre as cultivares de ameixeira, sendo que apresentaram maior enraizamento as cultivares Frontier e a Ace.The work was carried out in a greenhouse with intermitent mist to verify the effect of ethephon (2-chloroetyl phosphonic acid in plants, applied one week before of branch collection, and later treatment with indolebutyric acid (IBA on rooting of cuttings of Frontier, Reubennel, Ace, Songold, Beauty and Roxa de Itaquera cultivars. The plants were sprayed with ethephon at 0 (zero; 50 and 100 mg.l-1 concentrations. Branches of the year from eight years old plants were collected and from them median cuttings departed with 15cm lenght and two leaves. Later, they were treated with IBA at 0 (zero and 3000 mg.l-1 concentrations for 5 seconds immersion. The cuttings were packed in polietylene bags containing vermiculite with substrate. Ethephon increased the rooting percentage of Beauty cultivar and the IBA increased the rooting

  5. Impacts of transportation on a test and evaluation facility for nuclear waste disposal: a systems analysis

    International Nuclear Information System (INIS)

    An essential element of the Test and Evaluation Facility (TEF) is a waste packaging facility capable of producing a small number Test and Evaluation Facility of packages consisting of several different waste forms. The study envisions three scenarios for such a packaging facility: (1) modify an existing hot cell facility such as the Engine Maintenance Assembly and Disassembly (EMAD) facility at the Nevada Test Site so that it can serve as a packaging facility for the TEF. This scenario is referred to as the EMAD Option. (2) Build a new generic packaging facility (GPF) at the site of the TEF. In other words, colocate the GPF and the TEF. This scenario is referred to as the GPF Option, and (3) utilize the EMAD facility in conjunction with a colocated GPF (of minimal size and scope) at the TEF. This scenario is referred to as the Split Option. The results of the system study clearly bring out the fact that transportation has a significant impact on the selection and siting of the waste packaging facility. Preliminary conclusions, subject to the assumptions of the study, include the following: (1) regardless of the waste form, the GPF option is preferable to the other two in minimizing both transportation costs and logistical problems, (2) for any given scenario and choice of waste forms, there exists a candidate TEF location for which the transportation costs are at a minimum compared to the other locations, (3) in spite of the increased transportation costs and logistical complexity, the study shows that the overall system costs favor modification of an existing hot cell facility for the particular case considered

  6. Inadvertent Intruder Analysis For The Portsmouth On-Site Waste Disposal Facility (OSWDF)

    Energy Technology Data Exchange (ETDEWEB)

    Smith, Frank G.; Phifer, Mark A.

    2014-01-22

    The inadvertent intruder analysis considers the radiological impacts to hypothetical persons who are assumed to inadvertently intrude on the Portsmouth OSWDF site after institutional control ceases 100 years after site closure. For the purposes of this analysis, we assume that the waste disposal in the OSWDF occurs at time zero, the site is under institutional control for the next 100 years, and inadvertent intrusion can occur over the following 1,000 year time period. Disposal of low-level radioactive waste in the OSWDF must meet a requirement to assess impacts on such individuals, and demonstrate that the effective dose equivalent to an intruder would not likely exceed 100 mrem per year for scenarios involving continuous exposure (i.e. chronic) or 500 mrem for scenarios involving a single acute exposure. The focus in development of exposure scenarios for inadvertent intruders was on selecting reasonable events that may occur, giving consideration to regional customs and construction practices. An important assumption in all scenarios is that an intruder has no prior knowledge of the existence of a waste disposal facility at the site. Results of the analysis show that a hypothetical inadvertent intruder at the OSWDF who, in the worst case scenario, resides on the site and consumes vegetables from a garden established on the site using contaminated soil (chronic agriculture scenario) would receive a maximum chronic dose of approximately 7.0 mrem/yr during the 1000 year period of assessment. This dose falls well below the DOE chronic dose limit of 100 mrem/yr. Results of the analysis also showed that a hypothetical inadvertent intruder at the OSWDF who, in the worst case scenario, excavates a basement in the soil that reaches the waste (acute basement construction scenario) would receive a maximum acute dose of approximately 0.25 mrem/yr during the 1000 year period of assessment. This dose falls well below the DOE acute dose limit of 500 mrem/yr. Disposal inventory

  7. Economic Analysis for the Establishment of a Dry Dates Irradiation Facility at El Wadi - El Gedid Governorate

    International Nuclear Information System (INIS)

    The present study discus the economic analysis of the establishing dry dates irradiation facility at El Wadi El Gadid governorate. This study was divided into three sections the first section includes the arrangement of the equation of simple regression foretelling the future production for dry dates and radiation source activity , the second section was studied the financial analysis for the project. The third section includes the suitable commodities mix to full off the capacity

  8. The state of art of the NIES-TERRA (Accelerator analysis facility, National Institute for Environmental Studies)

    Energy Technology Data Exchange (ETDEWEB)

    Yoneda, Minoru; Shibata, Yasuyuki; Tanaka, Atsushi; Uchida, Masao; Hirota, Masashi; Uehiro, Takashi; Morita, Masatoshi [National Inst. for Environmental Studies Tsukuba, Ibaraki (Japan)

    2001-02-01

    The status of the NIES-TERRA accelerator facility in FY1999 is presented. Accelerator Mass Spectrometry (AMS) has been performed mainly for the routine measurement of environmental, geological, archaeological samples. Analysis has been done for Al-26, Be-10, as well as C-14. The operation experiences are described. The accelerator has been operated 23000 hours since its construction. Minor troubles during the operation are reported. The pretreatment system, required for the analysis in further precision, is under development. (A. Yamamoto)

  9. CFD analysis and optimization of a liquid lead–bismuth loop target for ISOL facilities

    International Nuclear Information System (INIS)

    In the context of the forthcoming next generation of Radioactive Ion Beams (RIBs) facilities based on an Isotope Separation On Line (ISOL) method, the development of production targets capable of dissipating the high power deposited by the primary beam is a major challenge. The concept of a high-power target based on a liquid Pb–Bi loop incorporating a heat-exchanger and a diffusion chamber was proposed within EURISOL DS and is being developed within the LIEBE project. Due to the non-static character of the target, specific hydrodynamics issues are of concern. In this paper, these issues are studied mostly based on three-dimensional (3D) Computational Fluid Dynamics analysis of the flow of the Lead Bismuth Eutectic (LBE) target, resulting in optimized designs. The concept and hydrodynamic challenges of generating RIBs from a liquid-metal-loop target irradiated with a high-power primary beam are presented. The optimization of the target design has been conducted keeping in mind the need for a fast and efficient release of short-lived isotopes. This study shows that approximately 100 ms after the proton pulse the irradiated liquid-metal is entirely and uniformly evacuated from the irradiation volume and spread in a shower of small droplets (100-μm radii), in order to reduce the diffusion length of isotopes. Solutions to deal with the typical cavitation risk due to the presence of low-pressure zones in the liquid have also been found and simulated

  10. Analysis of beam on target interaction in a neutron-source test facility

    International Nuclear Information System (INIS)

    The need is urgent for a high-flux, high-energy neutron test facility to evaluate the performance of fusion reactor materials. An accelerator-based deuterium-lithium source is generally considered the most reasonable approach to a high-flux neutron source in the near future. The idea is to bombard a high-energy (20--40 MeV) deuteron beam into a lithium jet target to produce high-energy neutrons in order to simulate a fusion reactor environment via the Li (d,n) nuclear stripping reaction. Deposition of the high-energy deuteron beam and the subsequent response of the lithium jet are modeled and evaluated in detail. To assess the feasibility of this concept, the analysis is done parametrically for various deuteron beam energies, beam currents, and jet velocities. A main requirement for a successful operation is to keep the free jet surface at a minimum temperature to reduce surface evaporation of lithium into the vacuum system. The effects of neutron-generated heating and irradiation on the jet-supporting back plate are also evaluated. The back plate must maintain a reasonable lifetime during system operation

  11. Prompt gamma ray activation analysis using neutron beam from THOR facility

    International Nuclear Information System (INIS)

    A reactor-based facility for neutron-capture prompt gamma-ray spectrometry for activation analysis has been installed at the one megawatt Tsing Hua Open-pool Reactor. The system consists a neutron beam port with collimators, irradiation stand, external beam tube, neutron beam dump, and counting system. The counting system consists of a 25 % n-type high purity germanium main gamma-ray detector, a 9'' x 10'' NaI(T1) anti-Compton detector shield, and Compton-suppressed electronics coupled to the CANBERRA S-88 Multi-parameter analyzer. Although the neutron beam at the sample irradiation station has an intensity of only 1,300,000 n/cm2s with a cadmium ratio of 26 : 1, the background levels of the on-line measurement in the mixed neutron/gamma field are sufficiently low, resulting a satisfactory detection of many elemental composition in samples. The lower limits of detection of 35 elements in sample matrix of the present system and the current applications are discussed. (author)

  12. Analysis of shielding calculation methods for 16- and 64-slice computed tomography facilities

    Energy Technology Data Exchange (ETDEWEB)

    Moreno, C; Cenizo, E; Bodineau, C; Mateo, B; Ortega, E M, E-mail: c_morenosaiz@yahoo.e [Servicio de RadiofIsica Hospitalaria, Hospital Regional Universitario Carlos Haya, Malaga (Spain)

    2010-09-15

    The new multislice computed tomography (CT) machines require some new methods of shielding calculation, which need to be analysed. NCRP Report No. 147 proposes three shielding calculation methods based on the following dosimetric parameters: weighted CT dose index for the peripheral axis (CTDI{sub w,per}), dose-length product (DLP) and isodose maps. A survey of these three methods has been carried out. For this analysis, we have used measured values of the dosimetric quantities involved and also those provided by the manufacturer, making a comparison between the results obtained. The barrier thicknesses when setting up two different multislice CT instruments, a Philips Brilliance 16 or a Philips Brilliance 64, in the same room, are also compared. Shielding calculation from isodose maps provides more reliable results than the other two methods, since it is the only method that takes the actual scattered radiation distribution into account. It is concluded therefore that the most suitable method for calculating the barrier thicknesses of the CT facility is the one based on isodose maps. This study also shows that for different multislice CT machines the barrier thicknesses do not necessarily become bigger as the number of slices increases, because of the great dependence on technique used in CT protocols for different anatomical regions.

  13. Analysis of beam-on-target interaction in a neutron-source test facility

    International Nuclear Information System (INIS)

    The need is urgent for a high-flux, high-energy neutron test facility to evaluate the performance of fusion reactor materials. An accelerator-based deuterium-lithium source is generally considered the most reasonable approach to a high-flux neutron source in the near future. The idea is to bombard a high-energy (20--40 MeV) deuteron beam into a lithium jet target to produce high-energy neutrons in order to simulate a fusion reactor environment via the Li (d, n) nuclear stripping reaction. Deposition of the high-energy deuteron beam and the subsequent response of the lithium jet are modeled and evaluated in detail. To assess the feasibility of this concept, the analysis is done parametrically for various deuteron beam energies, beam currents, and jet velocities. A main requirement for a successful operation is to keep the free jet surface at a minimum temperature to reduce surface evaporation of lithium into the vacuum system. The effects of neutron-generated heating and irradiation on the jet-supporting back plate are also evaluated. The back plate must maintain a reasonable lifetime during system operation

  14. CFD analysis and optimization of a liquid lead–bismuth loop target for ISOL facilities

    Energy Technology Data Exchange (ETDEWEB)

    Houngbo, D., E-mail: dhoungbo@sckcen.be [Belgian Nuclear Research Centre (SCK-CEN), Boeretang 200, B-2400 Mol (Belgium); Department of Flow, Heat and Combustion Mechanics, Ghent University (UGent), St.-Pietersnieuwstraat 41, B-9000 Gent (Belgium); Popescu, L.; Schuurmans, P. [Belgian Nuclear Research Centre (SCK-CEN), Boeretang 200, B-2400 Mol (Belgium); Delonca, M.; Losito, R.; Maglioni, C.; Stora, T. [CERN, 1211 Geneva 23 (Switzerland); Bricault, P. [TRIUMF, 4004 Wesbrook Mall, Vancouver, B.C., V6T 2A3 (Canada); Vierendeels, J. [Department of Flow, Heat and Combustion Mechanics, Ghent University (UGent), St.-Pietersnieuwstraat 41, B-9000 Gent (Belgium)

    2015-03-21

    In the context of the forthcoming next generation of Radioactive Ion Beams (RIBs) facilities based on an Isotope Separation On Line (ISOL) method, the development of production targets capable of dissipating the high power deposited by the primary beam is a major challenge. The concept of a high-power target based on a liquid Pb–Bi loop incorporating a heat-exchanger and a diffusion chamber was proposed within EURISOL DS and is being developed within the LIEBE project. Due to the non-static character of the target, specific hydrodynamics issues are of concern. In this paper, these issues are studied mostly based on three-dimensional (3D) Computational Fluid Dynamics analysis of the flow of the Lead Bismuth Eutectic (LBE) target, resulting in optimized designs. The concept and hydrodynamic challenges of generating RIBs from a liquid-metal-loop target irradiated with a high-power primary beam are presented. The optimization of the target design has been conducted keeping in mind the need for a fast and efficient release of short-lived isotopes. This study shows that approximately 100 ms after the proton pulse the irradiated liquid-metal is entirely and uniformly evacuated from the irradiation volume and spread in a shower of small droplets (100-μm radii), in order to reduce the diffusion length of isotopes. Solutions to deal with the typical cavitation risk due to the presence of low-pressure zones in the liquid have also been found and simulated.

  15. Analysis of acoustic data from UK sodium/water reaction test facilities

    International Nuclear Information System (INIS)

    This paper describes acoustic measurements made during a number of sodium/water reaction experiments in the UK. The tests have included water and steam injections through both realistic (fatigue crack) defects and machined orifices and have covered a range of experimental conditions including those appropriate to the inlet and outlet regions of the EFR steam generators. Injection rates were typically in the range 0.1 to 30 g/s. Where possible, gas injections were also included in the test programme for comparison, since it is anticipated that a practical SGU acoustic leak detection system would include a facility for gas injections to allow system calibration, and to confirm transmission properties within the SGU. The test sections were instrumented with accelerometers on waveguides and in some cases included an under-sodium microphone situated about 300mm above the reaction zone. Tape recordings were made during the tests and used for detailed analysis off-line, although an audible output from one of the acoustic channels was used to monitor the progress of the injections and provide information for the rig operators. A comparison of the signal amplitudes measured during the experiments with typical reactor background noise was made and an estimate of the detection sensitivity of an acoustic monitoring system was deduced. 3 refs, 5 figs, 1 tab

  16. Analysis of different design options for the beam target of the energy amplifier demonstration facility

    International Nuclear Information System (INIS)

    A thermal fluid dynamic analysis of different design options of a high intensity proton beam target has been performed for the 80 MW Demonstration Facility of the Energy Amplifier proposed by C. Rubbia (EADF), presently under development in Italy by Ansaldo, CRS4, ENEA and INFN. The present machine is driven by a 600 MeV proton accelerator at a current varying from about 2 to 6 mA during the fuel cycle. Two options have been considered: (i) a 'windowless' design, where the free surface of the spallation material (liquid Pb-Bi eutectic) is the interface with the void of the beam transport line, and (ii) a 'window' design, where a physical separation is made by means of a 9Cr 1Mo V Nb martensitic steel hemispherical window. Both designs have advantages and drawbacks. The beam window is a delicate element whose lifetime is at present moment difficult to assess, since it is affected by the combined action of liquid metal corrosion, radiation damage (induced by protons and high energy neutrons interactions) and thermal fatigue (induced by stress cycling due to beam trips and beam interruptions). The windowless option is less sensible to radiation damage, but its design is more complex for the presence of a free surface flow and of Pb-Bi vapours in the beam pipe. (author)

  17. Sampling and analysis plan for the preoperational environmental survey of the spent nuclear fuel project facilities

    International Nuclear Information System (INIS)

    This sampling and analysis plan will support the preoperational environmental monitoring for construction, development, and operation of the Spent Nuclear Fuel (SNF) Project facilities, which have been designed for the conditioning and storage of spent nuclear fuels; particularly the fuel elements associated with the operation of N-Reactor. The SNF consists principally of irradiated metallic uranium, and therefore includes plutonium and mixed fission products. The primary effort will consist of removing the SNF from the storage basins in K East and K West Areas, placing in multicanister overpacks, vacuum drying, conditioning, and subsequent dry vault storage in the 200 East Area. The primary purpose and need for this action is to reduce the risks to public health and safety and to the environment. Specifically these include prevention of the release of radioactive materials into the air or to the soil surrounding the K Basins, prevention of the potential migration of radionuclides through the soil column to the nearby Columbia River, reduction of occupational radiation exposure, and elimination of the risks to the public and to workers from the deterioration of SNF in the K Basins

  18. Analysis of kinetics experiments in LEU-HTR configurations of the PROTEUS facility

    International Nuclear Information System (INIS)

    On the recommendation of the International Atomic Energy Agency's (IAEA's) working group on gas-cooled reactors, the IAEA has established a coordinated research program (CRP) on the validation of safety-related physics calculations for low-enriched uranium (LEU)-fueled high-temperature gas-cooled reactors (HTGRs). The objective of the CRP is to provide safety-related physics data for LEU-fueled HTGRs for use in validating reactor physics codes and methods used by participating countries for analysis of their designs. At present, the main activities within the CRP are being carried out by the international project now under way at the PROTEUS critical facility at the Paul Scherrer Institute in Villigen, Switzerland. Within this project, critical experiments will be conducted for HTGR-LEU systems to determine core reactivity; flux and power profiles; reaction rate ratios; worth of control rods, including reflector control rods; worth of burnable poisons; and the effects of water ingress on these parameters. Of particular interest are quality-assured (benchmark type) measurements of the worth of control rods located in the graphite reflector. Two independent techniques have been selected for this purpose; the pulsed neutron source (PNS) and the inverse kinetics methods

  19. Calibration Report for the WRAP Facility Gamma Energy Analysis System [104-ND-06-102A

    Energy Technology Data Exchange (ETDEWEB)

    WILLS, C.E.

    2000-02-15

    The Waste Receiving And Processing facility (WRAP) adheres to providing gamma-ray spectroscopy instrument calibrations traceable to the National Institute for Standards and Technology (NIST) standards. The detectors are used to produce quantitative results for the Waste Isolation Pilot Plant (WIPP) and must meet calibration programmatic calibration goals. Instruments must meet portions of ANSI N42.14, 1978 guide for Germanium detectors. The Non-Destructive Assay (NDA) Gamma Energy Analysis (GEA) utilizes NIST traceable line source standards for the detector system calibrations. The counting configuration is a series of drums containing the line sources and different density filler matrices. The drums are used to develop system efficiencies with respect to density. The efficiency and density correction factors are required for the processing of drummed waste materials of similar densities. The calibration verification is carried out after the calibration is deemed final, by counting a second drum of NIST traceable sources. Three in-depth calibrations have been completed on one of the two systems to date, the first being the system acceptance plan. This report has a secondary function; that being the development of the instrument calibration errors which are to be folded into the Total Instrument Uncertainty document, HNF-4050.

  20. Accident analysis for aircraft crash into hazardous facilities: A statistical primer

    International Nuclear Information System (INIS)

    The DOE Standard 3014-96, Accident Analysis for Aircraft Crash into Hazardous Facilities provides a robust statistical framework useful for assessing the release frequency for hazardous materials used in many industrial operations. The formulae and the verbal instructions for calculating screening quantities and frequencies in the DOE Standard are consistent with an unstated underlying six-term expression for estimating the annual number of aircraft-impact-related releases. The six-term formula is here shown to result from iterated application of Bayes' rule. The statistical concepts underlying this formula are explained; the six-term model is then developed and its components related to the corresponding elements of the four-factor model presented in the Standard. The six-term model is shown to be consistent with the instructions given in the Standard for calculating the screening and evaluation quantities using the four-factor model. The difference between screening and evaluation of release frequencies is clarified. Discussion of the six-term model shows clearly how conservative approximations to its conditional probability terms lead to simple and efficient screening formulae. A numerical example is provided to demonstrate a screening calculation

  1. An Analysis of the Charter School Facility Landscape in New Jersey

    Science.gov (United States)

    National Alliance for Public Charter Schools, 2013

    2013-01-01

    In spring of 2012, the New Jersey Charter Schools Association, the Colorado League of Charter Schools, and the National Alliance for Public Charter Schools worked to collect evidence that would accurately portray both the adequacy of charter school facilities and the average spending for facilities out of charter schools' operating budgets in New…

  2. An Analysis of the Charter School Facility Landscape in Rhode Island

    Science.gov (United States)

    National Alliance for Public Charter Schools, 2013

    2013-01-01

    In winter of 2013, the Rhode Island League of Charter Schools, the Colorado League of Charter Schools, and the National Alliance for Public Charter Schools worked to collect evidence that would accurately portray both the adequacy of charter school facilities and the average amount of operating funds spent by charter schools on facilities.…

  3. Post test analysis of counterpart tests in LOBI, SPES, BETHSY, LSTF facilities performed with the CATHARE2 code

    International Nuclear Information System (INIS)

    The present paper deals with the evaluation of results from the application of the thermalhydraulic system code CATHARE2V1.3U to the post test analysis of six co-called counterpart tests performed in four PWR facilities. These are LOBI/Mod2, SPES, BETHSY and LSTF facilities operated respectively at the European Research Centre of Ispra (Italy), at Piacenza (Italy), at Grenoble (France) and at Tokaj Mura (Japan). The activity is a part of a wide research having as main objective the evaluation of scaling capabilities of the CATHARE2 code. (author)

  4. Qualitative and quantitative analysis of CATHARE2 code results of counterpart test calculations in LOBI, SPES, BETHSY, LSTF facilities

    International Nuclear Information System (INIS)

    The present paper deals with the qualitative and quantitative accuracy evaluation of results from the application of the thermalhydraulic system code CATHARE2V1.3U to the post test analysis of six so-called counterpart tests performed in four PWR facilities. These are LOBI/Mod2, SPES, BETHSY and LSTF facilities operated respectively at the European Research Centre of Ispra (Italy), at Piacenza (Italy), at Grenoble (France) and at Tokai Mura (Japan). The activity is a part of a wide research having as main objective the evaluation of scaling capabilities of the CATHARE2 code. (author)

  5. Pursuit of improvement in uranium bulk analysis at the clear facility for safeguards environmental samples

    International Nuclear Information System (INIS)

    Full text: In order to contribute to the IAEA strengthened safeguards system, a project started in Japan Atomic Energy Research Institute (JAERI) in 1998. Consequently, a clean room facility called as CLEAR, the Clean Laboratory for Environmental Analysis and Research, was constructed in June 2001 at JAERI Tokai and the analytical techniques of ultra-trace nuclear materials in environmental samples are being developed. As for the bulk analysis, performance of inductively-coupled plasma mass spectrometry (ICP-MS) was mainly examined because sample preparation for ICP-MS is simpler than that for thermal ionization mass spectrometry (TIMS). Interference of polyatomic ion (such as PtAr+) and coexisting element (such as Na) on the uranium ions, as well as mass bias caused by ICP-MS operating conditions, has been investigated for precise measurement on uranium isotope ratio. The authors have also studied on the uranium blanks during sample treatment process. The blank value below 10 pg uranium per sample treatment was obtained: dominant origins were elution from Teflon vessel surface in acid heating process of the sample to dry up. The work is in progress to minimize the blank. Compared with the process blank and the minimum uranium amount for isotope ratio measurement by ICP-MS (ca. 10 pg for natural uranium), the swipe cotton (Texwipe-304) which is currently used for IAEA Environmental Sampling includes much more amount of natural uranium in several nano-grams. If the amount of uranium collected on Texwipe-304 is small, sensitive and reliable measurement on isotope ratio will be impossible by bulk analysis. The authors are seeking alternative swipe materials with less amount of uranium. Recently, one of the authors devised an effective technique for recovery of uranium-containing particles from Texwipe-304. The technique, named as Vacuum Suction Method, uses a combination of polycarbonate membrane filters and a macro-pipette tip, which is connected to a vacuum pump

  6. Characterization Of Normalization Factor In TRIGA 2000 Bandung Reactor Pneumatic Facility for Neutron Activation Analysis

    International Nuclear Information System (INIS)

    Neutron activation analysis using synthetic multielement comparators is prevalent method for multielement analysis. This comparison method has several limitations such as preparation of synthetic standard is time consuming and needs high cost. In order to overcome such difficulties, the use of normalization factor of sample geometry and irradiation position as well need to be done. The normalization factor is used to overcome flux inhomogeneity, so that the used of standard reference material can be minimized. In this research, characterization of normalization factor in pneumatic facility of TRIGA 2000 Bandung reactor, have been done. The determination was done for two sample positions (bottom and top) using polyethylene container. The average normalization factor at 60,30 and 15 second irradiation at 1500 k Watt for Cu sample gave values of 1.2848, 1.2908 and 1.3348 respectively. The effect of power reactor fluctuation on normalization factor was also studied. Fluctuation of power reactor under 2 % for sample position top and bottom gave deviation values of 3.1699% and 1.6238% respectively. The determination of normalization factor for Ti, I, V and AI reference standards have also been done. Normalization factor at 60 second irradiation at 1500 k Watt for Ti, I, V and AI reference standards gave mean values of 1.2554, 1.2066, 1.3625 and 1.2475 respectively. Normalization factor obtained of this research have a narrow range (<6.2%). The results obtained can be use in developing the NAA method, to minimize the spent of time, energy and cost

  7. The analysis of interface emulsion detector for the OPERA experiment in JAPAN Scanning facility

    International Nuclear Information System (INIS)

    The OPERA experiment, designed to search for neutrino oscillations, started its physics run in July 2008. It is the most recent emulsion-counter hybrid experiment. In this experiment two different types of emulsion detectors are used. One is called Emulsion Cloud Chamber (ECC), and is used as a target. The other is called Changeable Sheet (CS), which is attached to the downstream side of each ECC to identify the ECC in which a tagged neutrino interaction occurred. The CS interfaces rough tracking information obtained in the electronic detectors to the ECC and therefore is a key element of the emulsion-counter hybrid experiment. As a first step, a CS selected by electronic detectors is scanned and analyzed to decide if the ECC is to be developed and analyzed in detail; a few CS are usually to be analyzed to identify an ECC for each tagged event due to the inaccuracy of the electronic detectors. The CS has a large scanning area and therefore Japan and Europe (Gran Sasso) are sharing in the CS analysis load to handle the scanning job. In this paper, the CS analysis method developed for the Japan scanning facility is described in detail. 100 million tracks are read out on each CS by an automatic emulsion read-out system ( S-UTS ), most of them are so-called fake tracks mainly due to low momentum Compton electrons or random noise and a few real tracks from a tagged neutrino interaction have to be picked up among a huge background. A dedicated method to reject this background without losing real tracks has been developed on the basis of analyzing track data obtained by S-UTS and combining these data with a final selection using additional information on multiple Coulomb scattering of candidate tracks obtained by human eye check to eliminate a remaining background. Performance of this method is shown to be sufficient for the OPERA experiment.

  8. The technical specification for seismic analysis for CNS facilities and the basic design for CNS instrument island

    International Nuclear Information System (INIS)

    This report details the technical specification on seismic analysis for CNS system facilities and the basic design for CNS instrument island which will be installed in the HANARO reactor building. The technical specification on seismic analysis describes the classification of a seismic category, the procedure of a seismic analysis, and the requirements of a seismic design. The design response spectrum for SSE and OBE are presented for the seismic analysis for seismic category I. The technical specification on the seismic analysis includes the procedure for FEM modelling, modal analysis, time history analysis for generation of floor response spectrum, response spectrum analysis. The CNS instrument islands is classified as the seismic category I. Basic design drawings and requirements for ensuring the location and the conceptual shape of CNS instrument islands were developed considering the design interface of as-built installed structures. Based on the basic design and the results of field measurements the detail design of CNS instrument islands will be carried out

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

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

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

    Energy Technology Data Exchange (ETDEWEB)

    Dionne, B.J.; Morris, S.C. III; Baum, J.W. [and others

    1998-01-01

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

  12. 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.

  13. New-doses limits introduction analysis for the design and operation of teletherapy facilities established by IAEA

    International Nuclear Information System (INIS)

    A design of a typical teletherapy facility was made considering a Co-60 rotating unit and using critical parameters, taking into account as a design base the dose limits established in the Safety Series No. 9 (1), and Safety Series No.115-I (2), shielding thickness when the dose limits were changed. An increment in the required thickness of 1,35 CHR for controlled areas and 2,37 CHR for non-controlled areas were found. This work considered the selection of four different types of teletherapy facilities using Co-60 sources, with different design and type of used unit. An analysis of thickness was made taking into account both the original values for the design and the real operation values in each facility. In order to determine the necessary changes for the wall thicknesses when the new recommendations are applied. (authors). 4 refs., 3 tabs

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

    International Nuclear Information System (INIS)

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

  15. Design basis threat analysis and implementation of the physical protection system at Nuclear Facility of BATAN Yogyakarta

    International Nuclear Information System (INIS)

    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

  16. Analysis of Hanford-based Options for Sustainable DOE Facilities on the West Coast

    Energy Technology Data Exchange (ETDEWEB)

    Warwick, William M.

    2012-06-30

    Large-scale conventional energy projects result in lower costs of energy (COE). This is true for most renewable energy projects as well. The Office of Science is interested in its facilities meeting the renewable energy mandates set by Congress and the Administration. Those facilities on the west coast include a cluster in the Bay Area of California and at Hanford in central Washington State. Land constraints at the California facilities do not permit large scale projects. The Hanford Reservation has land and solar insolation available for a large scale solar project as well as access to a regional transmission system that can provide power to facilities in California. The premise of this study is that a large-scale solar project at Hanford may be able to provide renewable energy sufficient to meet the needs of select Office of Science facilities on the west coast at a COE that is competitive with costs in California despite the lower solar insolation values at Hanford. The study concludes that although the cost of solar projects continues to decline, estimated costs for a large-scale project at Hanford are still not competitive with avoided power costs for Office of Science facilities on the west coast. Further, although it is possible to transmit power from a solar project at Hanford to California facilities, the costs of doing so add additional costs. Consequently, development of a large- scale solar project at Hanford to meet the renewable goals of Office of Science facilities on the west coast is currently uneconomic. This may change as solar costs decrease and California-based facilities face increasing costs for conventional and renewable energy produced in the state. PNNL should monitor those cost trends.

  17. Neutron shielding analysis for remote handled transuranic waste containers in facility casks at the Waste Isolation Pilot Plant

    International Nuclear Information System (INIS)

    Neutron shielding characteristics of the Waste Isolation Pilot Plant facility cask have been quantified for a variety of combinations of neutron sources and waste matrices which would potentially be handled in waste containers. The neutron attenuation and neutron environment of the waste container and the facility cask have been analyzed to ensure that the design requirement of neutron dose rate will be met under the combinations of the source and waste matrix conditions. The analyses considered the ranges of neutron source spectrum and waste matrices which combine to produce the minimum neutron shielding worth of the facility cask. One-dimensional analyses were performed with discrete ordinate transport theory methods using multigroup neutron cross section data. The results discussed in this report demonstrate the effect of source spectrum and waste container matrix on predicted neutron dose rates adjacent to the unshielded waste container and the surface of the facility cask. An evaluation of the uncertainties in predicted neutron dose rates is provided which results in an assessment of the maximum measured neutron dose rate external to the facility cask. A description of the analytical models developed, the analysis methodology, the neutron source spectra, and the detailed results are described in this report. 10 refs., 50 figs., 39 tabs

  18. Probabilistic risk analysis for Test Area North Hot Shop Storage Pool Facility

    International Nuclear Information System (INIS)

    A storage pool facility used for storing spent fuel and radioactive debris from the Three Mile Island (TMI) accident was evaluated to determine the risk associated with its normal operations. Several hazards were identified and examined to determine if any any credible accident scenarios existed. Expected annual occurrence frequencies were calculated for hazards for which accident scenarios were identified through use of fault trees modeling techniques. Fault tree models were developed for two hazards: (1) increased radiation field and (2) spread of contamination. The models incorporated facets of the operations within the facility as well as the facility itself. 6 refs

  19. Preliminary analysis of the operating characteristics of a generic repository receiving facility: Status report

    International Nuclear Information System (INIS)

    The operating characteristics of a repository receiving facility structured around current technology and practices have been reviewed. Cask turnaround times and operator doses were estimated. Large throughout and long-term receiving operations at a nuclear waste repository result in an unprecedented number of casks being handled. While the current generation of material-handling equipment is adequate to process the casks, personnel radiation exposures for the generic facility analyzed are unacceptably high. This emphasizes the need for development of occupational radiation exposure control concepts for application in repository receiving facilities. 3 refs., 22 figs., 6 tabs

  20. Reference Mission Operational Analysis Document (RMOAD) for the Life Sciences Research Facilities

    Science.gov (United States)

    1987-01-01

    The space station will be constructed during the next decade as an orbiting, low-gravity, permanent facility. The facility will provide a multitude of research opportunities for many different users. The pressurized research laboratory will allow life scientists to study the effects of long-term exposure to microgravity on humans, animals, and plants. The results of these studies will increase our understanding of this foreign environment on basic life processes and ensure the safety of man's long-term presence in space. This document establishes initial operational requirements for the use of the Life Sciences Research Facility (LSRF) during its construction.

  1. IBA analysis of a laser cleaned archaeological metal object: The San Esteban de Gormaz cross (Soria-Spain)

    Energy Technology Data Exchange (ETDEWEB)

    Zucchiatti, A., E-mail: alessandro.zucchiatti@uam.es [CMAM, Universidad Autonoma de Madrid, c/Farady 3, E-28049 Madrid (Spain); Gutierrez Neira, P.C., E-mail: carolina.gutierrez@uam.es [CMAM, Universidad Autonoma de Madrid, c/Farady 3, E-28049 Madrid (Spain); Climent-Font, A., E-mail: acf@uam.es [CMAM, Universidad Autonoma de Madrid, c/Farady 3, E-28049 Madrid (Spain); Escudero, C., E-mail: escremcr@jcyl.es [Centro de Conservacion y Restauracion de Bienes Culturales (CCRBC) de la Junta de Castilla y Leon, C/Carretera No. 2, 47130 Valladolid (Spain); Barrera, M., E-mail: barbarmr@jcyl.es [Centro de Conservacion y Restauracion de Bienes Culturales (CCRBC) de la Junta de Castilla y Leon, C/Carretera No. 2, 47130 Valladolid (Spain)

    2011-12-15

    The object under study, a 12th century gilded copper cross with a wooden core, now almost disappeared, shows the typical features produced by a long burial time: the entire surface of the copper alloys is covered by several layers of degradation products, which hinder the 'legibility' of the cross in terms of the original materials and manufacturing techniques employed. In its cleaning several techniques have been applied and compared (dry and wet laser ablation, mechanical ablation, ultrasound brush). In the intermediate cleaning phase the cross has been extensively analysed with the external proton micro-beam of the Centro de Micro-Analisis de Materiales (CMAM) of the Universidad Autonoma de Madrid. PIXE and RBS techniques have been used in parallel, to asses both the chemical composition and the layered structure of cleaned and original parts with the aim of verifying that none of the object structural features are being modified by the cleaning process leaving intact the possibility of artistic interpretation of the object (e.g. small series production of the cross elements). The recovery of this exceptional ornamental object is made possible by the coordinated work of several professionals coming from various disciplines and aimed at establishing the importance of this cross in terms of its physical appearance and in terms of the manufacturing techniques.

  2. IBA analysis of a laser cleaned archaeological metal object: The San Esteban de Gormaz cross (Soria-Spain)

    Science.gov (United States)

    Zucchiatti, A.; Gutiérrez Neira, P. C.; Climent-Font, A.; Escudero, C.; Barrera, M.

    2011-12-01

    The object under study, a 12th century gilded copper cross with a wooden core, now almost disappeared, shows the typical features produced by a long burial time: the entire surface of the copper alloys is covered by several layers of degradation products, which hinder the "legibility" of the cross in terms of the original materials and manufacturing techniques employed. In its cleaning several techniques have been applied and compared (dry and wet laser ablation, mechanical ablation, ultrasound brush). In the intermediate cleaning phase the cross has been extensively analysed with the external proton micro-beam of the Centro de Micro-Análisis de Materiales (CMAM) of the Universidad Autónoma de Madrid. PIXE and RBS techniques have been used in parallel, to asses both the chemical composition and the layered structure of cleaned and original parts with the aim of verifying that none of the object structural features are being modified by the cleaning process leaving intact the possibility of artistic interpretation of the object (e.g. small series production of the cross elements). The recovery of this exceptional ornamental object is made possible by the coordinated work of several professionals coming from various disciplines and aimed at establishing the importance of this cross in terms of its physical appearance and in terms of the manufacturing techniques.

  3. IBA analysis of a laser cleaned archaeological metal object: The San Esteban de Gormaz cross (Soria-Spain)

    International Nuclear Information System (INIS)

    The object under study, a 12th century gilded copper cross with a wooden core, now almost disappeared, shows the typical features produced by a long burial time: the entire surface of the copper alloys is covered by several layers of degradation products, which hinder the “legibility” of the cross in terms of the original materials and manufacturing techniques employed. In its cleaning several techniques have been applied and compared (dry and wet laser ablation, mechanical ablation, ultrasound brush). In the intermediate cleaning phase the cross has been extensively analysed with the external proton micro-beam of the Centro de Micro-Análisis de Materiales (CMAM) of the Universidad Autónoma de Madrid. PIXE and RBS techniques have been used in parallel, to asses both the chemical composition and the layered structure of cleaned and original parts with the aim of verifying that none of the object structural features are being modified by the cleaning process leaving intact the possibility of artistic interpretation of the object (e.g. small series production of the cross elements). The recovery of this exceptional ornamental object is made possible by the coordinated work of several professionals coming from various disciplines and aimed at establishing the importance of this cross in terms of its physical appearance and in terms of the manufacturing techniques.

  4. Stress Analysis and Evaluation of Piping System in Uranium Liquor Critical Facility

    Institute of Scientific and Technical Information of China (English)

    2008-01-01

    <正>The piplines of the piping system in the uranium liquor critical facility are very thin, so the piping rigidity is bad, the measuring cylinders piping system (Fig. 1) connects the vessel the pump and the rigid

  5. Preliminary Analysis of the Transient Reactor Test Facility (TREAT) with PROTEUS

    Energy Technology Data Exchange (ETDEWEB)

    Connaway, H. M. [Argonne National Lab. (ANL), Argonne, IL (United States); Lee, C. H. [Argonne National Lab. (ANL), Argonne, IL (United States)

    2015-11-30

    The neutron transport code PROTEUS has been used to perform preliminary simulations of the Transient Reactor Test Facility (TREAT). TREAT is an experimental reactor designed for the testing of nuclear fuels and other materials under transient conditions. It operated from 1959 to 1994, when it was placed on non-operational standby. The restart of TREAT to support the U.S. Department of Energy’s resumption of transient testing is currently underway. Both single assembly and assembly-homogenized full core models have been evaluated. Simulations were performed using a historic set of WIMS-ANL-generated cross-sections as well as a new set of Serpent-generated cross-sections. To support this work, further analyses were also performed using additional codes in order to investigate particular aspects of TREAT modeling. DIF3D and the Monte-Carlo codes MCNP and Serpent were utilized in these studies. MCNP and Serpent were used to evaluate the effect of geometry homogenization on the simulation results and to support code-to-code comparisons. New meshes for the PROTEUS simulations were created using the CUBIT toolkit, with additional meshes generated via conversion of selected DIF3D models to support code-to-code verifications. All current analyses have focused on code-to-code verifications, with additional verification and validation studies planned. The analysis of TREAT with PROTEUS-SN is an ongoing project. This report documents the studies that have been performed thus far, and highlights key challenges to address in future work.

  6. Counting radon tracks in Makrofol detectors with the 'image reduction and analysis facility' (IRAF) software package

    International Nuclear Information System (INIS)

    Makrofol detectors are commonly used for long-term radon (222Rn) measurements in houses, schools and workplaces. The use of this type of passive detectors for the determination of radon concentrations requires the counting of the nuclear tracks produced by alpha particles on the detecting material. The 'image reduction and analysis facility' (IRAF) software package is a piece of software commonly used in astronomical applications. It allows detailed counting and mapping of sky sections where stars are grouped very closely, even forming clusters. In order to count the nuclear tracks in our Makrofol radon detectors, we have developed an inter-disciplinary application that takes advantage of the similitude that exist between counting stars in a dark sky and tracks in a track-etch detector. Thus, a low cost semi-automatic system has been set up in our laboratory which utilises a commercially available desktop scanner and the IRAF software package. A detailed description of the proposed semi-automatic method and its performance, in comparison to ocular counting, is described in detail here. In addition, the calibration factor for this procedure, 2.97+/-0.07kBqm-3htrack-1cm2, has been calculated based on the results obtained from exposing 46 detectors to certified radon concentrations. Furthermore, the results of a preliminary radon survey carried out in 62 schools in Tenerife island (Spain), using Makrofol detectors, counted with the mentioned procedure, are briefly presented. The results reported here indicate that the developed procedure permits a fast, accurate and unbiased determination of the radon tracks in a large number of detectors. The measurements carried out in the schools showed that the radon concentrations in at least 12 schools were above 200Bqm-3 and, in two of them, above 400Bqm-3. Further studies should be performed at those schools following the European Union recommendations about radon concentrations in buildings

  7. Analysis of flow fields, temperatures and ruthenium transport in the test facility

    International Nuclear Information System (INIS)

    Ruthenium transport experiments were conducted at VTT during years 2002- 2006. Experiments gave information about ruthenium behaviour in air ingress accident conditions. This study complements those experiments with an analysis of the flows and thermal fields in the test system. Temperature profiles were measured at the walls of the experimental facility. Computational fluid dynamics (CFD) simulations used the measured profiles and provided predictions of flows and temperatures inside the furnace. Ruthenium transport was also modelled with CFD. Thermal characterisation of the reactor demonstrated that buoyancy has a significant role during the cooling after the furnace. A hypothesis of the dominant role of RuO2 and RuO3 condensation on reactor walls gave simulation results that are in accordance with radiotracer measurements of deposition in experiments conducted with furnace at 1500K. Actually, RuO3 does not condensate, but it thermal decomposes to RuO2. This does not seem to have effect on result. Particle formation around the furnace exit could be detected from the comparison of modelling results with the measured profiles. In several other experiments ruthenium behaviour is dominated by other issues. These are related to the complex ruthenium chemistry that includes various surface reactions. Thermal equilibrium indicates significant gaseous RuO4 concentration around 1300 K. It seems that seed particles decreased the catalytic decomposition activity of RuO4 to RuO2 around this temperature pushing the gas concentration towards the equilibrium, and further give rise to gaseous RuO4 transport to low temperatures. At higher temperature increasing mass flow rate of RuO2 particles is likely to catalyse (decomposition) reaction of RuO4 to RuO2. (au)

  8. AMS analysis of 36Cl induced in concrete of accelerator facilities

    International Nuclear Information System (INIS)

    Accelerator mass spectrometry (AMS) was applied to the analysis of 36Cl induced in concrete samples obtained from accelerator facilities. In order to use a small amount of concrete sample and to separate chlorine as pure as possible, an improvement of separation process was developed. Chlorine was extracted from 1-5 g of concrete into 0.01 M nitric acid in a pressurized decomposition vessel. After determining chlorine using ion chromatography, a certain amount of NaCl solution was added to obtain sufficient amounts of AgCl precipitate and to dilute to a suitable isotope ratio of 36Cl to 35Cl (36Cl/35Cl) for the AMS (10-12-10-10). A careful purification procedure was applied to reduce 36S interference in AMS. Good reproducibility and small error throughout the chemical process for sample preparation was attained. Depth profiles of 36Cl/35Cl in concrete of a medium-energy cyclotron were measured by the developed method and compared with the results of γ-emitters induced by thermal neutrons. Since it was confirmed that 36Cl was produced by thermal neutron capture of 35Cl, the thermal neutron fluence irradiated during accelerator operation could be obtained using 36Cl/35Cl. In order to estimate the neutron fluences, the 36Cl/35Cl measurement by AMS is more useful than radioactivity measurements of other isotopes such as γ-emitters because AMS directly provides the isotope ratio and the half-life of 36Cl is very long. (orig.)

  9. Preliminary Analysis of the Transient Reactor Test Facility (TREAT) with PROTEUS

    International Nuclear Information System (INIS)

    The neutron transport code PROTEUS has been used to perform preliminary simulations of the Transient Reactor Test Facility (TREAT). TREAT is an experimental reactor designed for the testing of nuclear fuels and other materials under transient conditions. It operated from 1959 to 1994, when it was placed on non-operational standby. The restart of TREAT to support the U.S. Department of Energy's resumption of transient testing is currently underway. Both single assembly and assembly-homogenized full core models have been evaluated. Simulations were performed using a historic set of WIMS-ANL-generated cross-sections as well as a new set of Serpent-generated cross-sections. To support this work, further analyses were also performed using additional codes in order to investigate particular aspects of TREAT modeling. DIF3D and the Monte-Carlo codes MCNP and Serpent were utilized in these studies. MCNP and Serpent were used to evaluate the effect of geometry homogenization on the simulation results and to support code-to-code comparisons. New meshes for the PROTEUS simulations were created using the CUBIT toolkit, with additional meshes generated via conversion of selected DIF3D models to support code-to-code verifications. All current analyses have focused on code-to-code verifications, with additional verification and validation studies planned. The analysis of TREAT with PROTEUS-SN is an ongoing project. This report documents the studies that have been performed thus far, and highlights key challenges to address in future work.

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

    International Nuclear Information System (INIS)

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

  11. 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...

  12. IBA applied to adsorption and coadsorption studies of H2 and C6H6 on Ni(111)

    International Nuclear Information System (INIS)

    15N-induced nuclear reactions on H and D have been used to study hydrogen and benzene adsorption on Ni(111) in a UHV system connected to a Van de Graaff accelerator and equipped with surface cleaning facilities. Analysis can be performed in vacuum or in a gas atmosphere which is of particular interest for molecules with a low sticking probability like H2. The coverage of hydrogen on the Ni surface has been measured in the 10-8-10-2 mbar pressure range taking into account the contribution of the nuclear reactions induced on hydrogen atoms in the gas phase for pressures higher than 10-5 mbar. When the analysis is performed after gas evacuation (H2 or C6H6) an ion-induced desorption effect can be observed and a low irradiation fluence is required (integrated charge of 1 μC) setting a detection limit of 7.5x1013 at/cm2. Working with or without gas pressure points out for C6H6 a second phase reversibly adsorbed on the surface. In the coadsorption study with labelled molecules (C6D6-H2 or C6H6-D2) the nonresonant nuclear reactions on deuterium allow to analyse deuterium without interference from hydrogen and a detection limit of 2.2x1014 at/cm2 is obtained at a 8 MeV incident energy. The variation of the D concentration on the surface precovered with benzene as a function of hydrogen exposure, points out an exchange reaction between adsorbed molecules. (orig.)

  13. 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.

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

    International Nuclear Information System (INIS)

    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

  15. Description and Analysis of Educational Facilities Design Criteria Based on Creative thinking from the Perspective of Educational Technology Specialists

    OpenAIRE

    2013-01-01

    The aim of this study is description and analysis of educational facilities design criteria based on creative thinking from the perspective of educational technology specialists. Study\\'s method is descriptive-surveyand it is polling type. Method description - is a survey of surveys. Population consists of full-time faculty members in the field of educational technology at the University of Tehran that are 36 persons. Tools for data collection are questionnaire responses depending on the rese...

  16. A Spatial Hedonic Analysis of the Effects of Wind Energy Facilities on Surrounding Property Values in the United States

    Energy Technology Data Exchange (ETDEWEB)

    Hoen, Ben [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States); Wiser, Ryan [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States); Cappers, Peter [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States); Brown, Jason P. [Federal Reserve Bank of Kansas City, MO (United States); Jackson, Thomas [Real Analytics Inc. and Texas A & M Univ., College Station, TX (United States); Thayer, Mark A. [San Diego State Univ., CA (United States)

    2013-08-21

    This report summarizes a new analysis, building on previously published research, about wind energy’s effects on residential property values. This study helps fill research gaps by collecting and analyzing data from 27 counties across nine U.S. states, related to 67 different wind facilities, and constructs a pooled model that investigates average effects near the turbines across the sample while controlling for local variables, such as sale prices of nearby homes.

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

    Energy Technology Data Exchange (ETDEWEB)

    Lisa Harvego; Mike Lehto

    2010-05-01

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

  18. Source term modeling and analysis for vault/trench facilities located in an unsaturated zone

    International Nuclear Information System (INIS)

    This report outlines an analytical work on the third test case, Test Case 2b, specified by the IAEA sponsored co-ordinated research programme on the safety assessment of near-surface radioactive waste disposal facilities (NSARS). Test Case 2b focuses on a source term modeling of a disposal facility in an unsaturated soil layer. This report includes an analytical method used, groundwater flow analyses, a screening approach used, and transport calculations carried out, for two types of facilities: (1) a concrete vault with grout backfill around the waste, and (2) an open trench with soil backfill around the waste. Optional infiltration barrier test cases for two types of facilities are also analyzed. The results of the Test Case 2b are presented in this report, and show that the effectiveness of the concrete vault to reduce the infiltration rate to the facilities. Furthermore, in order to examine the suitability of an assumption that a soil layer is saturated, which is often used in safety analyses to avoid a complexity of analyzing an unsaturated-saturated groundwater flow, various conceptual models are applied for the evaluation of the source term. The results show that the assumption of the saturated condition does not always give enough conservative results and then it is important to simulate the unsaturated flow velocity. (author)

  19. Post-accident air leakage analysis in a nuclear facility via T-method airflow simulation

    International Nuclear Information System (INIS)

    This paper explains application of the T-method for calculating air leakages and pressure differentials in a nuclear facility following a Design Basis Accident (DBA). The nuclear facility ventilation systems are designed to maintain confinement of airborne radioactive material during normal operation and after a DBA. The confinement is achieved by maintaining the negative pressure below the outside atmospheric pressure. The ventilation exhaust capacity, required to maintain negative pressures in the facility during normal operation, is estimated using building components leakage data. However, following a DBA, the ventilation system equipment, ductwork, shielding windows, doors, etc. may be damaged and create new leakage paths. The system designer needs to know the exhaust airflow capacity required to maintain radioactive material confinement in the facility following a DBA. The T-method is a new computational tool for hydraulic networks optimization and simulation. Simple numerical computation in conjunction with airflows, pressures, and fan characteristics simulation for a complicated tree-network makes this method an efficient tool for studying air leakage flows and pressure in a facility following a DBA

  20. 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.