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Sample records for mcnp visual editor

  1. Modification to the Monte Carlo N-Particle (MCNP) Visual Editor (MCNPVised) to Read in Computer Aided Design (CAD) Files

    SciTech Connect

    Randolph Schwarz; Leland L. Carter; Alysia Schwarz

    2005-08-23

    Monte Carlo N-Particle Transport Code (MCNP) is the code of choice for doing complex neutron/photon/electron transport calculations for the nuclear industry and research institutions. The Visual Editor for Monte Carlo N-Particle is internationally recognized as the best code for visually creating and graphically displaying input files for MCNP. The work performed in this grant was used to enhance the capabilities of the MCNP Visual Editor to allow it to read in both 2D and 3D Computer Aided Design (CAD) files, allowing the user to electronically generate a valid MCNP input geometry.

  2. DeviceEditor visual biological CAD canvas

    PubMed Central

    2012-01-01

    Background Biological Computer Aided Design (bioCAD) assists the de novo design and selection of existing genetic components to achieve a desired biological activity, as part of an integrated design-build-test cycle. To meet the emerging needs of Synthetic Biology, bioCAD tools must address the increasing prevalence of combinatorial library design, design rule specification, and scar-less multi-part DNA assembly. Results We report the development and deployment of web-based bioCAD software, DeviceEditor, which provides a graphical design environment that mimics the intuitive visual whiteboard design process practiced in biological laboratories. The key innovations of DeviceEditor include visual combinatorial library design, direct integration with scar-less multi-part DNA assembly design automation, and a graphical user interface for the creation and modification of design specification rules. We demonstrate how biological designs are rendered on the DeviceEditor canvas, and we present effective visualizations of genetic component ordering and combinatorial variations within complex designs. Conclusions DeviceEditor liberates researchers from DNA base-pair manipulation, and enables users to create successful prototypes using standardized, functional, and visual abstractions. Open and documented software interfaces support further integration of DeviceEditor with other bioCAD tools and software platforms. DeviceEditor saves researcher time and institutional resources through correct-by-construction design, the automation of tedious tasks, design reuse, and the minimization of DNA assembly costs. PMID:22373390

  3. A Visual Editor in Java for View

    NASA Technical Reports Server (NTRS)

    Stansifer, Ryan

    2000-01-01

    In this project we continued the development of a visual editor in the Java programming language to create screens on which to display real-time data. The data comes from the numerous systems monitoring the operation of the space shuttle while on the ground and in space, and from the many tests of subsystems. The data can be displayed on any computer platform running a Java-enabled World Wide Web (WWW) browser and connected to the Internet. Previously a special-purpose program bad been written to display data on emulations of character-based display screens used for many years at NASA. The goal now is to display bit-mapped screens created by a visual editor. We report here on the visual editor that creates the display screens. This project continues the work we bad done previously. Previously we had followed the design of the 'beanbox,' a prototype visual editor created by Sun Microsystems. We abandoned this approach and implemented a prototype using a more direct approach. In addition, our prototype is based on newly released Java 2 graphical user interface (GUI) libraries. The result has been a visually more appealing appearance and a more robust application.

  4. A Visually Oriented Text Editor

    NASA Technical Reports Server (NTRS)

    Gomez, J. E.

    1985-01-01

    HERMAN employs Evans & Sutherland Picture System 2 to provide screenoriented editing capability for DEC PDP-11 series computer. Text altered by visual indication of characters changed. Group of HERMAN commands provides for higher level operations. HERMAN provides special features for editing FORTRAN source programs.

  5. Visualization and analyses of MCNP criticality calculation results

    SciTech Connect

    Urbatsch, T.J.; Forster, R.A.; Booth, T.E.; Van Riper, K.A.; Waters, L.S.

    1995-07-01

    Careful assessment of the results of a calculation by the code itself can detect mistakes in the problem setup and execution. MCNP has over four hundred error messages that inform the user of FATAL or WARNING errors that have been discovered during processing of just the input file. MCNP4A performs a self assessment of the calculated results to aid the user in determining the quality of the Monte Carlo results. MCNP4A contains new built-in sensitivity analyses of the Monte Carlo calculation that provide the user with simple WARNING messages for both criticality and fixed source calculations. The goal of the new analyses described in this paper is to provide the MCNP criticality practitioner with enough information in the output to assess the validity of the k{sub eff} calculation and any associated tallies. The results of these checks are presented in the k{sub eff} results summary, several k{sub eff} tables and graphs, and tally tables and graphs. Plots of k{sub eff} at the workstation are also available as the problem is running or in a postprocessing mode to assess problem performance and results. Plots of the fission source by cycle supply valuable visual information, although they are not yet available in the production version of MCNP.

  6. Visualizing MCNP Tally Segment Geometry and Coupling Results with ABAQUS

    SciTech Connect

    J. R. Parry; J. A. Galbraith

    2007-11-01

    The Advanced Graphite Creep test, AGC-1, is planned for irradiation in the Advanced Test Reactor (ATR) in support of the Next Generation Nuclear Plant program. The experiment requires very detailed neutronics and thermal hydraulics analyses to show compliance with programmatic and ATR safety requirements. The MCNP model used for the neutronics analysis required hundreds of tally regions to provide the desired detail. A method for visualizing the hundreds of tally region geometries and the tally region results in 3 dimensions has been created to support the AGC-1 irradiation. Additionally, a method was created which would allow ABAQUS to access the results directly for the thermal analysis of the AGC-1 experiment.

  7. Guest Editors' Introduction--Visual Analytics

    SciTech Connect

    Wong, Pak C.; Thomas, Jim

    2004-09-01

    The information revolution is upon us, and it is guaran-teed to change our lives and the way we conduct our daily business. The fact that we have to deal with not just the size but also the variety and complexity of this in-formation makes it a real challenge to survive the revolu-tion. Enter Visual Analytics, a contemporary and proven approach to combine the art of human intuition and the science of mathematical deduction to directly perceive patterns and derive knowledge and insight from them.

  8. Conversion of Input Data between KENO V.a and MCNP File Formats, Version 5L.

    Energy Science and Technology Software Center (ESTSC)

    2007-10-31

    Version 00 The KENO2MCNP program was written to convert KENO V.a input files to MCNP Format. This program currently only works with KENO Va geometries and will not work with geometries that contain more than a single array. A C++ graphical user interface was created that was linked to Fortran routines from KENO V.a that read the material library and Fortran routines from the MCNP Visual Editor that generate the MCNP input file. Either SCALEmore » 5.0 or SCALE 5.1 cross section files will work with this release. This version of KENO2MCNP was tested with CCC-730/MCNP5 1.40 and with CCC-725/SCALE5.0 and CCC-732/SCALE 5.1. Note that this distribution does not include either MCNP or SCALE, which are available separately through either RSICC or the NEA Data Bank.« less

  9. A 3D Immersive Fault Visualizer and Editor

    NASA Astrophysics Data System (ADS)

    Yikilmaz, M. B.; van Aalsburg, J.; Kreylos, O.; Kellogg, L. H.; Rundle, J. B.

    2007-12-01

    Digital fault models are an important resource for the study of earthquake dynamics, fault-earthquake interactions and seismicity. Once digitized these fault models can be used in Finite Element Model (FEM) programs or earthquake simulations such as Virtual California (VC). However, these models are often difficult to create, requiring a substantial amount of time to generate the fault topology and compute the properties of the individual segments. To aid in the construction of such models we have developed an immersive virtual reality (VR) application to visualize and edit fault models. Our program is designed to run in a CAVE (walk-in VR environment), but also works in a wide range of other environments, including desktop systems and GeoWalls. It is being developed at the UC Davis W.M. Keck Center for Active Visualization in the Earth Sciences (KeckCAVES, http://www.keckcaves.org). Immersive VR environments are ideal for visualizing and manipulating three- dimensional data sets. Our program allows users to create new models or modify existing ones; for example by repositioning individual fault-segments, by changing the dip angle, or by modifying (or assigning) the value of a property associated with a particular fault segment (i.e. slip rate). With the addition of high resolution Digital Elevation Models (DEM) the user can accurately add new segments to an existing model or create a fault model entirely from scratch. Interactively created or modified models can be written to XML files at any time; from there the data may easily be converted into various formats required by the analysis software or simulation. We believe that the ease of interaction provided by VR technology is ideally suited to the problem of creating and editing digital fault models. Our software provides the user with an intuitive environment for visualizing and editing fault model data. This translates not only into less time spent creating fault models, but also enables the researcher to

  10. TOAD Editor

    NASA Technical Reports Server (NTRS)

    Bingle, Bradford D.; Shea, Anne L.; Hofler, Alicia S.

    1993-01-01

    Transferable Output ASCII Data (TOAD) computer program (LAR-13755), implements format designed to facilitate transfer of data across communication networks and dissimilar host computer systems. Any data file conforming to TOAD format standard called TOAD file. TOAD Editor is interactive software tool for manipulating contents of TOAD files. Commonly used to extract filtered subsets of data for visualization of results of computation. Also offers such user-oriented features as on-line help, clear English error messages, startup file, macroinstructions defined by user, command history, user variables, UNDO features, and full complement of mathematical statistical, and conversion functions. Companion program, TOAD Gateway (LAR-14484), converts data files from variety of other file formats to that of TOAD. TOAD Editor written in FORTRAN 77.

  11. Programming the Navier-Stokes computer: An abstract machine model and a visual editor

    NASA Technical Reports Server (NTRS)

    Middleton, David; Crockett, Tom; Tomboulian, Sherry

    1988-01-01

    The Navier-Stokes computer is a parallel computer designed to solve Computational Fluid Dynamics problems. Each processor contains several floating point units which can be configured under program control to implement a vector pipeline with several inputs and outputs. Since the development of an effective compiler for this computer appears to be very difficult, machine level programming seems necessary and support tools for this process have been studied. These support tools are organized into a graphical program editor. A programming process is described by which appropriate computations may be efficiently implemented on the Navier-Stokes computer. The graphical editor would support this programming process, verifying various programmer choices for correctness and deducing values such as pipeline delays and network configurations. Step by step details are provided and demonstrated with two example programs.

  12. SUPERIMPOSED MESH PLOTTING IN MCNP

    SciTech Connect

    J. HENDRICKS

    2001-02-01

    The capability to plot superimposed meshes has been added to MCNP{trademark}. MCNP4C featured a superimposed mesh weight window generator which enabled users to set up geometries without having to subdivide geometric cells for variance reduction. The variance reduction was performed with weight windows on a rectangular or cylindrical mesh superimposed over the physical geometry. Experience with the new capability was favorable but also indicated that a number of enhancements would be very beneficial, particularly a means of visualizing the mesh and its values. The mathematics for plotting the mesh and its values is described here along with a description of other upgrades.

  13. SIERRA Editor v. 1.2.1

    Energy Science and Technology Software Center (ESTSC)

    2010-03-24

    The SIERRA Editor is a syntax editor for text-based input decks for the SIERRA modeling and simulations codes. The SIERRA Editor provides color coded syntax, error checking, hyperlink navigation to referenced entities (e.g. functions and materials), and visual verification of mesh entity references (blocks, sidesets, and nodesets). The SIERRA Editor helps modeling and simulation analysts who use the SIERRA codes to produce syntactically correct input decks.

  14. New Editor

    NASA Astrophysics Data System (ADS)

    2007-03-01

    It is an honour and a challenge to take up the editorship of the Messenger at this time of ESO's expanding role in European and worldwide astronomy. In order to mark the change, we have made a few adjustments to the appearance without departing from the overall style that Peter Shaver had evolved during his term as editor. I would like to thank Peter for gen-tly coaching me into the position and Jutta Boxheimer, the technical editor, for the high quality of the layout.

  15. Features of MCNP6

    NASA Astrophysics Data System (ADS)

    Goorley, T.; James, M.; Booth, T.; Brown, F.; Bull, J.; Cox, L. J.; Durkee, J.; Elson, J.; Fensin, M.; Forster, R. A.; Hendricks, J.; Hughes, H. G.; Johns, R.; Kiedrowski, B.; Martz, R.; Mashnik, S.; McKinney, G.; Pelowitz, D.; Prael, R.; Sweezy, J.; Waters, L.; Wilcox, T.; Zukaitis, T.

    2014-06-01

    MCNP6 is simply and accurately described as the merger of MCNP5 and MCNPX capabilities, but it is much more than the sum of these two computer codes. MCNP6 is the result of six years of effort by the MCNP5 and MCNPX code development teams. These groups of people, residing in Los Alamos National Laboratory's X Computational Physics Division, Monte Carlo Codes Group (XCP-3) and Nuclear Engineering and Nonproliferation Division, Radiation Transport Modeling Team (NEN-5) respectively, have combined their code development efforts to produce the next evolution of MCNP. While maintenance and major bug fixes will continue for MCNP5 1.60 and MCNPX 2.7.0 for upcoming years, new code development capabilities only will be developed and released in MCNP6. In fact, the initial release of MCNP6 contains numerous new features not previously found in either code. These new features are summarized in this document. Packaged with MCNP6 is also the new production release of the ENDF/B-VII.1 nuclear data files usable by MCNP. The high quality of the overall merged code, usefulness of these new features, along with the desire in the user community to start using the merged code, have led us to make the first MCNP6 production release: MCNP6 version 1. High confidence in the MCNP6 code is based on its performance with the verification and validation test suites, comparisons to its predecessor codes, our automated nightly software debugger tests, the underlying high quality nuclear and atomic databases, and significant testing by many beta testers.

  16. MPS Editor

    NASA Technical Reports Server (NTRS)

    Mathews, William S.; Liu, Ning; Francis, Laurie K.; OReilly, Taifun L.; Schrock, Mitchell; Page, Dennis N.; Morris, John R.; Joswig, Joseph C.; Crockett, Thomas M.; Shams, Khawaja S.

    2011-01-01

    Previously, it was time-consuming to hand-edit data and then set up simulation runs to find the effect and impact of the input data on a spacecraft. MPS Editor provides the user the capability to create/edit/update models and sequences, and immediately try them out using what appears to the user as one piece of software. MPS Editor provides an integrated sequencing environment for users. It provides them with software that can be utilized during development as well as actual operations. In addition, it provides them with a single, consistent, user friendly interface. MPS Editor uses the Eclipse Rich Client Platform to provide an environment that can be tailored to specific missions. It provides the capability to create and edit, and includes an Activity Dictionary to build the simulation spacecraft models, build and edit sequences of commands, and model the effects of those commands on the spacecraft. MPS Editor is written in Java using the Eclipse Rich Client Platform. It is currently built with four perspectives: the Activity Dictionary Perspective, the Project Adaptation Perspective, the Sequence Building Perspective, and the Sequence Modeling Perspective. Each perspective performs a given task. If a mission doesn't require that task, the unneeded perspective is not added to that project's delivery. In the Activity Dictionary Perspective, the user builds the project-specific activities, observations, calibrations, etc. Typically, this is used during the development phases of the mission, although it can be used later to make changes and updates to the Project Activity Dictionary. In the Adaptation Perspective, the user creates the spacecraft models such as power, data store, etc. Again, this is typically used during development, but will be used to update or add models of the spacecraft. The Sequence Building Perspective allows the user to create a sequence of activities or commands that go to the spacecraft. It provides a simulation of the activities and

  17. MCNP Progress & Performance Improvements

    SciTech Connect

    Brown, Forrest B.; Bull, Jeffrey S.; Rising, Michael Evan

    2015-04-14

    Twenty-eight slides give information about the work of the US DOE/NNSA Nuclear Criticality Safety Program on MCNP6 under the following headings: MCNP6.1.1 Release, with ENDF/B-VII.1; Verification/Validation; User Support & Training; Performance Improvements; and Work in Progress. Whisper methodology will be incorporated into the code, and run speed should be increased.

  18. MCNP: Photon benchmark problems

    SciTech Connect

    Whalen, D.J.; Hollowell, D.E.; Hendricks, J.S.

    1991-09-01

    The recent widespread, markedly increased use of radiation transport codes has produced greater user and institutional demand for assurance that such codes give correct results. Responding to these pressing requirements for code validation, the general purpose Monte Carlo transport code MCNP has been tested on six different photon problem families. MCNP was used to simulate these six sets numerically. Results for each were compared to the set's analytical or experimental data. MCNP successfully predicted the analytical or experimental results of all six families within the statistical uncertainty inherent in the Monte Carlo method. From this we conclude that MCNP can accurately model a broad spectrum of photon transport problems. 8 refs., 30 figs., 5 tabs.

  19. Geometry creation for MCNP by Sabrina and XSM

    SciTech Connect

    Van Riper, K.A.

    1994-02-01

    The Monte Carlo N-Particle transport code MCNP is based on a surface description of 3-dimensional geometry. Cells are defined in terms of boolean operations on signed quadratic surfaces. MCNP geometry is entered as a card image file containing coefficients of the surface equations and a list of surfaces and operators describing cells. Several programs are available to assist in creation of the geometry specification, among them Sabrina and the new ``Smart Editor`` code XSM. We briefly describe geometry creation in Sabrina and then discuss XSM in detail. XSM is under development; our discussion is based on the state of XSM as of January 1, 1994.

  20. Journal Editors Celebrated at Editors' Evening

    NASA Astrophysics Data System (ADS)

    Panning, Jeanette

    2014-02-01

    At the Fall Meeting, the premiere social event for AGU's many journal editors is the annual Editors' Evening, an opportunity for members to celebrate and to recognize the efforts of retiring editors. At the event, AGU president Carol Finn welcomed all those in attendance and thanked them for volunteering their time for the benefit of AGU and the wider research community.

  1. Recent MCNP developments

    SciTech Connect

    Hendricks, J.S.; Briesmeister, J.F.

    1991-01-01

    MCNP is a widely used and actively developed Monte Carlo radiation transport code. Many important features have recently been added and more are under development. Benchmark studies not only indicate that MCNP is accurate but also that modern computer codes can give answers basically as accurate as the physics data that goes in them. Even deep penetration problems can be correct to within a factor of two after 10 to 25 mean free paths of penetration. And finally, Monte Carlo calculations, once thought to be too expensive to run routinely, can now be run effectively on desktop computers which compete with the supercomputers of yesteryear. 21 refs., 3 tabs.

  2. MCNP6 Status

    SciTech Connect

    Goorley, John T.

    2012-06-25

    We, the development teams for MCNP, NJOY, and parts of ENDF, would like to invite you to a proposed 3 day workshop October 30, 31 and November 1 2012, to be held at Los Alamos National Laboratory. At this workshop, we will review new and developing missions that MCNP6 and the underlying nuclear data are being asked to address. LANL will also present its internal plans to address these missions and recent advances in these three capabilities and we will be interested to hear your input on these topics. Additionally we are interested in hearing from you additional technical advances, missions, concerns, and other issues that we should be considering for both short term (1-3 years) and long term (4-6 years)? What are the additional existing capabilities and methods that we should be investigating? The goal of the workshop is to refine priorities for mcnp6 transport methods, algorithms, physics, data and processing as they relate to the intersection of MCNP, NJOY and ENDF.

  3. Present and future capabilities of MCNP

    PubMed

    Hendricks; Adam; Booth; Briesmeister; Carter; Cox; Favorite; Forster; McKinney; Prael

    2000-10-01

    Several new capabilities have been added to MCNP4C including: (1) macrobody surfaces; (2) the superimposed mesh importance functions, so that it is no longer necessary to subdivide geometries for variance reduction; and (3) Xlib graphics and DVF Fortran 90 for PCs. There are also improvements in neutron physics, electron physics, perturbations, and parallelization. In the more distant future we are working on adaptive Monte Carlo code modernization, more parallelization, visualization, and charged particles. PMID:11003531

  4. DNA Align Editor: DNA Alignment Editor Tool

    Technology Transfer Automated Retrieval System (TEKTRAN)

    The SNPAlignEditor is a DNA sequence alignment editor that runs on Windows platforms. The purpose of the program is to provide an intuitive, user-friendly tool for manual editing of multiple sequence alignments by providing functions for input, editing, and output of nucleotide sequence alignments....

  5. Validation suite for MCNP

    SciTech Connect

    Mosteller, R. D.

    2002-01-01

    Two validation suites, one for criticality and another for radiation shielding, have been defined and tested for the MCNP Monte Carlo code. All of the cases in the validation suites are based on experiments so that calculated and measured results can be compared in a meaningful way. The cases in the validation suites are described, and results from those cases are discussed. For several years, the distribution package for the MCNP Monte Carlo code1 has included an installation test suite to verify that MCNP has been installed correctly. However, the cases in that suite have been constructed primarily to test options within the code and to execute quickly. Consequently, they do not produce well-converged answers, and many of them are physically unrealistic. To remedy these deficiencies, sets of validation suites are being defined and tested for specific types of applications. All of the cases in the validation suites are based on benchmark experiments. Consequently, the results from the measurements are reliable and quantifiable, and calculated results can be compared with them in a meaningful way. Currently, validation suites exist for criticality and radiation-shielding applications.

  6. MCNP: Multigroup/adjoint capabilities

    SciTech Connect

    Wagner, J.C.; Redmond, E.L. II; Palmtag, S.P.; Hendricks, J.S.

    1994-04-01

    This report discusses various aspects related to the use and validity of the general purpose Monte Carlo code MCNP for multigroup/adjoint calculations. The increased desire to perform comparisons between Monte Carlo and deterministic codes, along with the ever-present desire to increase the efficiency of large MCNP calculations has produced a greater user demand for the multigroup/adjoint capabilities. To more fully utilize these capabilities, we review the applications of the Monte Carlo multigroup/adjoint method, describe how to generate multigroup cross sections for MCNP with the auxiliary CRSRD code, describe how to use the multigroup/adjoint capability in MCNP, and provide examples and results indicating the effectiveness and validity of the MCNP multigroup/adjoint treatment. This information should assist users in taking advantage of the MCNP multigroup/adjoint capabilities.

  7. The REBUS-MCNP linkage.

    SciTech Connect

    Stevens, J. G.; Nuclear Engineering Division

    2009-04-24

    The Reduced Enrichment Research and Test Reactor (RERTR) Program uses the REBUS-PC computer code to provide reactor physics and core design information such as neutron flux distributions in space, energy, and time, and to track isotopic changes in fuel and neutron absorbers with burnup. REBUS-PC models the complete fuel cycle including shuffling capability. REBUS-PC evolved using the neutronic capabilities of multi-group diffusion theory code DIF3D 9.0, but was extended to apply the continuous energy Monte Carlo code MCNP for one-group fluxes and cross-sections. The linkage between REBUS-PC and MCNP has recently been modernized and extended, as described in this manual. REBUS-PC now calls MCNP via a system call so that the user can apply any valid MCNP executable. The interface between REBUS-PC and MCNP requires minimal changes to an existing MCNP model, and little additional input. The REBUS-MCNP interface can also be used in conjunction with DIF3D neutronics to update an MCNP model with fuel compositions predicted using a DIF3D based depletion.

  8. MCNP LWR Core Generator

    SciTech Connect

    Fischer, Noah A.

    2012-08-14

    The reactor core input generator allows for MCNP input files to be tailored to design specifications and generated in seconds. Full reactor models can now easily be created by specifying a small set of parameters and generating an MCNP input for a full reactor core. Axial zoning of the core will allow for density variation in the fuel and moderator, with pin-by-pin fidelity, so that BWR cores can more accurately be modeled. LWR core work in progress: (1) Reflectivity option for specifying 1/4, 1/2, or full core simulation; (2) Axial zoning for moderator densities that vary with height; (3) Generating multiple types of assemblies for different fuel enrichments; and (4) Parameters for specifying BWR box walls. Fuel pin work in progress: (1) Radial and azimuthal zoning for generating further unique materials in fuel rods; (2) Options for specifying different types of fuel for MOX or multiple burn assemblies; (3) Additional options for replacing fuel rods with burnable poison rods; and (4) Control rod/blade modeling.

  9. DNAAlignEditor: DNA alignment editor tool

    PubMed Central

    Sanchez-Villeda, Hector; Schroeder, Steven; Flint-Garcia, Sherry; Guill, Katherine E; Yamasaki, Masanori; McMullen, Michael D

    2008-01-01

    Background With advances in DNA re-sequencing methods and Next-Generation parallel sequencing approaches, there has been a large increase in genomic efforts to define and analyze the sequence variability present among individuals within a species. For very polymorphic species such as maize, this has lead to a need for intuitive, user-friendly software that aids the biologist, often with naïve programming capability, in tracking, editing, displaying, and exporting multiple individual sequence alignments. To fill this need we have developed a novel DNA alignment editor. Results We have generated a nucleotide sequence alignment editor (DNAAlignEditor) that provides an intuitive, user-friendly interface for manual editing of multiple sequence alignments with functions for input, editing, and output of sequence alignments. The color-coding of nucleotide identity and the display of associated quality score aids in the manual alignment editing process. DNAAlignEditor works as a client/server tool having two main components: a relational database that collects the processed alignments and a user interface connected to database through universal data access connectivity drivers. DNAAlignEditor can be used either as a stand-alone application or as a network application with multiple users concurrently connected. Conclusion We anticipate that this software will be of general interest to biologists and population genetics in editing DNA sequence alignments and analyzing natural sequence variation regardless of species, and will be particularly useful for manual alignment editing of sequences in species with high levels of polymorphism. PMID:18366684

  10. New Journal Editors Appointed

    NASA Astrophysics Data System (ADS)

    Major, Barbara

    2009-11-01

    New editors have been appointed for Geophysical Research Letters (GRL), Journal of Geophysical Research (JGR)-Solid Earth, Reviews of Geophysics, JGR-Space Physics, Paleoceanography, and Tectonics. At GRL, new editors Noah Diffenbaugh (Stanford University, Stanford, Calif.), Paolo D’Odorico (University of Virginia, Charlottesville), Ruth Harris (U.S. Geological Survey (USGS), Menlo Park, Calif.), Wolfgang Knorr (University of Bristol, Bristol, UK), Geoffrey Tyndall (National Center for Atmospheric Research, Boulder, Colo.), and Michael Wysession (Washington University, St. Louis, Mo.) have joined Editor-in-Chief Eric Calais and other editors Margaret Chen, Fabio Florindo, Anne Müller, Nikolai Ostgaard, Eric Rignot, and Meric Srokosz.

  11. Boerhaave: Author and Editor *

    PubMed Central

    Lindeboom, G. A.

    1974-01-01

    The many facets of Herman Boerhaave's life are presented. He was a renowned teacher, physician, author, and editor. Discussed here are his activities as cataloger of the Vossius Collection, author of books on chemistry, botany, and medicine, and as editor of works by Vesalius and early Greek medical writers. Printing and bookselling in Leiden during Boerhaave's era are described. Images PMID:4596962

  12. MCNP-DSP users manual

    SciTech Connect

    Valentine, T.E.

    1997-01-01

    The Monte Carlo code MCNP-DSP was developed from the Los Alamos MCNP4a code to calculate the time and frequency response statistics obtained from the {sup 252}Cf-source-driven frequency analysis measurements. This code can be used to validate calculational methods and cross section data sets from subcritical experiments. This code provides a more general model for interpretation and planning of experiments for nuclear criticality safety, nuclear safeguards, and nuclear weapons identification and replaces the use of point kinetics models for interpreting the measurements. The use of MCNP-DSP extends the usefulness of this measurement method to systems with much lower neutron multiplication factors.

  13. A new MCNP{trademark} test set

    SciTech Connect

    Brockhoff, R.C.; Hendricks, J.S.

    1994-09-01

    The MCNP test set is used to test the MCNP code after installation on various computer platforms. For MCNP4 and MCNP4A this test set included 25 test problems designed to test as many features of the MCNP code as possible. A new and better test set has been devised to increase coverage of the code from 85% to 97% with 28 problems. The new test set is as fast as and shorter than the MCNP4A test set. The authors describe the methodology for devising the new test set, the features that were not covered in the MCNP4A test set, and the changes in the MCNP4A test set that have been made for MCNP4B and its developmental versions. Finally, new bugs uncovered by the new test set and a compilation of all known MCNP4A bugs are presented.

  14. Potential MCNP enhancements for NCT

    SciTech Connect

    Estes, G.P.; Taylor, W.M.

    1992-01-01

    MCNP a Monte Carlo radiation transport code, is currently widely used in the medical community for a variety of purposes including treatment planning, diagnostics, beam design, tomographic studies, and radiation protection. This is particularly true in the Neutron Capture Therapy (NCT) community. The current widespread medical use of MCNP after its general public distribution in about 1980 attests to the code's general versatility and usefulness, particularly since its development to date has not been influenced by medical applications. This paper discusses enhancements to MCNP that could be implemented at Los Alamos for the benefit of the NCT community. These enhancements generally fall into two categories, namely those that have already been developed to some extent but are not yet publicly available, and those that seem both needed based on our current understanding of NCT goals, and achievable based on our working knowledge of the MCNP code. MCNP is a general, coupled neutron/photon/electron Monte Carlo code developed and maintained by the Radiation Transport Group at Los Alamos. It has been used extensively for radiation shielding studies, reactor analysis, detector design, physics experiment interpretation, oil and gas well logging, radiation protection studies, accelerator design, etc. over the years. MCNP is a three-dimensional geometry, continuous energy physics code capable of modeling complex geometries, specifying material regions such as organs by the intersections of analytical surfaces.

  15. Potential MCNP enhancements for NCT

    SciTech Connect

    Estes, G.P.; Taylor, W.M.

    1992-12-01

    MCNP a Monte Carlo radiation transport code, is currently widely used in the medical community for a variety of purposes including treatment planning, diagnostics, beam design, tomographic studies, and radiation protection. This is particularly true in the Neutron Capture Therapy (NCT) community. The current widespread medical use of MCNP after its general public distribution in about 1980 attests to the code`s general versatility and usefulness, particularly since its development to date has not been influenced by medical applications. This paper discusses enhancements to MCNP that could be implemented at Los Alamos for the benefit of the NCT community. These enhancements generally fall into two categories, namely those that have already been developed to some extent but are not yet publicly available, and those that seem both needed based on our current understanding of NCT goals, and achievable based on our working knowledge of the MCNP code. MCNP is a general, coupled neutron/photon/electron Monte Carlo code developed and maintained by the Radiation Transport Group at Los Alamos. It has been used extensively for radiation shielding studies, reactor analysis, detector design, physics experiment interpretation, oil and gas well logging, radiation protection studies, accelerator design, etc. over the years. MCNP is a three-dimensional geometry, continuous energy physics code capable of modeling complex geometries, specifying material regions such as organs by the intersections of analytical surfaces.

  16. Editors' Fall Picks

    ERIC Educational Resources Information Center

    Hoffert, Barbara; Heilbrun, Margaret; Kuzyk, Raya; Kim, Ann; McCormack, Heather; Katterjohn, Anna; Burns, Ann; Williams, Wilda

    2008-01-01

    From the fall's cascade of great new books, "Library Journal's" editors select their favorites--a dark rendition of Afghan life, a look at the "self-esteem trap," a celebration of Brooklyn activism, and much more.

  17. ISTP CDF Skeleton Editor

    NASA Technical Reports Server (NTRS)

    Chimiak, Reine; Harris, Bernard; Williams, Phillip

    2013-01-01

    Basic Common Data Format (CDF) tools (e.g., cdfedit) provide no specific support for creating International Solar-Terrestrial Physics/Space Physics Data Facility (ISTP/SPDF) standard files. While it is possible for someone who is familiar with the ISTP/SPDF metadata guidelines to create compliant files using just the basic tools, the process is error-prone and unreasonable for someone without ISTP/SPDF expertise. The key problem is the lack of a tool with specific support for creating files that comply with the ISTP/SPDF guidelines. There are basic CDF tools such as cdfedit and skeletoncdf for creating CDF files, but these have no specific support for creating ISTP/ SPDF compliant files. The SPDF ISTP CDF skeleton editor is a cross-platform, Java-based GUI editor program that allows someone with only a basic understanding of the ISTP/SPDF guidelines to easily create compliant files. The editor is a simple graphical user interface (GUI) application for creating and editing ISTP/SPDF guideline-compliant skeleton CDF files. The SPDF ISTP CDF skeleton editor consists of the following components: A swing-based Java GUI program, JavaHelp-based manual/ tutorial, Image/Icon files, and HTML Web page for distribution. The editor is available as a traditional Java desktop application as well as a Java Network Launching Protocol (JNLP) application. Once started, it functions like a typical Java GUI file editor application for creating/editing application-unique files.

  18. MCNP(TM) Version 5.

    SciTech Connect

    Cox, L. J.; Barrett, R. F.; Booth, Thomas Edward; Briesmeister, Judith F.; Brown, F. B.; Bull, J. S.; Giesler, G. C.; Goorley, J. T.; Mosteller, R. D.; Forster, R. A.; Post, S. E.; Prael, R. E.; Selcow, Elizabeth Carol,; Sood, A.

    2002-01-01

    The Monte Carlo transport workhorse, MCNP, is undergoing a massive renovation at Los Alamos National Laboratory (LANL) in support of the Eolus Project of the Advanced Simulation and Computing (ASCI) Program. MCNP Version 5 (V5) (expected to be released to RSICC in Spring, 2002) will consist of a major restructuring from FORTRAN-77 (with extensions) to ANSI-standard FORTRAN-90 with support for all of the features available in the present release (MCNP-4C2/4C3). To most users, the look-and-feel of MCNP will not change much except for the improvements (improved graphics, easier installation, better online documentation). For example, even with the major format change, full support for incremental patching will still be provided. In addition to the language and style updates, MCNP V5 will have various new user features. These include improved photon physics, neutral particle radiography, enhancements and additions to variance reduction methods, new source options, and improved parallelism support (PVM, MPI, OpenMP).

  19. MCNP-DSP USERS MANUAL

    SciTech Connect

    Valentine, T.E.

    2001-01-19

    The Monte Carlo code MCNP-DSP was developed from the Los Alamos MCNP4a code to calculate the time and frequency response statistics obtained from subcritical measurements. The code can be used to simulate a variety of subcritical measurements including source-driven noise analysis, Rossi-{alpha}, pulsed source, passive frequency analysis, multiplicity, and Feynman variance measurements. This code can be used to validate Monte Carlo methods and cross section data sets with subcritical measurements and replaces the use of point kinetics models for interpreting subcritical measurements.

  20. Verification of MCNP5-1.60 and MCNP6-Beta-2 for Criticality Safety Applications

    SciTech Connect

    Brown, Forrest B.; Kiedrowski, Brian C.; Bull, Jeffrey S.

    2012-05-01

    To verify that both MCNP5-1.60 and MCNP6-Beta-2 are performing correctly for criticality safety applications, several suites of verification/validation benchmark problems were run in early 2012. Results from these benchmark suites were compared with results from previously verified versions of MCNP5. The goals of this verification testing were: (1) Verify that MCNP5-1.60 works correctly for nuclear criticality safety applications, producing the same results as for the previous verification performed in 2010; (2) Determine the sensitivity to computer roundoff using different Fortran-90 compilers for building MCNP5 and MCNP6, to support moving to current versions of the compilers; and (3) Verify that MCNP6-Beta-2 works correctly for nuclear criticality safety applications, producing the same results as for MCNP5-1.60. This provides support for eventual migration of users and applications to MCNP6. The current production version of MCNP5 included in the RSICC release package is MCNP5-1.60. This version was first distributed by RSICC in October 2010. While there were subsequent RSICC distributions of the MCNP package in July 2011 and February 2012, no changes were made to MCNP5-1.60. The RSICC release package in February 2012 included both MCNP5-1.60 and the current beta version of MCNP6, MCNP6-Beta-2. MCNP6 is the merger of MCNP5 and MCNPX capabilities. The current release of MCNP6 available from RSICC as of February 2012 is MCNP6-Beta-2. This version includes all of the features for criticality safety calculations that are available in MCNP5-1.60, and many new features largely unrelated to nuclear criticality safety calculations. This release is a 'beta' release to allow intermediate and advanced users to begin testing the merged code in their field of expertise. It should not be used for production calculations.

  1. MCNP Output Data Analysis with ROOT (MODAR)

    NASA Astrophysics Data System (ADS)

    Carasco, C.

    2010-06-01

    MCNP Output Data Analysis with ROOT (MODAR) is a tool based on CERN's ROOT software. MODAR has been designed to handle time-energy data issued by MCNP simulations of neutron inspection devices using the associated particle technique. MODAR exploits ROOT's Graphical User Interface and functionalities to visualize and process MCNP simulation results in a fast and user-friendly way. MODAR allows to take into account the detection system time resolution (which is not possible with MCNP) as well as detectors energy response function and counting statistics in a straightforward way. Program summaryProgram title: MODAR Catalogue identifier: AEGA_v1_0 Program summary URL:http://cpc.cs.qub.ac.uk/summaries/AEGA_v1_0.html Program obtainable from: CPC Program Library, Queen's University, Belfast, N. Ireland Licensing provisions: Standard CPC licence, http://cpc.cs.qub.ac.uk/licence/licence.html No. of lines in distributed program, including test data, etc.: 155 373 No. of bytes in distributed program, including test data, etc.: 14 815 461 Distribution format: tar.gz Programming language: C++ Computer: Most Unix workstations and PC Operating system: Most Unix systems, Linux and windows, provided the ROOT package has been installed. Examples where tested under Suse Linux and Windows XP. RAM: Depends on the size of the MCNP output file. The example presented in the article, which involves three two-dimensional 139×740 bins histograms, allocates about 60 MB. These data are running under ROOT and include consumption by ROOT itself. Classification: 17.6 External routines: ROOT version 5.24.00 ( http://root.cern.ch/drupal/) Nature of problem: The output of an MCNP simulation is an ASCII file. The data processing is usually performed by copying and pasting the relevant parts of the ASCII file into Microsoft Excel. Such an approach is satisfactory when the quantity of data is small but is not efficient when the size of the simulated data is large, for example when time

  2. MCNP output data analysis with ROOT (MODAR)

    NASA Astrophysics Data System (ADS)

    Carasco, C.

    2010-12-01

    MCNP Output Data Analysis with ROOT (MODAR) is a tool based on CERN's ROOT software. MODAR has been designed to handle time-energy data issued by MCNP simulations of neutron inspection devices using the associated particle technique. MODAR exploits ROOT's Graphical User Interface and functionalities to visualize and process MCNP simulation results in a fast and user-friendly way. MODAR allows to take into account the detection system time resolution (which is not possible with MCNP) as well as detectors energy response function and counting statistics in a straightforward way. New version program summaryProgram title: MODAR Catalogue identifier: AEGA_v1_1 Program summary URL:http://cpc.cs.qub.ac.uk/summaries/AEGA_v1_1.html Program obtainable from: CPC Program Library, Queen's University, Belfast, N. Ireland Licensing provisions: Standard CPC licence, http://cpc.cs.qub.ac.uk/licence/licence.html No. of lines in distributed program, including test data, etc.: 150 927 No. of bytes in distributed program, including test data, etc.: 4 981 633 Distribution format: tar.gz Programming language: C++ Computer: Most Unix workstations and PCs Operating system: Most Unix systems, Linux and windows, provided the ROOT package has been installed. Examples where tested under Suse Linux and Windows XP. RAM: Depends on the size of the MCNP output file. The example presented in the article, which involves three two dimensional 139×740 bins histograms, allocates about 60 MB. These data are running under ROOT and include consumption by ROOT itself. Classification: 17.6 Catalogue identifier of previous version: AEGA_v1_0 Journal reference of previous version: Comput. Phys. Comm. 181 (2010) 1161 External routines: ROOT version 5.24.00 ( http://root.cern.ch/drupal/) Does the new version supersede the previous version?: Yes Nature of problem: The output of a MCNP simulation is an ascii file. The data processing is usually performed by copying and pasting the relevant parts of the ascii

  3. PANEL LIBRARY AND EDITOR

    NASA Technical Reports Server (NTRS)

    Raible, E.

    1994-01-01

    The Panel Library and Editor is a graphical user interface (GUI) builder for the Silicon Graphics IRIS workstation family. The toolkit creates "widgets" which can be manipulated by the user. Its appearance is similar to that of the X-Windows System. The Panel Library is written in C and is used by programmers writing user-friendly mouse-driven applications for the IRIS. GUIs built using the Panel Library consist of "actuators" and "panels." Actuators are buttons, dials, sliders, or other mouse-driven symbols. Panels are groups of actuators that occupy separate windows on the IRIS workstation. The application user can alter variables in the graphics program, or fire off functions with a click on a button. The evolution of data values can be tracked with meters and strip charts, and dialog boxes with text processing can be built. Panels can be stored as icons when not in use. The Panel Editor is a program used to interactively create and test panel library interfaces in a simple and efficient way. The Panel Editor itself uses a panel library interface, so all actions are mouse driven. Extensive context-sensitive on-line help is provided. Programmers can graphically create and test the user interface without writing a single line of code. Once an interface is judged satisfactory, the Panel Editor will dump it out as a file of C code that can be used in an application. The Panel Library (v9.8) and Editor (v1.1) are written in C-Language (63%) and Scheme, a dialect of LISP, (37%) for Silicon Graphics 4D series workstations running IRIX 3.2 or higher. Approximately 10Mb of disk space is required once compiled. 1.5Mb of main memory is required to execute the panel editor. This program is available on a .25 inch streaming magnetic tape cartridge in UNIX tar format for an IRIS, and includes a copy of XScheme, the public-domain Scheme interpreter used by the Panel Editor. The Panel Library Programmer's Manual is included on the distribution media. The Panel Library and

  4. LDAP Browser/Editor

    Energy Science and Technology Software Center (ESTSC)

    2000-07-18

    The LDAP Browser/Editor provides a user-friendly Java-based interface to LDAP databases with tightly integrated browsing and editing capabilities. Entirely written in Java with help of the JFC (Swingset) and JNDI class libraries. It connects to any X.500, LDAP v2 and v3 servers and supports editing of multiple-value attributes.

  5. Editors' Spring Picks

    ERIC Educational Resources Information Center

    Library Journal, 2011

    2011-01-01

    While they do not represent the rainbow of reading tastes American public libraries accommodate, Book Review editors are a wildly eclectic bunch. One look at their bedside tables and ereaders would reveal very little crossover. This article highlights an eclectic array of spring offerings ranging from print books to an audiobook to ebook apps. It…

  6. WRR editor Ronald Cummings

    NASA Astrophysics Data System (ADS)

    1984-04-01

    It has been nearly a year since Ronald Cummings took over as policy sciences editor of Water Resources Research (WRR), and in that time he has worked to make the journal live up to its role as “an interdisciplinary journal integrating research in the social and natural sciences of water.” Cummings takes the “interdisciplinary” part seriously. “I'd like to see a much broader range of policy issues presented to readers,” he says. “I would hope it would then stimulate interchange between our colleagues concerning evolving issues of the '80s and '90s.”Cummings brings a solid background as a resource economist to his 4-year term as editor, which began last January and runs until December 1987. Cummings succeeds Jared Cohon as policy sciences editor. Stephen J. Burges is the WRR editor for hydrological, physical, chemical, and biological sciences. Now a Professor of Economics and Director of the Program in Natural Resources Economics at the University of New Mexico, Cummings is a past president of the Association of Environmental and Resource Economists. He has been a consultant in matters of water resources management, forestry management, and energy policy for more than a decade, working on projects in both the United States and Latin America. Since joining the faculty at New Mexico in 1975, he has, among other things, worked with engineers at the Los Alamos National Laboratory in developing operation'management models for hot, dry rock geothermal systems.

  7. Editors' Fall Picks

    ERIC Educational Resources Information Center

    Heilbrun, Margaret; McCormack, Heather; Katterjohn, Anna; Kuzyk, Raya; Roncevic, Mirela; Fox, Bette-Lee; Hoffert, Barbara

    2009-01-01

    "Library Journal's" review editors select fall titles readers won't want to miss--"Waiting on a Train: The Embattled Future of Passenger Rail Service" (James McCommons); "Happy" (Alex Lemon); "Free for All: Joe Papp, the Public, and the Greatest Theater Story Ever Told" (Kenneth Turan & Joseph Papp); "In My Father's Shadow: A Daughter Remembers…

  8. Meet the APS Journal Editors

    NASA Astrophysics Data System (ADS)

    2016-05-01

    The Editors of the APS journals invite you to join them for conversation. The Editors will be available to answer questions, hear your ideas, and discuss any comments about the journals. All are welcome. Light refreshments will be served.

  9. Letters to the Editor

    NASA Astrophysics Data System (ADS)

    2000-11-01

    All the Letters to the Editor in this issue are in the same PostScript or PDF file. Contents The equivalence of mass and energy Peter Stansbury Head of Physics, Christ Church Grammar School, Claremont, Western Australia 6010 Comment on `A simple experiment to study parabolic surfaces' N Gauthier Department of Physics, The Royal Military College of Canada, Kingston, Ontario K7K 7B4, Canada

  10. Letters to the Editor

    NASA Astrophysics Data System (ADS)

    1997-03-01

    All the Letters to the Editor in this issue are in the same PostScript or PDF file. Contents Criticisms of hands-on pseudoscience David J Fisher 27 Elderberry Road, Cardiff CF5 3RG, UK Measuring varying fields Don Koks Adelaide University, Australia Relativity at A-level: a comment David Sang 3 Ellasdale Road, Bognor Regis, PO21 2SG, UK

  11. ION Configuration Editor

    NASA Technical Reports Server (NTRS)

    Borgen, Richard L.

    2013-01-01

    The configuration of ION (Inter - planetary Overlay Network) network nodes is a manual task that is complex, time-consuming, and error-prone. This program seeks to accelerate this job and produce reliable configurations. The ION Configuration Editor is a model-based smart editor based on Eclipse Modeling Framework technology. An ION network designer uses this Eclipse-based GUI to construct a data model of the complete target network and then generate configurations. The data model is captured in an XML file. Intrinsic editor features aid in achieving model correctness, such as field fill-in, type-checking, lists of valid values, and suitable default values. Additionally, an explicit "validation" feature executes custom rules to catch more subtle model errors. A "survey" feature provides a set of reports providing an overview of the entire network, enabling a quick assessment of the model s completeness and correctness. The "configuration" feature produces the main final result, a complete set of ION configuration files (eight distinct file types) for each ION node in the network.

  12. MCNP6 Cosmic-Source Option

    SciTech Connect

    McKinney, Gregg W; Armstrong, Hirotatsu; James, Michael R; Clem, John; Goldhagen, Paul

    2012-06-19

    MCNP is a Monte Carlo radiation transport code that has been under development for over half a century. Over the last decade, the development team of a high-energy offshoot of MCNP, called MCNPX, has implemented several physics and algorithm improvements important for modeling galactic cosmic-ray (GCR) interactions with matter. In this presentation, we discuss the latest of these improvements, a new Cosmic-Source option, that has been implemented in MCNP6.

  13. MCNP6 Fission Multiplicity with FMULT Card

    SciTech Connect

    Wilcox, Trevor; Fensin, Michael Lorne; Hendricks, John S.; James, Michael R.; McKinney, Gregg W.

    2012-06-18

    With the merger of MCNPX and MCNP5 into MCNP6, MCNP6 now provides all the capabilities of both codes allowing the user to access all the fission multiplicity data sets. Detailed in this paper is: (1) the new FMULT card capabilities for accessing these different data sets; (2) benchmark calculations, as compared to experiment, detailing the results of selecting these separate data sets for thermal neutron induced fission on U-235.

  14. EDITORIAL: Editor's Farewell

    NASA Astrophysics Data System (ADS)

    Hudson, R. P.

    1989-01-01

    The completion of Volume 26, 1989, marked the end of my tenure as Editor of Metrologia. My association with the journal, its parent body the Comité International des Poids et Mesures, its host organization the Bureau International des Poids et Mesures, the publishers Springer-Verlag and last (but by no means least) the Editorial Board, has been a pleasant one and I trust that the subscribers will have found the product to be generally satisfactory. There have been, it is true, some disappointments along the way and I shall mention two of these while expressing the hope that the new Editor will enjoy a greater success in their regard. First is the question of circulation, which has stayed dangerously low, although the shrinkage has tapered off in the most recent years. Because of the narrow public support, the costs of production are relatively high and this, through a consequently high subscription rate, tends to enshrine the unsatisfactory state of affairs. Modest schemes to broaden the journal's appeal and bring in a wider readership have foundered upon the first step, namely, that of procuring from staff members of the national standards laboratories the hoped-for articles which would discuss the state of the art in delivering the highest-quality measurement services to the public. However, some very interesting and bolder schemes are presently under discussion. I had also hoped to leaven the journal's content a little by regularly appearing articles on the latest developments within the great national laboratories. But, as with technical review articles, it has proven very difficult to find the right authors who can also spare the time, and only a few laboratories have found it possible to collaborate. In taking my leave, it remains for me to thank all the contributors, referees and readers for their support, to express the hope of an ever brighter future for Metrologia and to wish to the new Editor, Dr D A Blackburn, a happy and successful tenure.

  15. Letters to the Editor

    NASA Astrophysics Data System (ADS)

    2000-09-01

    All the Letters to the Editor in this issue are in the same PostScript or PDF file. Contents Heat and temperature Kevin Carlton Canterbury Christ Church University College, North Holmes Road, Canterbury, Kent CT1 1QU, UK James Bond's shoes J Oliver Linton Head of Physics, Wolverhampton Grammar School, Compton Road, Wolverhampton WV3 9RB, UK Of springs and strings Ronald Newburgh Extension School, Harvard University, Cambridge, MA 02138, USA Clarifying the concept Keith Atkin 14 Cortworth Road, Ecclesall, Sheffield S11 9LP, UK

  16. Letters to the Editor

    NASA Astrophysics Data System (ADS)

    1998-01-01

    All the Letters to the Editor in this issue are in the same PostScript or PDF file. Contents Physics and history Arthur I Miller Department of Science & Technology Studies, University College London, Gower Street, London WC1E 6BT, UK Physics and history: a reply David Miller Department of Physics and Astronomy, University College London, Gower Street, London WC1E 6BT, UK Cathode rays, the electron and Thomson's discovery John Harris 33 Glentham Road, London SW13 9JD, UK Vectors: swallow them whole! David Wheeler Mahanakorn University of Technology, Bangkok, Thailand

  17. Letters to the Editor

    NASA Astrophysics Data System (ADS)

    1998-03-01

    All the Letters to the Editor in this issue are in the same PostScript or PDF file. Contents Comment on `Magnetic and electric field strengths of high voltage power lines and household appliances' José Luis Giordano Dept. de Ciencia y Tecnología de Materiales y Fluidos, CPSI, Universidad de Zaragoza, Spain Twins paradox S R Carson Norton College, Malton, North Yorkshire, UK On alternative ways of finding the ratio of specific heats of gases Tomas Ficker Physics Department, Technical University of Brno, Czech Republic

  18. Letters to the Editor

    NASA Astrophysics Data System (ADS)

    1998-11-01

    All the Letters to the Editor in this issue are in the same PostScript or PDF file. Contents Narrow-band interference filters for lecture demonstrations A P Ovcharenko, B M Valiyov and V D Yegorenkov Kharkov State University, Ukraine Static electricity and the gas lift chair P Cooke Department of Physics, University of South Australia, Levels Campus, Pooraka, South Australia Relativistic mass Simon Carson Norton College, Langton Road, Norton, Malton, North Yorkshire YO17 9PT, UK Magazine or journal? Philip Britton Head of Physics, Leeds Grammar School, UK

  19. The new MCNP6 depletion capability

    SciTech Connect

    Fensin, M. L.; James, M. R.; Hendricks, J. S.; Goorley, J. T.

    2012-07-01

    The first MCNP based in-line Monte Carlo depletion capability was officially released from the Radiation Safety Information and Computational Center as MCNPX 2.6.0. Both the MCNP5 and MCNPX codes have historically provided a successful combinatorial geometry based, continuous energy, Monte Carlo radiation transport solution for advanced reactor modeling and simulation. However, due to separate development pathways, useful simulation capabilities were dispersed between both codes and not unified in a single technology. MCNP6, the next evolution in the MCNP suite of codes, now combines the capability of both simulation tools, as well as providing new advanced technology, in a single radiation transport code. We describe here the new capabilities of the MCNP6 depletion code dating from the official RSICC release MCNPX 2.6.0, reported previously, to the now current state of MCNP6. NEA/OECD benchmark results are also reported. The MCNP6 depletion capability enhancements beyond MCNPX 2.6.0 reported here include: (1) new performance enhancing parallel architecture that implements both shared and distributed memory constructs; (2) enhanced memory management that maximizes calculation fidelity; and (3) improved burnup physics for better nuclide prediction. MCNP6 depletion enables complete, relatively easy-to-use depletion calculations in a single Monte Carlo code. The enhancements described here help provide a powerful capability as well as dictate a path forward for future development to improve the usefulness of the technology. (authors)

  20. The New MCNP6 Depletion Capability

    SciTech Connect

    Fensin, Michael Lorne; James, Michael R.; Hendricks, John S.; Goorley, John T.

    2012-06-19

    The first MCNP based inline Monte Carlo depletion capability was officially released from the Radiation Safety Information and Computational Center as MCNPX 2.6.0. Both the MCNP5 and MCNPX codes have historically provided a successful combinatorial geometry based, continuous energy, Monte Carlo radiation transport solution for advanced reactor modeling and simulation. However, due to separate development pathways, useful simulation capabilities were dispersed between both codes and not unified in a single technology. MCNP6, the next evolution in the MCNP suite of codes, now combines the capability of both simulation tools, as well as providing new advanced technology, in a single radiation transport code. We describe here the new capabilities of the MCNP6 depletion code dating from the official RSICC release MCNPX 2.6.0, reported previously, to the now current state of MCNP6. NEA/OECD benchmark results are also reported. The MCNP6 depletion capability enhancements beyond MCNPX 2.6.0 reported here include: (1) new performance enhancing parallel architecture that implements both shared and distributed memory constructs; (2) enhanced memory management that maximizes calculation fidelity; and (3) improved burnup physics for better nuclide prediction. MCNP6 depletion enables complete, relatively easy-to-use depletion calculations in a single Monte Carlo code. The enhancements described here help provide a powerful capability as well as dictate a path forward for future development to improve the usefulness of the technology.

  1. MCNP4A: Features and philosophy

    SciTech Connect

    Hendricks, J.S.

    1993-05-01

    This paper describes MCNP, states its philosophy, introduces a number of new features becoming available with version MCNP4A, and answers a number of questions asked by participants in the workshop. MCNP is a general-purpose three-dimensional neutron, photon and electron transport code. Its philosophy is ``Quality, Value and New Features.`` Quality is exemplified by new software quality assurance practices and a program of benchmarking against experiments. Value includes a strong emphasis on documentation and code portability. New features are the third priority. MCNP4A is now available at Los Alamos. New features in MCNP4A include enhanced statistical analysis, distributed processor multitasking, new photon libraries, ENDF/B-VI capabilities, X-Windows graphics, dynamic memory allocation, expanded criticality output, periodic boundaries, plotting of particle tracks via SABRINA, and many other improvements. 23 refs.

  2. Editors' report, 2012.

    PubMed

    García-Puig, J; Alonso-Vega, G Gaspar; Ríos-Blanco, J J

    2013-01-01

    The editors of Revista Clínica Española (Rev Clin Esp) inform on their editorial activity during the last 12 months: a) objectives and attainments; b) editorial activity; and c) objectives for 2013. In 2012 the most relevant modifications concerning the editorial activity have been: a) revision by the responsible editor of all manuscripts sent to peer review, and b) translation into English of five manuscripts with abstract of each issue. From the first January to the 30th September 2012 we handled 457 manuscripts (50 manuscripts per month) a figure 22.5% higher than in 2011 (40.8 manuscripts per month). We have accepted 27.2% of all manuscripts (originals, 13.0%). We asked for 295 revisions to 241 reviewers and we have received 66.1% of the revisions asked for in less than two weeks (mean time to receive a revision, 11.3 days). The mean time to adopt an editorial decision for all manuscripts («accept»/«reject») has been 23.9 days (31.3 days in 2011; 35.4 in 2010). This figure has been 29.4 days for the original manuscripts (9.5 and 12.3 days less than in 2011 and 2010, respectively). The mean time taken since a manuscript is received to publication has dropped from 203 days in 2010, 168 in 2011 and 115 in 2012 (less than 3 months). The collaboration with the working groups has reported 19 published manuscripts in 2012. We hope that in 2013 both the English version and the digitalization of Rev Clin Esp from 1940 to 1999 (the journal is already digitalized since 2000) will become a reality. The renewal of the actual sections (i.e., clinical conference, an image for a diagnosis) pretends, with the collaboration of all, to make our journal, each day, better. PMID:23261839

  3. Editors in the Electronic Age.

    ERIC Educational Resources Information Center

    Dye, Robert M., Ed.

    Intended for newspaper writers and editors, this collection of articles includes the following titles and authors: "VDTs, TV Haven't Shocked Editors" by Jay Rogers; "Opinions Vary on Electronics' Effect" by Bob Nordyke; "A Few Kind Words for the Censors" by Hugh A. Mulligan; "Those Awards Have Their Limitations" by Larry Fortner; "Obituaries Are…

  4. Modularized training for technical editors

    SciTech Connect

    Murphy, P.W.

    1988-09-08

    This paper outlines the editorial services provided at the Lawrence Livermore National Laboratory (LLNL), sketches a syllabus of basic training for technical editors, describes the approach being used to develop this cost-effective individualized instruction for editors (experienced or not) new to work at LLNL, and enumerates the advantages of this approach. 8 refs.

  5. HEART handbook for guest editors

    SciTech Connect

    Vittitoe, C.N.

    1991-02-01

    This handbook outlines the basic job of guest editors for the HEART Conference proceedings, published by the DoD Nuclear Information and Analysis Center in the Journal of Radiation Effects, Research and Engineering. Suggestions are offered for procedures to aid the editors, authors, reviewers, and the publisher in assuring that the journal communicates clearly, concisely, and honestly.

  6. Microbial Properties Database Editor Tutorial

    EPA Science Inventory

    A Microbial Properties Database Editor (MPDBE) has been developed to help consolidate microbial-relevant data to populate a microbial database and support a database editor by which an authorized user can modify physico-microbial properties related to microbial indicators and pat...

  7. Message from the Editor

    NASA Astrophysics Data System (ADS)

    Stambaugh, Ronald D.

    2014-01-01

    This last year being an odd numbered year, the pages of Nuclear Fusion saw a large influx of expanded papers from the 2012 Fusion Energy Conference in San Diego. Many papers have focused on the scientific and technical challenges posed by ITER. Contributions are steadily increasing from the new superconducting tokamaks in Asia. The ITER Project continues to move ahead. Construction at the Cadarache site is quite remarkable. Buildings completed include the huge Poloidal Field Coils Winding Facility and the Headquarters building, which has been occupied by the ITER staff. Work is progressing on the Assembly building and the Cryostat Workshop. The base of the tokamak complex is being laid. Besides the construction that is taking place and will take place at the site, components from around the world have to navigate the complex route from Marseilles to the site. A test convoy replicating the dimensions and weights of the most exceptional ITER loads successfully traversed that route in 2013. We are pleased to report that the IAEA and ITER have finalized the agreement for ITER authors to publish papers in Nuclear Fusion . Nuclear Fusion is proud to continue its key role in providing the leading forum for the documentation of scientific progress and exchange of research results internationally toward fusion energy. Refereeing The Nuclear Fusion editorial office appreciates greatly the effort made by our referees to sustain the high quality of the journal. Since January 2005, we have been offering the most active referees over the past year a personal subscription to Nuclear Fusion with electronic access for one year, free of charge. We have excluded our Board Members, Guest Editors of special editions and those referees who were already listed in previous years. The following people have been selected: J.M. Canik, Oak Ridge National Laboratory, USA I.T. Chapman, Culham Centre for Fusion Energy, UK L.-G. Eriksson, Commission of the European Communities, Belgium T. Evans

  8. EDITORIAL: Editor's Introduction

    NASA Astrophysics Data System (ADS)

    Blackburn, D. A.

    1990-01-01

    Since its first issue in 1965 Metrologia has had just three editors, a history of tenure which suggests that those who hold the post find in it sufficient to interest, occupy, challenge and amuse them. I see no reason to doubt that this happy circumstance will continue and look forward to my own period as editor with the intention of retaining, insofar as I am able to interpret them, the best traditions the journal has established so far. As I take up my editorial duties I have become aware that surrounding Metrologia there is a small community of authors, reviewers and readers on whose support the success of the journal entirely depends. It is a community in which the roles change daily with some of its members engaged, even simultaneously, as reader, reviewer and author. I am well aware that the goodwill extended to me as I enter this community is in no small part due the efforts of the outgoing editor, Dr Ralph Hudson, whose easy, engaging and courteous, yet firm, relationship with authors and reviewers emerges clearly from editorial correspondence. I thank him for that he has done and wish him an active and happy retirement. A short foray into the records of Metrologia shows - in the first editorial - that four main kinds of article were originally envisaged: research articles likely to contribute to progress in fundamental scientific measurements, reports of experiments or techniques of particular importance or originality in the area of secondary measurement, articles concerning the decisions of the Comité International des Poids et Mesures, and review articles. No balance was specified but a priority was assigned to articles dealing with fundamental metrology. Of the four categories, the first two represent the core of Metrologia's activity and largely determine its reputation as a publication. For this reason, editorial implementation of the policy set by the CIPM is mainly exercised through the operation of a reviewing system which is intentionally strict

  9. EzEditor: a versatile sequence alignment editor for both rRNA- and protein-coding genes.

    PubMed

    Jeon, Yoon-Seong; Lee, Kihyun; Park, Sang-Cheol; Kim, Bong-Soo; Cho, Yong-Joon; Ha, Sung-Min; Chun, Jongsik

    2014-02-01

    EzEditor is a Java-based molecular sequence editor allowing manipulation of both DNA and protein sequence alignments for phylogenetic analysis. It has multiple features optimized to connect initial computer-generated multiple alignment and subsequent phylogenetic analysis by providing manual editing with reference to biological information specific to the genes under consideration. It provides various functionalities for editing rRNA alignments using secondary structure information. In addition, it supports simultaneous editing of both DNA sequences and their translated protein sequences for protein-coding genes. EzEditor is, to our knowledge, the first sequence editing software designed for both rRNA- and protein-coding genes with the visualization of biologically relevant information and should be useful in molecular phylogenetic studies. EzEditor is based on Java, can be run on all major computer operating systems and is freely available from http://sw.ezbiocloud.net/ezeditor/. PMID:24425826

  10. GUEST EDITORS' INTRODUCTION: Guest Editors' introduction

    NASA Astrophysics Data System (ADS)

    Coulson, Geoff; de Meer, Jan B.

    1997-03-01

    . Their scheme is embedded in an experimental ATM network with the potential for guaranteed QoS. The system features QoS support mechanisms in both the network and the end systems. Of particular interest is reported experience with a dynamic QoS adaptation protocol implemented in the network and based on video scaling techniques and filtering. In summary, this special issue provides an up to date review of approaches to QoS management and their practical realization. Of course, no claim is made as to comprehensiveness, but the chosen papers do serve as a highly representative sample of current directions in QoS research. The editors are very much obliged to all authors, reviewers and publishers. Without their excellent work, and the contribution of their valuable time this special issue would not have been possible.

  11. MCNP Perturbation Capability for Monte Carlo Criticality Calculations

    SciTech Connect

    Hendricks, J.S.; Carter, L.L.; McKinney, G.W.

    1999-09-20

    The differential operator perturbation capability in MCNP4B has been extended to automatically calculate perturbation estimates for the track length estimate of k{sub eff} in MCNP4B. The additional corrections required in certain cases for MCNP4B are no longer needed. Calculating the effect of small design changes on the criticality of nuclear systems with MCNP is now straightforward.

  12. From the Editor's Desk

    PubMed Central

    2014-01-01

    One of the admirable aspects of science is that its practitioners accept that advancing the field is an ongoing process. There is always more to be discovered. I view scientific publishing in a similar light. Last month, we instituted several changes to the journal, and I look forward to receiving your feedback. I anticipate some of the changes will be welcomed while others will not. ToxSci relies on the feedback from our readers, authors, and reviewers to assure that we are serving the research community to the highest degree. The editorial staff is dedicated to producing a high-quality journal that features outstanding science like that seen in this issue. In their Forum article, Wu and coworkers describe how increasing dietary diversity can reduce exposure to foodborne toxins. This is an important public health observation that can help mitigate many of the toxic effects described in the pages of the ToxSci. You will also note that we are using a new format for our Letters to the Editor. Rather than appearing at the end of the journal they immediately follow the highlights below. In this issue, the formulation of caroboxyfullerenes is the topic of discussion. I invite you to Look Inside ToxSci for the best original research in the field of toxicology. —Gary W. Miller PMID:25288704

  13. MatMCNP: A Code for Producing Material Cards for MCNP

    SciTech Connect

    DePriest, Kendall Russell; Saavedra, Karen C.

    2014-09-01

    A code for generating MCNP material cards (MatMCNP) has been written and verified for naturally occurring, stable isotopes. The program allows for material specification as either atomic or weight percent (fractions). MatMCNP also permits the specification of enriched lithium, boron, and/or uranium. In addition to producing the material cards for MCNP, the code calculates the atomic (or number) density in atoms/barn-cm as well as the multiplier that should be used to convert neutron and gamma fluences into dose in the material specified.

  14. MCNP APPLICATIONS FOR THE 21ST CENTURY

    SciTech Connect

    G. MCKINNEY; T. BOOTH; ET AL

    2000-10-01

    The Los Alamos National Laboratory (LANL) Monte Carlo N-Particle radiation transport code, MCNP, has become an international standard for a wide spectrum of neutron, photon, and electron radiation transport applications. The latest version of the code, MCNP 4C, was released to the Radiation Safety Information Computational Center (RSICC) in February 2000. This paper describes the code development philosophy, new features and capabilities, applicability to various problems, and future directions.

  15. MCNP application for the 21 century

    SciTech Connect

    McKinney, M.C.

    2000-08-01

    The Los Alamos National Laboratory (LANL) Monte Carlo N-Particle radiation transport code, MCNP, has become an international standard for a wide spectrum of neutron, photon, and electron radiation transport applications. The latest version of the code, MCNP 4C, was released to the Radiation Safety Information Computational Center (RSICC) in February 2000. This paper describes the code development philosophy, new features and capabilities, applicability to various problems, and future directions.

  16. PREFACE: Scientific and Publishing Editors

    NASA Astrophysics Data System (ADS)

    2016-02-01

    1.Scientific Editors Section 1: Particle physics Mikhail Skorohvatov - NRC Kurchatov Institute, Moscow, Russia Section 2: Nuclear physics Mikhail Danilov - ITEP NRC Kurchatov Institute, Moscow, Russia Section 3: Cosmic rays Arkady Galper - NRNU MEPhI, Moscow, Russia Anatoly Petrukhin - NRNU MEPhI, Moscow, Russia Section 4: Methods of experimental physics Valery Dmitrenko - NRNU MEPhI, Moscow, Russia 2.Publishing Editors Irene Arkhangelskaja - NRNU MEPhI, Moscow, Russia Pavel Buzhan - NRNU MEPhI, Moscow, Russia

  17. MCNP capabilities for nuclear well logging calculations

    SciTech Connect

    Forster, R.A.; Little, R.C.; Briesmeister, J.F.; Hendricks, J.S. . Applied Theoretical Physics Div.)

    1990-06-01

    The Los Alamos Radiation Transport Code System (LARTCS) consists of state-of-the-art Monte Carlo and discrete ordinates transport codes and data libraries. This paper discusses how the general-purpose continuous-energy Monte Carlo code MCNP ({und M}onte {und C}arlo {und n}eutron {und p}hoton), part of the LARTCS, provides a computational predictive capability for many applications of interest to the nuclear well logging community. The generalized three-dimensional geometry of MCNP is well suited for borehole-tool models. SABRINA, another component of the LARTCS, is a graphics code that can be used to interactively create a complex MCNP geometry. Users can define many source and tally characteristics with standard MCNP features. The time-dependent capability of the code is essential when modeling pulsed sources. Problems with neutrons, photons, and electrons as either single particle or coupled particles can be calculated with MCNP. The physics of neutron and photon transport and interactions is modeled in detail using the latest available cross-section data.

  18. MCNP-ORIGEN2 Coupling Utility Program

    Energy Science and Technology Software Center (ESTSC)

    1997-07-30

    The MOCUP code system is a series of pre- and post-processor modules to connect the MCNP Monte Carlo transport code and the ORIGEN2.1 depletion and isotopics code into a generalized transport/depletion package for use on non-lattice or non-uniform lattice reactor calculations. No modifications were made to either MCNP or ORIGEN2.1, permitting standard versions of each code to be used. MOCUP contains a simple graphical user interface to allow the user to easily execute the modulesmore » governing MCNP and ORIGEN2.1 input assembly, output processing, and execution, and to perform various file housekeeping tass. Flux and reaction rate calculations are performed in MCNP, with the results extracted by the menpPRO module and passed to the ORIGEN2.1 code by the origenPRO module for deletion. The resulting new isotopic inventories are used to modify the MCNP input in the compPRO module for use in the next timestep. MOCUP permits an arbitary number of depletable cells, different depletable cell types (fuel, targets, etc.) and isotopes that may be tracked. anticipated applications are to test and research reactor physics analyses; isotope production; fuel, target, filter, control, and/or burnable absorber depletion; structural material transmutation; and verification of lattice code calculations.« less

  19. MCNP analyses of criticality calculation results

    SciTech Connect

    Forster, R.A.; Booth, T.E.

    1995-05-01

    Careful assessment of the results of a calculation by the code itself can reduce mistakes in the problem setup and execution. MCNP has over four hundred error messages that inform the user of FATAL or WARNING errors that have been discovered during the processing of just the input file. The latest version, MCNP4A, now performs a self assessment of the calculated results to aid the user in determining the quality of the Monte Carlo results. MCNP4A, which was released to RSIC in October 1993, contains new analyses of the MCNP Monte Carlo calculation that provide simple user WARNINGs for both criticality and fixed source calculations. The goal of the new analyses is to provide the MCNP criticality practitioner with enough information in the output to assess the validity of the k{sub eff} calculation and any associated tallies. The results of these checks are presented in the k{sub eff} results summary page, several k{sub eff} tables and graphs, and tally tables and graphs. Plots of k{sub eff} at the workstation are also available as the problem is running or in a postprocessing mode to assess problem performance and results.

  20. Message from the Editor

    NASA Astrophysics Data System (ADS)

    Stambaugh, Ronald D.

    2013-01-01

    reviewed five manuscripts in the period November 2011 to December 2012 and provided excellent advice to the authors. We have excluded our Board Members, Guest Editors of special editions and those referees who were already listed in recent years. The following people have been selected: Marina Becoulet, CEA-Cadarache, France Jiaqui Dong, Southwestern Institute of Physics, China Emiliano Fable, Max-Planck-Institut für Plasmaphysik, Germany Ambrogio Fasoli, Ecole Polytechnique Federale de Lausanne, Switzerland Eric Fredrickson, Princeton Plasma Physics Laboratory, USA Manuel Garcia-Munoz, Max-Planck-Institut fuer Plasmaphysik, Germany William Heidbrink, California University, USA Katsumi Ida, National Inst. For Fusion Science, Japan Peter Stangeby, Toronto University, Canada James Strachan, Princeton Plasma Physics Laboratory, USA Victor Yavorskij, Ukraine National Academy of Sciences, Ukraine In addition, there is a group of several hundred referees who have helped us in the past year to maintain the high scientific standard of Nuclear Fusion. At the end of this issue we give the full list of all referees for 2012. Our thanks to them!

  1. SABRINA - an interactive geometry modeler for MCNP

    SciTech Connect

    West, J.T.; Murphy, J. )

    1988-01-01

    One of the most difficult tasks when analyzing a complex three-dimensional system with Monte Carlo is geometry model development. SABRINA attempts to make the modeling process more user-friendly and less of an obstacle. It accepts both combinatorial solid bodies and MCNP surfaces and produces MCNP cells. The model development process in SABRINA is highly interactive and gives the user immediate feedback on errors. Users can view their geometry from arbitrary perspectives while the model is under development and interactively find and correct modeling errors. An example of a SABRINA display is shown. It represents a complex three-dimensional shape.

  2. Adjoint-Based Uncertainty Quantification with MCNP

    SciTech Connect

    Seifried, Jeffrey E.

    2011-09-01

    This work serves to quantify the instantaneous uncertainties in neutron transport simulations born from nuclear data and statistical counting uncertainties. Perturbation and adjoint theories are used to derive implicit sensitivity expressions. These expressions are transformed into forms that are convenient for construction with MCNP6, creating the ability to perform adjoint-based uncertainty quantification with MCNP6. These new tools are exercised on the depleted-uranium hybrid LIFE blanket, quantifying its sensitivities and uncertainties to important figures of merit. Overall, these uncertainty estimates are small (< 2%). Having quantified the sensitivities and uncertainties, physical understanding of the system is gained and some confidence in the simulation is acquired.

  3. Application of MCNP{trademark} to computed tomography in medicine

    SciTech Connect

    Brockhoff, R.C.; Estes, G.P.; Hills, C.R.; Demarco, J.J.; Solberg, T.D.

    1996-03-01

    The MCNP{trademark} code has been used to simulate CT scans of the MIRD human phantom. In addition. an actual CT scan of a patient was used to create an MCNP geometry, and this geometry was computationally ``CT scanned`` using MCNP to reconstruct CT images. The results show that MCNP can be used to model the human body based on data obtained from CT scans and to simulate CT scans that are based on these or other models.

  4. New methods for neutron response calculations with MCNP

    SciTech Connect

    Hendricks, J.S.

    1997-05-01

    MCNP4B was released for international distribution in February, 1997. The author summarized the new MCNP4B features since the release of MCNP4A over three years earlier and compare some results. Then he describes new methods being developed for future code releases. The focus is methods and applications of ex-core neutron response calculations.

  5. Research Review: Magazine Editors and Editing Practices.

    ERIC Educational Resources Information Center

    Jolliffe, Lee

    1994-01-01

    Reviews and critiques literature in the subfield of magazine editing research, chiefly biographical studies of individual editors and various types of studies of editorial practices, including surveys, magazine content analyses, and close qualitative examinations of editors' relationships with others. (SR)

  6. New Editors, Editorial Advisory Board for Eos

    NASA Astrophysics Data System (ADS)

    Richman, Barbara T.

    2010-11-01

    Eos has two new editors and, with this issue, a revitalized Editorial Advisory Board. Christina M. S. Cohen, of the California Institute of Technology, is the new editor for space sciences. She succeeds Manuel Grande, who had served since 2006. Carol A. Stein, of the University of Illinois at Chicago, is the new editor for solid Earth. She succeeds John W. Geissman, who has been solid Earth editor since 2001; he will continue through the end of 2010.

  7. Learning To Use a Text Editor.

    ERIC Educational Resources Information Center

    Beal, Carole R.; Griffin, Elizabeth A.

    Designed to determine how quickly elementary school children can learn to use a text editor and what editing concepts are difficult for them to master, this study presents preliminary data on children's acquisition of text editor skills and on the kinds of revisions they accomplished with the text editor. Observations were made on a total of 25…

  8. Message from the Editor Message from the Editor

    NASA Astrophysics Data System (ADS)

    Thomas, Paul

    2012-04-01

    Whilst travelling to Vienna to hand over the Editorship of Nuclear Fusion to Ron Stambaugh, I jotted down a few ideas to put in a farewell message. Somewhat unsurprisingly, I find them almost identical to the remarks that Chris Schueller made in handing over to me five years ago. Both of us served in this role for five years, which seems like a good timescale to replace presidents and editors alike; just to allow a fresh approach. In addition, since I have been directly involved in ITER, I have found it increasingly difficult, due to time pressure, to give the journal the attention that it deserves. Therefore, I am very pleased that Ron Stambaugh has agreed to take over as Editor. Not only does he bring the experience as a leading figure in the US fusion programme but, in addition, he has all the contacts, worldwide, from his leadership of the ITPA. I am completely assured that the journal is in a highly competent pair of hands. Such a farewell should not lack my heartfelt thanks to all of those who have made being Editor of Nuclear Fusion so enjoyable and stimulating; readership, authors, referees, the Editorial Board and the NF Office alike. I wish Ron all the best for his tenure and have offered such help and support as I am able to give.

  9. CMS Configuration Editor: GUI based application for user analysis job

    NASA Astrophysics Data System (ADS)

    de Cosa, A.

    2011-12-01

    We present the user interface and the software architecture of the Configuration Editor for the CMS experiment. The analysis workflow is organized in a modular way integrated within the CMS framework that organizes in a flexible way user analysis code. The Python scripting language is adopted to define the job configuration that drives the analysis workflow. It could be a challenging task for users, especially for newcomers, to develop analysis jobs managing the configuration of many required modules. For this reason a graphical tool has been conceived in order to edit and inspect configuration files. A set of common analysis tools defined in the CMS Physics Analysis Toolkit (PAT) can be steered and configured using the Config Editor. A user-defined analysis workflow can be produced starting from a standard configuration file, applying and configuring PAT tools according to the specific user requirements. CMS users can adopt this tool, the Config Editor, to create their analysis visualizing in real time which are the effects of their actions. They can visualize the structure of their configuration, look at the modules included in the workflow, inspect the dependences existing among the modules and check the data flow. They can visualize at which values parameters are set and change them according to what is required by their analysis task. The integration of common tools in the GUI needed to adopt an object-oriented structure in the Python definition of the PAT tools and the definition of a layer of abstraction from which all PAT tools inherit.

  10. Line-Editor Computer Program

    NASA Technical Reports Server (NTRS)

    Scott, Peter J.

    1989-01-01

    ZED editing program for DEC VAX computer simple, powerful line editor for text, program source code, and nonbinary data. Excels in processing of text by use of procedure files. Also features versatile search qualifiers, global changes, conditionals, online help, hexadecimal mode, space compression, looping, logical combinations of search strings, journaling, visible control characters, and automatic detabbing. Users of Cambridge implementation devised such ZED procedures as chess games, calculators, and programs for evaluating pi. Written entirely in C.

  11. Training the unseasoned technical writer-editor: From the trainee's perspective

    SciTech Connect

    Gibbs, B.R.

    1991-01-01

    Many unseasoned technical writer-editors who are not adequately trained may become seasoned inadequately trained technical writer-editors. This problem can occur when a trainee is involved in an ineffective training program, but it can be alleviated by the trainer's assessing the unseasoned writer's talents, becoming involved with the trainee's growth in writing and editing skills, and helping him to visualize his potential as a technical writer-editor. Assessment, support, mentoring, and nurturing are important elements in the trainee's growth process and in any good training or internship program. 1 ref.

  12. EDITORIAL: Message from the Editor Message from the Editor

    NASA Astrophysics Data System (ADS)

    Thomas, Paul

    2010-02-01

    November 2009 and provided particularly detailed advice to the authors. The other three have been very helpful in 'minority fields'. We have excluded our Board members, Guest Editors of special editions and those referees who were already listed in the last four years. Guest Editors' work on papers submitted to their Special Issues is also excluded from consideration. The following people have been selected: Tomonori Takizuka, JAEA-Naka Fusion Institute, Japan Rudolf Neu, Max-Planck-Institut für Plasmaphysik, Germany Sibylle Guenter, Max-Planck-Institut für Plasmaphysik, Germany Taik-Soo Hahm, Princeton Plasma Physics Laboratory, United States David R. Mikkelsen, Princeton Plasma Physics Laboratory, United States Peter C. de Vries, EURATOM/UKAEA Fusion Association, United Kingdom Yasuhiro Suzuki, National Institute for Fusion Science, Japan Jerzy Wolowski, Institute of Plasma Physics and Laser Microfusion, Poland Tetsuo Tanabe, Kyushu University, Japan Yasuyuki Yagi, National Institute of Advanced Industrial Science and Technology, Japan Congratulations and many, many thanks! The Guest Editors of special editions deserve a special mention for the excellent help that they have given us. They are: Taik-Soo Hahm, Princeton Plasma Physics Laboratory, United States, Special Issue on H-Mode Physics and Transport Barriers Yaroslav Kolesnichenko, Institute for Nuclear Research, Ukraine, Special Issue on Energetic Particles in Magnetic Confinement Systems Kimitaka Itoh, National Institute for Fusion Science, Japan and Howard R. Wilson, University of York, UK, Special Issue on Plasma Instabilities Bernhard Unterberg, Forschungszentrum Juelich, Germany, Special Issue on Stochastic Fusion Plasma In addition, there is a group of several hundred referees who have helped us in the past year to maintain the high scientific standard of Nuclear Fusion. At the end of this issue we give the full list of all referees for 2009. Our thanks to them! Authors The winner of the 2009 Nuclear Fusion

  13. Evaluation of Geometric Progression (GP) Buildup Factors using MCNP Codes (MCNP6.1 and MCNP5-1.60)

    NASA Astrophysics Data System (ADS)

    Kim, Kyung-O.; Roh, Gyuhong; Lee, Byungchul

    2016-02-01

    The gamma-ray buildup factors of three-dimensional point kernel code (QAD-CGGP) are re-evaluated by using MCNP codes (MCNP6.1 and MCNPX5-1.60) and ENDF/B-VI.8 photoatomic data, which cover an energy range of 0.015-15 MeV and an iron thickness of 0.5-40 Mean Free Path (MFP). These new data are fitted to the Geometric Progression (GP) fitting function and are then compared with ANS standard data equipped with QAD-CGGP. In addition, a simple benchmark calculation was performed to compare the QAD-CGGP results applied with new and existing buildup factors based on the MCNP codes. In the case of the buildup factors of low-energy gamma-rays, new data are evaluated to be about 5% higher than the existing data. In other cases, these new data present a similar trend based on the specific penetration depth, while existing data continuously increase beyond that depth. In a simple benchmark, the calculations using the existing data were slightly underestimated compared to the reference data at a deep penetration depth. On the other hand, the calculations with new data were stabilized with an increasing penetration depth, despite a slight overestimation at a shallow penetration depth.

  14. The MCNP5 Random number generator

    SciTech Connect

    Brown, F. B.; Nagaya, Y.

    2002-01-01

    MCNP and other Monte Carlo particle transport codes use random number generators to produce random variates from a uniform distribution on the interval. These random variates are then used in subsequent sampling from probability distributions to simulate the physical behavior of particles during the transport process. This paper describes the new random number generator developed for MCNP Version 5. The new generator will optionally preserve the exact random sequence of previous versions and is entirely conformant to the Fortran-90 standard, hence completely portable. In addition, skip-ahead algorithms have been implemented to efficiently initialize the generator for new histories, a capability that greatly simplifies parallel algorithms. Further, the precision of the generator has been increased, extending the period by a factor of 10{sup 5}. Finally, the new generator has been subjected to 3 different sets of rigorous and extensive statistical tests to verify that it produces a sufficiently random sequence.

  15. Familiarizing with science editors' associations

    PubMed Central

    Gasparyan, Armen Yuri

    2011-01-01

    The number of science editors' associations is growing to resolve a variety of professional problems. The main objective of the associations is to educate their members by facilitating dissemination of information, publishing scholarly journals, books, networking of experts, and regular meetings. There are many science editing associations – general and specialized, traditional, and new. The article presents activities of some of these associations, which include upholding standards of science writing, editing, indexing, research reporting, peer review, editorial independence, and other editorial policies. PMID:22180273

  16. 2011 Editors' Citations for Excellence in Refereeing

    NASA Astrophysics Data System (ADS)

    2012-12-01

    In the 2 October 2012 issue of Eos, the 2011 Editors' Citations for Excellence in Refereeing were announced (Eos, 93(40), 391-394, doi:10.1029/2012EO400012). The editors' citations recognize this special service to the Union, and these individuals are to be commended for consistently providing constructive and thoughtful reviews. The reviewers listed below were inadvertently omitted from that announcement. They, too, have been cited by editors of AGU journals for excellence in refereeing.

  17. MCNP4B{sup {trademark}} verification and validation

    SciTech Connect

    Hendricks, J.S.; Court, J.D.

    1996-08-01

    Several new features and bug fixes have been incorporated into the new release of MCNP. As required by the MCNP Software Quality Assurance Plan, these changes to the code and the test set are documented here for user reference. This document summarizes the new MCNP4B features and corrections, separated into major and minor groupings. Also included are a code cleanup section and a section delineating problems identified in LA-12839 which have not been corrected. Finally, we document the MCNP4B test set modifications and explain how test set coverage has been improved.

  18. Neutron Cross Section Library Based on JEFF3.1 for Use with MCNP.

    Energy Science and Technology Software Center (ESTSC)

    2007-03-20

    Version 00 This continuous energy cross-section data library in ACE format is for shielding and criticality applications done with MCNP. In addition to the description of the NJOY processing procedure used to create the library, the included report NEA/NSC/DOC(2006)18 contains results from the benchmarking activity aimed at testing the quality of the data for criticality and shielding applications. The library at 300K has been verified: visually (no discontinuities, correct processing in all range) and withmore » comparisons with other libraries available for the same purposes (ENDF/B-VI.8, JEF2.2, JENDL3.3, …) A set of experiments using MCNP4c are used in order to validate the processed library.« less

  19. EDITORIAL: Message from the Editor Message from the Editor

    NASA Astrophysics Data System (ADS)

    Thomas, Paul

    2011-01-01

    As usual, being an even year, the 23rd IAEA Fusion Energy Conference took place at Daejeon, Korea. The event was notable not just for the quality of the presentations but also for the spectacular opening ceremony, in the presence of the Prime Minister, Kim Hwang-sik. The Prime Minister affirmed the importance of research into fusion energy research and pledged support for ITER. Such political visibility is good news, of course, but it brings with it the obligation to perform. Fortunately, good performance was much in evidence in the papers presented at the conference, of which a significant proportion contain 'ITER' in the title. Given this importance of ITER and the undertaking by the Nuclear Fusion journal to publish papers associated with Fusion Energy Conference presentations, the Nuclear Fusion Editorial Board has decided to adopt a simplified journal scope that encompasses technology papers more naturally. The scope is available from http://iopscience.iop.org/0029-5515/page/Journal%20information but is reproduced here for clarity: Nuclear Fusion publishes articles making significant advances to the field of controlled thermonuclear fusion. The journal scope includes: the production, heating and confinement of high temperature plasmas; the physical properties of such plasmas; the experimental or theoretical methods of exploring or explaining them; fusion reactor physics; reactor concepts; fusion technologies. The key to scope acceptability is now '....significant advances....' rather than any particular area of controlled thermonuclear fusion research. It is hoped that this will make scope decisions easier for the Nuclear Fusion office, the referees and the Editor.The Nuclear Fusion journal has continued to make an important contribution to the research programme and has maintained its position as the leading journal in the field. This is underlined by the fact that Nuclear Fusion has received an impact factor of 4.270, as listed in ISI's 2009 Science Citation

  20. Examining Editor-Author Ethics: Real-World Scenarios from Interviews with Three Journal Editors

    ERIC Educational Resources Information Center

    Amare, Nicole; Manning, Alan

    2009-01-01

    Those who submit manuscripts to academic journals may benefit from a better understanding of how editors weigh ethics in their interactions with authors. In an attempt to ascertain and to understand editors' ethics, we interviewed 3 current academic journal editors of technical and/or business communication journals. We asked them about the…

  1. MCNP simulations of material exposure experiments (u)

    SciTech Connect

    Temple, Brian A

    2010-12-08

    Simulations of proposed material exposure experiments were performed using MCNP6. The experiments will expose ampules containing different materials of interest with radiation to observe the chemical breakdown of the materials. Simulations were performed to map out dose in materials as a function of distance from the source, dose variation between materials, dose variation due to ampule orientation, and dose variation due to different source energy. This write up is an overview of the simulations and will provide guidance on how to use the data in the spreadsheet.

  2. ESO Vacancy - Editor (EDG 604)

    NASA Astrophysics Data System (ADS)

    2002-09-01

    Assignment: Within the ESO Education and Public Relations Department team, your main tasks and responsibilities will comprise: • Development, update and maintenance of the comprehensive ESO Outreach website in its new look, including preparation of related material (texts, images, etc.) to be displayed; • Design, layout and production of the ESO quarterly journal “The Messenger” (e.g. image selection and processing, technical editing, etc.), in close collaboration with the Messenger editor; • Conception and production of promotional brochures, posters and other EPR products, in close collaboration with the Head of the Education and Public Relations Dept. of ESO Press Releases and various high-level publications, including the ESO Annual Report.

  3. Farewell editorial from the founding editors.

    PubMed

    Izatt, Joseph A; Faris, Gregory

    2016-01-01

    The retiring Editor-in-Chief and Deputy Editor provide a brief retrospective of the first six volumes of Biomedical Optics Express, thank the Editorial Board and OSA professional staff, and endorse the new journal leadership and the continued support of the journal by the biomedical optics community. PMID:26819829

  4. Letter to Editor - "Reply to RP Heaney"

    Technology Transfer Automated Retrieval System (TEKTRAN)

    A letter to the editor was submitted in reply to a letter written to the editor of the American Journal of Clinical Nutrition regarding a recent publication (Hunt, CD. and Johnson, LK. Calcium requirements: new estimations for men and women by cross-sectional statistical analyses of calcium balance...

  5. Linguistic Prescriptivism in Letters to the Editor

    ERIC Educational Resources Information Center

    Lukac, Morana

    2016-01-01

    The public's concern with the fate of the standard language has been well documented in the history of the complaint tradition. The print media have for centuries featured letters to the editor on questions of language use. This study examines a corpus of 258 language-related letters to the editor published in the English-speaking print media. By…

  6. 2010 editors' citations for excellence in refereeing

    NASA Astrophysics Data System (ADS)

    2011-09-01

    The reviewers listed on these pages have been cited by editors of AGU journals for excellence in refereeing. The editors' citations recognize this special service to the Union. These individuals (photographs provided as available) are to be commended for consistently providing constructive and thoughtful reviews.

  7. 2011 editors' citations for excellence in refereeing

    NASA Astrophysics Data System (ADS)

    Anonymous

    2012-10-01

    The reviewers listed below have been cited by editors of AGU journals for excellence in refereeing. The editors' citations recognize this special service to the Union, and these individuals (photographs provided as available) are to be commended for consistently providing constructive and thoughtful reviews.

  8. EDITORIAL: Message from the Editor

    NASA Astrophysics Data System (ADS)

    Thomas, Paul

    2009-01-01

    Plasmaphysik, Germany) V. Philipps (Forschungszentrum Juelich, Germany) S. Zweben (Princeton Plasma Physics Laboratory, USA) Y. Hirano (National Institute of Advanced Industrial Science and Technology, Japan) Y. Takase (Tokyo University, Japan) In addition there is a group of several hundred referees who have helped us in the past year to maintain the high scientific standard of Nuclear Fusion. At the end of this issue we give the full list of all referees for 2008. Our thanks to them! Authors The winner of the 2007 award was Clemente Angioni for the paper entitled `Density response to central electron heating: theoretical investigations and experimental observations in ASDEX Upgrade' (Nucl. Fusion 44 8277-845). The winner of the 2008 Nuclear Fusion award is Todd Evans et al for the paper `Suppression of large edge localized modes with edge resonant magnetic fields in high confinement DIII-D plasmas' (Nucl. Fusion 45 595-607). The awards were presented by the IAEA Deputy Director General, Werner Burkart, and the Chairman of the Board of Editors, Mitsuru Kikuchi, on 16 October 2008 at the 22nd IAEA Fusion Energy Conference in Geneva, Switzerland. Given the topicality of these papers for the ITER design, it is a matter of pride to the journal that the work should be published in Nuclear Fusion. Reviews Like many who have worked for a long time in the field, I still make use of Nuclear Fusion Reviews that go back 20 or 30 years. It is particularly useful, therefore, that the Board of Editors has been working to re-activate the review programme. The first fruits will appear in this issue, in the form of `A review of zonal flow experiments', by Akihide Fujisawa. The special procedures for Reviews should be noted: most specifically that they should normally be commissioned by the Board of Editors. However, not only is the Board of Editors working on a programme but I am sure that they would be pleased to consider suggestions for review subjects. Letters The reputation of Nuclear

  9. MCNP6 Cosmic & Terrestrial Background Particle Fluxes -- Release 4

    SciTech Connect

    McMath, Garrett E.; McKinney, Gregg W.; Wilcox, Trevor

    2015-01-23

    Essentially a set of slides, the presentation begins with the MCNP6 cosmic-source option, then continues with the MCNP6 transport model (atmospheric, terrestrial) and elevation scaling. It concludes with a few slides on results, conclusions, and suggestions for future work.

  10. Benchmarking MCNP and TRIPOLI with PGNAA measurements

    NASA Astrophysics Data System (ADS)

    Carasco, C.; Perot, B.; Sikora, A.; Mauerhofer, E.; Havenith, A.; Payan, E.; Kettler, J.; Kring, T.; Ma, J. L.

    2014-06-01

    The French Alternative Energies and Atomic Energy Commission (CEA Cadarache), the Forschungszentrum Jülich GmbH (FZJ), and the RWTH Aachen University (RWTH) are involved in a cooperation aiming at characterizing toxic and reactive elements in radioactive waste packages by means of Prompt Gamma Neutron Activation Analysis (PGNAA). The design of an optimized measurement system and the assessment of its performances for realistic scenarios can be conveniently studied by numerical Monte Carlo simulation, provided the model and nuclear data offer a sufficient precision. Previous studies performed with MCNP have shown that when the nuclear data libraries lack of precision, relevant results can still be obtained by performing calculations in multiple steps (by first determining the radiative capture rate, and transporting the induced gamma toward the detector) and by injecting valid gamma-ray production data in-between [1]. In such cases, it is interesting to compare the results obtained with different codes. In the present paper, we propose to compare the MCNP and TRIPOLI codes with measurements obtained in MEDINA (Multi Element Detection based on Instrumental Neutron Activation), which is the new FZJ PGNAA facility [2]. The aim of the measurement campaign is to assess capture gamma rays of toxic elements that can be found in 200 L waste drums which are expected for geological repository.

  11. Hot Cell Window Shielding Analysis Using MCNP

    SciTech Connect

    Chad L. Pope; Wade W. Scates; J. Todd Taylor

    2009-05-01

    The Idaho National Laboratory Materials and Fuels Complex nuclear facilities are undergoing a documented safety analysis upgrade. In conjunction with the upgrade effort, shielding analysis of the Fuel Conditioning Facility (FCF) hot cell windows has been conducted. This paper describes the shielding analysis methodology. Each 4-ft thick window uses nine glass slabs, an oil film between the slabs, numerous steel plates, and packed lead wool. Operations in the hot cell center on used nuclear fuel (UNF) processing. Prior to the shielding analysis, shield testing with a gamma ray source was conducted, and the windows were found to be very effective gamma shields. Despite these results, because the glass contained significant amounts of lead and little neutron absorbing material, some doubt lingered regarding the effectiveness of the windows in neutron shielding situations, such as during an accidental criticality. MCNP was selected as an analysis tool because it could model complicated geometry, and it could track gamma and neutron radiation. A bounding criticality source was developed based on the composition of the UNF. Additionally, a bounding gamma source was developed based on the fission product content of the UNF. Modeling the windows required field inspections and detailed examination of drawings and material specifications. Consistent with the shield testing results, MCNP results demonstrated that the shielding was very effective with respect to gamma radiation, and in addition, the analysis demonstrated that the shielding was also very effective during an accidental criticality.

  12. An assessment of the MCNP4C weight window

    SciTech Connect

    Christopher N. Culbertson; John S. Hendricks

    1999-12-01

    A new, enhanced weight window generator suite has been developed for MCNP version 4C. The new generator correctly estimates importances in either a user-specified, geometry-independent, orthogonal grid or in MCNP geometric cells. The geometry-independent option alleviates the need to subdivide the MCNP cell geometry for variance reduction purposes. In addition, the new suite corrects several pathologies in the existing MCNP weight window generator. The new generator is applied in a set of five variance reduction problems. The improved generator is compared with the weight window generator applied in MCNP4B. The benefits of the new methodology are highlighted, along with a description of its limitations. The authors also provide recommendations for utilization of the weight window generator.

  13. Performance of MCNP4A on seven computing platforms

    SciTech Connect

    Hendricks, J.S.; Brockhoff, R.C.

    1994-12-31

    The performance of seven computer platforms has been evaluated with the MCNP4A Monte Carlo radiation transport code. For the first time we report timing results using MCNP4A and its new test set and libraries. Comparisons are made on platforms not available to us in previous MCNP timing studies. By using MCNP4A and its 325-problem test set, a widely-used and readily-available physics production code is used; the timing comparison is not limited to a single ``typical`` problem, demonstrating the problem dependence of timing results; the results are reproducible at the more than 100 installations around the world using MCNP; comparison of performance of other computer platforms to the ones tested in this study is possible because we present raw data rather than normalized results; and a measure of the increase in performance of computer hardware and software over the past two years is possible. The computer platforms reported are the Cray-YMP 8/64, IBM RS/6000-560, Sun Sparc10, Sun Sparc2, HP/9000-735, 4 processor 100 MHz Silicon Graphics ONYX, and Gateway 2000 model 4DX2-66V PC. In 1991 a timing study of MCNP4, the predecessor to MCNP4A, was conducted using ENDF/B-V cross-section libraries, which are export protected. The new study is based upon the new MCNP 25-problem test set which utilizes internationally available data. MCNP4A, its test problems and the test data library are available from the Radiation Shielding and Information Center in Oak Ridge, Tennessee, or from the NEA Data Bank in Saclay, France. Anyone with the same workstation and compiler can get the same test problem sets, the same library files, and the same MCNP4A code from RSIC or NEA and replicate our results. And, because we report raw data, comparison of the performance of other compute platforms and compilers can be made.

  14. Editor's Choice Offered as a Service

    NASA Astrophysics Data System (ADS)

    Richman, Barbara T.

    2010-06-01

    Editor's Choice is now being offered as a service rather than on a subscription basis. As in the past, articles will be selected by collection editors with assistance from advisory panels. The selected articles will be listed on the AGU Web site (http://www.agu.org/pubs/journals/virtual/editors_choice/); these lists will be accessible to anyone. Those who are interested in reading the articles can access them through a personal or institutional subscription or can purchase them either individually or as part of a MultiChoice packet.

  15. Editor profile: Donald H. Eckhardt

    NASA Astrophysics Data System (ADS)

    For Don Eckhardt, editor of AGU's Geodynamics book series, the scope of subjects appropriate for inclusion in the series is wide. “ The forces implied in the term ‘geodynamics’ operate on this planet on all scales and from the surface deep into the interior,” he says. The articles collected in the red volumes are often united, he suggests, by “an emphasis on common techniques as much as by subject matter.”Like the potential range of topics in the geodynamics series, the breadth of Eckhardt's professional responsibilities is large. As director of the Earth Sciences Division at the Air Force Geophysical Laboratory (AFGL) at Hanscom Air Force Base near Bedford, Mass., he oversees research and development in geodesy, gravity, seismology, geology, and dynamical astronomy. He administers more than 50 outside contracts while actively conducting theoretical and applied research of his own. In the past year, he has become well-known for his proposition that geophysical measurements made by an AFGL team demonstrate the existence and magnitude of two previously undetected fundamental forces in the universe, supplementing electromagnetism, the strong and weak nuclear forces, and Newtonian gravity.

  16. EDITORIAL: Letter from the Editor Letter from the Editor

    NASA Astrophysics Data System (ADS)

    Pashinin, Pavel P.

    2013-01-01

    Dear readers, contributors, and members of the world laser physics community. It is a great honour for us to introduce to you our new publishing partner, IOP Publishing, a subsidiary of the Institute of Physics, United Kingdom. IOP Publishing is a world renowned authority in producing journals, magazines, websites and services that enable researchers and research organizations to present their work to a world-wide audience. Laser Physics, the first English-language scientific journal in Russia, was founded in 1990 on the initiative of Alexander M Prokhorov, a pioneer and leader in laser physics research. Professor Prokhorov served as the first Editor-in-Chief of the journal until 2002. We are proud that it is our 23rd year of publishing Laser Physics and our 10th year of publishing Laser Physics Letters. We would like to honour the memory of our friend, late Professor Igor Yevseyev, whose enthusiasm and unwavering dedication to our journals contributed most significantly to their success. It was initially his idea in 2011 to approach IOP with a partnership proposal. We deeply regret that he is no longer with us as we enter this productive alliance. Now, in partnership with IOP, we are turning a new page in providing world-wide access to the cutting-edge research results in our journals, serving our well established global audience. We see new horizons opening for our journals for years to come and hope that our readers share our enthusiasm and aspirations. Please accept our best wishes for all your new scientific endeavors in the exciting field of laser physics.

  17. Enhancements to the MCNP6 background source

    DOE PAGESBeta

    McMath, Garrett E.; McKinney, Gregg W.

    2015-10-19

    The particle transport code MCNP has been used to produce a background radiation data file on a worldwide grid that can easily be sampled as a source in the code. Location-dependent cosmic showers were modeled by Monte Carlo methods to produce the resulting neutron and photon background flux at 2054 locations around Earth. An improved galactic-cosmic-ray feature was used to model the source term as well as data from multiple sources to model the transport environment through atmosphere, soil, and seawater. A new elevation scaling feature was also added to the code to increase the accuracy of the cosmic neutronmore » background for user locations with off-grid elevations. Furthermore, benchmarking has shown the neutron integral flux values to be within experimental error.« less

  18. Enhancements to the MCNP6 background source

    SciTech Connect

    McMath, Garrett E.; McKinney, Gregg W.

    2015-10-19

    The particle transport code MCNP has been used to produce a background radiation data file on a worldwide grid that can easily be sampled as a source in the code. Location-dependent cosmic showers were modeled by Monte Carlo methods to produce the resulting neutron and photon background flux at 2054 locations around Earth. An improved galactic-cosmic-ray feature was used to model the source term as well as data from multiple sources to model the transport environment through atmosphere, soil, and seawater. A new elevation scaling feature was also added to the code to increase the accuracy of the cosmic neutron background for user locations with off-grid elevations. Furthermore, benchmarking has shown the neutron integral flux values to be within experimental error.

  19. MCNP modelling of the PBMR equilibrium core

    SciTech Connect

    Albornoz, F.; Korochinsky, S.

    2006-07-01

    A complete MCNP model of the PBMR equilibrium core is presented, which accounts for the same fuel regions defined in the PBMR core management code, as well as for complete fuel and reflector temperature distributions. This comprehensive 3D model is the means to calculate and characterize the neutron and photon boundary sources of the equilibrium core, and is also used to support some specific core neutronic studies needing detailed geometry modelling. Due to the geometrical modelling approach followed, an unrealistic partial cutting of fuel kernels and pebbles is introduced in the model. The variations introduced by this partial cutting both on the packing fraction and on the uranium load of the modelled core and its corresponding effect on core reactivity and flux levels, have been investigated and quantified. A complete set of high-temperature cross-section data was applied to the calculation of the PBMR equilibrium core, and its effect on the calculated core reactivity is also reported. (authors)

  20. SABRINA - An interactive geometry modeler for MCNP (Monte Carlo Neutron Photon)

    SciTech Connect

    West, J.T.; Murphy, J.

    1988-01-01

    SABRINA is an interactive three-dimensional geometry modeler developed to produce complicated models for the Los Alamos Monte Carlo Neutron Photon program MCNP. SABRINA produces line drawings and color-shaded drawings for a wide variety of interactive graphics terminals. It is used as a geometry preprocessor in model development and as a Monte Carlo particle-track postprocessor in the visualization of complicated particle transport problem. SABRINA is written in Fortran 77 and is based on the Los Alamos Common Graphics System, CGS. 5 refs., 2 figs.

  1. Sir William Wilde: an enlightened editor.

    PubMed

    O'Doherty, M

    2016-05-01

    This paper examines Sir William Wilde's peculiar genius as editor, his contribution to the Irish Journal of Medical Science in ensuring its endurance and making it a treasure-house of the history of medicine in Ireland. PMID:26969455

  2. Richard Gilbert, Reporter and Assistant City Editor.

    ERIC Educational Resources Information Center

    Bender, Larry

    1988-01-01

    Looks at the experiences of Richard Gilbert, reporter and assistant editor for "The Herald Telephone," a daily newspaper in Bloomington, Indiana, and discusses Gilbert's suggested guidelines for high school journalism advisers. (MS)

  3. MCNP (trademark) ENDF/B-VI iron benchmark calculations

    NASA Astrophysics Data System (ADS)

    Court, J. D.; Hendricks, J. S.

    Four iron shielding benchmarks have been calculated for, we believe the first time, with MCNP4A and its new ENDF/B-VI library. These calculations are part of the Hiroshima/Nagasaki dose re-evaluation for the National Academy of Sciences and the Defense Nuclear Agency. We believe these calculations are significant because they validate MCNP and the new ENDF/B-VI libraries. These calculations are compared to ENDF/B-V, experiment, and in some cases the recommended MCNP data library (a T-2 evaluation) and ENDF/IV.

  4. Computational radiology and imaging with the MCNP Monte Carlo code

    SciTech Connect

    Estes, G.P.; Taylor, W.M.

    1995-05-01

    MCNP, a 3D coupled neutron/photon/electron Monte Carlo radiation transport code, is currently used in medical applications such as cancer radiation treatment planning, interpretation of diagnostic radiation images, and treatment beam optimization. This paper will discuss MCNP`s current uses and capabilities, as well as envisioned improvements that would further enhance MCNP role in computational medicine. It will be demonstrated that the methodology exists to simulate medical images (e.g. SPECT). Techniques will be discussed that would enable the construction of 3D computational geometry models of individual patients for use in patient-specific studies that would improve the quality of care for patients.

  5. 2012 Editors' Citations for Excellence in Refereeing

    NASA Astrophysics Data System (ADS)

    2013-09-01

    One of the most important services performed for AGU is the conscientious reviewing of submitted papers. Because of the nature of the reviewing process, this service is also one of the least recognized. Every year editors are asked to select the outstanding reviewers from the previous year. The reviewers listed below have been cited by editors of AGU journals and Eos for excellence in refereeing. These individuals are to be commended for consistently providing constructive and thoughtful reviews.

  6. 2013 Editors' Citations for Excellence in Refereeing

    NASA Astrophysics Data System (ADS)

    2014-06-01

    One of the most important services performed for AGU is the conscientious reviewing of submitted papers. Because of the nature of the reviewing process, this service is also one of the least recognized. Every year editors are asked to select the outstanding reviewers from the previous year. The reviewers listed below have been cited by editors of AGU journals and Eos for excellence in refereeing. These individuals are to be commended for consistently providing constructive and thoughtful reviews.

  7. EDITORIAL: Message from the Editor Message from the Editor

    NASA Astrophysics Data System (ADS)

    Thomas, Paul

    2012-01-01

    Board Members, Guest Editors of special editions and those referees who were already listed in the last years. The following people have been selected: Marina Becoulet, CEA Cadarache, France Russell Doerner, University of California - San Diego, USA Emiliano Fable, Max-Planck-Institut fuer Plasmaphysik, Germany Akihide Fujisawa, Kyushi University, Japan Gerardo Giruzzi, CEA Cadarache, France Grigory Kagan, LANL, USA Morten Lennholm, CCFE, UK Akinobu Matsuyama, NIFS, Japan Peter Stangeby, University of Toronto, Canada Leonid Zakharov, PPPL, USA In addition, there is a group of several hundred referees who have helped us in the past year to maintain the high scientific standard of Nuclear Fusion. At the end of this issue we give the full list of all referees for 2011. Our thanks to them! Authors The winner of the 2011 Nuclear Fusion Award is H. Urano, for the paper 'Dimensionless parameter dependence of H-mode pedestal width using hydrogen and deuterium plasmas in JT-60U' (Nucl. Fusion 48 045008). The award was presented at the Plasma Conference 2011 (Joint meeting of 28th JSPF Annual Meeting, The 29th Symposium on Plasma Processing, and Division of Plasma Physics, 2011 Autumn Meeting of The Physical Society of Japan). This is the sixth year that the International Atomic Energy Agency (IAEA) has awarded an annual prize to honour exceptional work published in Nuclear Fusion. IOP Publishing has generously made a contribution of $2500 to the award. The Nuclear Fusion Electronic Archive The journal's electronic archive has been online since the beginning of the year. The archive has been a roaring success and has contributed to the nearly 300 000 downloads of journal papers in 2011. The archive can be accessed via http://iopscience.iop.org/0029-5515/page/Archive. It has direct links to 16 landmark papers, from authors such as Artsimovich and Mercier. The Nuclear Fusion office and IOP Publishing Just as the journal depends on the authors and referees, so its success is also

  8. MCNP-model for the OAEP Thai Research Reactor

    SciTech Connect

    Gallmeier, F.X.; Tang, J.S.; Primm, R.T. III

    1998-06-01

    An MCNP input was prepared for the Thai Research Reactor, making extensive use of the MCNP geometry`s lattice feature that allows a flexible and easy rearrangement of the core components and the adjustment of the control elements. The geometry was checked for overdefined or undefined zones by two-dimensional plots of cuts through the core configuration with the MCNP geometry plotting capabilities, and by a three-dimensional view of the core configuration with the SABRINA code. Cross sections were defined for a hypothetical core of 67 standard fuel elements and 38 low-enriched uranium fuel elements--all filled with fresh fuel. Three test calculations were performed with the MCNP4B-code to obtain the multiplication factor for the cases with control elements fully inserted, fully withdrawn, and at a working position.

  9. Report of the editors, 2014.

    PubMed

    García Puig, J; Gaspar Alonso-Vega, G; Ríos Blanco, J J

    2015-01-01

    The editors of Revista Clínica Española(Rev Clin Esp) inform on their editorial activity during the last 12 months: (a) Objectives and attainments in 2014, (b) Editorial activity, 2014, and (c) 2013 impact factor. In 2014 we achieved the 5 planned objectives. We have published the 9 programmed issues and 103% of the planned papers according to the usual fixed sections. We emphasize the publication of 29 editorials, 21 of which are signed by prestigious foreign authors. From the first January to the 30th September 2014 we received 421 manuscripts (46.8 manuscripts per month), a slight lower figure to that obtained in 2013 (50.9 manuscripts per month). The acceptance rate of the 404 manuscripts whose editorial process has been concluded was 32.3% (originals, 22.4%). We asked for 315 revisions to 240 reviewers and we received 53.3% revisions in less than two weeks (10.4 days). The mean time to adopt an editorial decision for all manuscripts («accepted»/«rejected») has been 18,3 (less than half than in 2009). For «originals» this figure has dropped from 56,6 days in 2009 to 26.6 days in 2014. The mean time elapsed from manuscript reception to its on-line publication was 103 days. In 2014 the collaboration with the working groups from the Internal Medicine Spanish Foundation (FEMI) has reported 11 published manuscripts. In July 2014 we were informed that the Journal Citation Reports gave Rev Clin Esp an Impact Factor of 1,314 (year 2013). This Impact Factor without self-citations would have been 0.705 (in 2009 the global impact factor was 0,584). With the Editorial Committee farewell we welcome the new editorial team and we sincerely thank the SEMI Steering Committee, our colleagues, journal officers, reviewers, readers and authors that since 2009 have trusted on our editorial work. PMID:25441406

  10. [Report of the editors, 2013].

    PubMed

    García Puig, J; Gaspar Alonso-Vega, G; Ríos Blanco, J J

    2014-01-01

    The editors of Revista Clínica Española(Rev Clin Esp) inform on their editorial activity during the last 12 months: (a) objectives and attainments, (b) editorial activity, and (c) objectives for 2014. In 2013 the most relevant modification concerning the editorial activity has been the translation into English of the 5 manuscripts with abstract contained in each issue (http://www.revclinesp.es/). From the first January to the 30th September 2013 we received 458 manuscripts (50.9 manuscripts per month), a similar figure to that obtained in 2012 (51.1 manuscripts per month). The acceptance rate of the 443 manuscripts whose editorial process has been concluded was 23.7% (originals, 11.8%). We asked for 253 revisions to 186 reviewers and we received 74.4% revisions in less than 2 weeks (10.9 days). The mean time to adopt an editorial decision for all manuscripts («accepted»/«rejected») has been 20,3 (half than in 2009). For «originals» this figure has dropped from 56.6 days in 2009 to 22.5 days in 2013. The mean time elapsed from manuscript reception to its on-line publication was 94.8 days in 2013 (110.5 in 2012 and 155.8 in 2011). In 2013 the collaboration with the working groups from the Internal Medicine Spanish Foundation has reported 17 published manuscripts. In 2013 we were informed that the Journal Citation Reports excluded Rev Clin Esp from its impact factor journal list due to its elevated self-citations. We have taken a number of actions to reduce self-citations and we expect to be a minority in 2014. Some other data concerning the editorial policy are encouraging. In this sense, manuscript citation to Rev Clin Esp published articles has seen a substantial increase from 19% in 2008 to 29% in 2012. We work to achieve the digitalization of Rev Clin Esp from 1940 to 1999 (the journal is already digitalized since 2000). The continuous renewal of the journal sections and the working groups collaboration are necessary elements to make our journal, each day

  11. EDITORIAL: Letter from the Editor Letter from the Editor

    NASA Astrophysics Data System (ADS)

    Hauptmann, Peter

    2011-01-01

    Dear authors and reviewers of articles for Measurement Science and Technology, I would like to thank all those who have published papers with us in 2010, and special thanks go to those of you who have kindly reviewed articles for the journal. I would also like to take this opportunity to update you on some of the developments on the journal and look ahead to 2011. As many of you are no doubt aware, our impact factor (a measure of the average number of times recent papers are referred to by others) is currently 1.317. This is often taken as an indication of the quality and relevance of recently published research, and although as readers we develop our own instinct for journals of high quality, it is gratifying as an Editor to see the data from an independent organization (Thomson ISI) agreeing with my own assessment. Measurement Science and Technology is a journal with a broad scope covering new measurement techniques in all fields of science and engineering. I therefore find it particularly enjoyable to read summaries of recent research in our strong topical review programme as these cover many varied topics of interest. In 2010 several interesting articles by international leaders in their field were published, for example: Single-photon generation and detection, by G S Buller and R J Collins of Heriot-Watt University [1]. Fluorescence lifetime imaging microscopy in life sciences, by Jan Willem Borst and Antonie J W G Visser, from the Microspectroscopy Centre of Wageningen University [2]. Biological and chemical sensors for cancer diagnosis, by Elfriede Simon of Siemens AG [3]. I hope that these articles, and the others published in 2010 and now in 2011, will provide a useful overview for our readers, and be helpful to new researchers. When speaking to young researchers I am particularly aware that having their articles published in a timely fashion is important, and I am pleased that our publication times are highly competitive, with most authors receiving a

  12. Criticality calculations with MCNP{trademark}: A primer

    SciTech Connect

    Harmon, C.D. II; Busch, R.D.; Briesmeister, J.F.; Forster, R.A.

    1994-06-06

    With the closure of many experimental facilities, the nuclear criticality safety analyst increasingly is required to rely on computer calculations to identify safe limits for the handling and storage of fissile materials. However, in many cases, the analyst has little experience with the specific codes available at his/her facility. This primer will help you, the analyst, understand and use the MCNP Monte Carlo code for nuclear criticality safety analyses. It assumes that you have a college education in a technical field. There is no assumption of familiarity with Monte Carlo codes in general or with MCNP in particular. Appendix A gives an introduction to Monte Carlo techniques. The primer is designed to teach by example, with each example illustrating two or three features of MCNP that are useful in criticality analyses. Beginning with a Quickstart chapter, the primer gives an overview of the basic requirements for MCNP input and allows you to run a simple criticality problem with MCNP. This chapter is not designed to explain either the input or the MCNP options in detail; but rather it introduces basic concepts that are further explained in following chapters. Each chapter begins with a list of basic objectives that identify the goal of the chapter, and a list of the individual MCNP features that are covered in detail in the unique chapter example problems. It is expected that on completion of the primer you will be comfortable using MCNP in criticality calculations and will be capable of handling 80 to 90 percent of the situations that normally arise in a facility. The primer provides a set of basic input files that you can selectively modify to fit the particular problem at hand.

  13. AGU Publications Volunteers Feted At Elegant Editors' Evening

    NASA Astrophysics Data System (ADS)

    Panning, Jeanette

    2013-01-01

    The 2012 Fall Meeting Editors' Evening, held at the City Club of San Francisco, was hosted by the Publications Committee and is the premier social event for editors and associate editors attending the Fall Meeting. The evening commenced with a welcome from Carol Finn, incoming AGU president, in which she expressed her thanks to the editors and associate editors for volunteering their time to benefit AGU.

  14. Release of MCNP5_RSICC_1.30.

    SciTech Connect

    Goorley, T.; Bull, J. S.; Brown, F. B.; Booth, Thomas Edward; Hughes, H. G.; Mosteller, R. D.; Forster, R. A.; Post, S. E.; Prael, R. E.; Selcow, Elizabeth Carol,; Sood, A.; Sweezy, J. E.

    2004-01-01

    In July of 2004, an updated version of MCNP5{trademark} (MCNP5-RSICC-1.30) was released to the Radiation Shielding Information Computational Center. This updated version has three new features, thirteen bug fixes and several minor coding improvements. The new features are: support for 8 byte integers, specialized tally treatment of large lattices, and mesh tally enhancements. Of the thirteen bug fixes, only four resulted in incorrect answers in specific circumstances. In addition to the standard RSICC distribution of the MCNP5 source, executables and patches, the patch file (only) is available on the MCNP website: http://www-xdiv.lanl.gov/x5/MCNP/theresources.html. The three new MCNP5 features are discussed. Several new improvements have also been made to the manual and development environment. All of the features, bug fixes, coding improvement issues and related documentation are now maintained in Sourceforge. Fortran and C source code and regression test problems are now under version control with CVS.

  15. MCWO - Linking MCNP And ORIGEN2 For Fuel Burnup Analysis

    SciTech Connect

    Gray S Chang

    2005-04-01

    The UNIX BASH (Bourne Again Shell) script MCWO has been developed at the Idaho National Engineering and Environment Laboratory (INEEL) to couple the Monte Carlo transport code MCNP with the depletion and buildup code ORIGEN2. MCWO is a fully automated tool that links the Monte Carlo transport code MCNP with the radioactive decay and burnup code ORIGEN2. MCWO can handle a large number of fuel burnup and material loading specifications, Advanced Test Reactor (ATR) powers, and irradiation time intervals. The program processes input from the user that specifies the system geometry, initial material compositions, feed/removal specifications, and other code-specific parameters. Calculated results from MCNP, ORIGEN2, and data process module calculations are then output successively as the code runs. The principal function of MCWO is to transfer one-group cross-section and flux values from MCNP to ORIGEN2, and then transfer the resulting material compositions (after irradiation and/or decay) from ORIGEN2 back to MCNP in a repeated, cyclic fashion. The basic requirement of the code is that the user have a working MCNP input file and other input parameters; all interaction with ORIGEN2 and other calculations are performed by UNIX BASH script MCWO. This paper presents the MCWO-calculated results of the RERTR-1 and -2 , and the Weapons-Grade Mixed Oxiide fuel (Wg-MOX) fuel experiments in ATR and compares the MCWO-calculated results with the measured data.

  16. Spectral measurements in critical assemblies: MCNP specifications and calculated results

    SciTech Connect

    Stephanie C. Frankle; Judith F. Briesmeister

    1999-12-01

    Recently, a suite of 86 criticality benchmarks for the Monte Carlo N-Particle (MCNP) transport code was developed, and the results of testing the ENDF/B-V and ENDF/B-VI data (through Release 2) were published. In addition to the standard k{sub eff} measurements, other experimental measurements were performed on a number of these benchmark assemblies. In particular, the Cross Section Evaluation Working Group (CSEWG) specifications contain experimental data for neutron leakage and central-flux measurements, central-fission ratio measurements, and activation ratio measurements. Additionally, there exists another set of fission reaction-rate measurements performed at the National Institute of Standards and Technology (NIST) utilizing a {sup 252}Cf source. This report will describe the leakage and central-flux measurements and show a comparison of experimental data to MCNP simulations performed using the ENDF/B-V and B-VI (Release 2) data libraries. Central-fission and activation reaction-rate measurements will be described, and the comparison of experimental data to MCNP simulations using available data libraries for each reaction of interest will be presented. Finally, the NIST fission reaction-rate measurements will be described. A comparison of MCNP results published previously with the current MCNP simulations will be presented for the NIST measurements, and a comparison of the current MCNP simulations to the experimental measurements will be presented.

  17. Writer/editor and the computer

    SciTech Connect

    Smith, B.R.

    1985-04-01

    When the computer entered the publications process it created almost seismic shocks all along the line of creation from authoring to editing to composing to layout and to printing. Authors and editors of scientific and engineering documents felt the impact in adverse as well as beneficial ways. In the tradiational system, the writer/editor took from an author a manuscript and, using the powers of wordsmithing and the knowledge of the publications process, created a finished document using nothing more sophisticated than a red pencil for the mechanical process. Once the computer entered the scene, the writer/editor had to learn different hardware systems, try to keep up with the software explosion, and fight against a rising fear that a machine was going to take over. Fortunately, an innate flexibility and specialized knowledge of how to get a document into the best form for its specific audience guaranteed the writer/editor's survival, although there is still a long way to go in this transition phase from red pencil to VDT. This paper reviews the experiences of writer/editors in one scientific laboratory, experiences that typify challenges the forward-moving manager of a technical document production system can expect to encounter.

  18. EDITORIAL: Letter from the Editor

    NASA Astrophysics Data System (ADS)

    Hauptmann, Peter

    2008-01-01

    Dear authors and reviewers of articles for Measurement Science and Technology, I would like to thank all those who have published papers with us in 2007, and special thanks go to those of you who have kindly reviewed articles for the journal this year. I would also like to take this opportunity to update you on some of the developments on the journal. As many of you are no doubt aware, our latest impact factor (a measure of the average number of times recent papers are referred to by others) has risen to 1.228. This is often taken as an indication of the quality and relevance of recently published research, and although as readers we develop our own instinct for journals of high quality, it is gratifying as an Editor to see the data from an independent organization agreeing with my own assessment. The popularity of the journal amongst authors and readers has prompted us to introduce a new subject classification for articles, to make it easier for readers to find articles of interest. The eight subject categories are: Measurement theory and practical developments (e.g. precision measurements, metrology, new measurement principles, signal processing techniques, theory of measurement, calibration); Sensors and sensing systems (based on physical, chemical or biological principles; micro- and nano-scale systems; sensors for physical, chemical and biological quantities); Optical and laser based techniques (e.g. fibre optics, interferometry, etc); Fluid mechanics measurements (e.g. fluid flow, velocimetry, particle sizing, etc); Imaging techniques (e.g. tomography, microscopy, holography, THz, etc); Spectroscopy (e.g. optical, acoustic, dielectric, MS, NMR, ESR, IR, UV-VIS, fluorescence, PCS, x-ray, etc); New and improved techniques for materials evaluation (e.g. non-destructive testing and evaluation, structural measurements); Novel instrumentation. We kindly ask you to assign your paper to a category when you send it to the journal. In order to maintain our rapid

  19. EDITORIAL: Letter from the Editor

    NASA Astrophysics Data System (ADS)

    Hauptmann, Peter

    2009-01-01

    Marella de Angelis and her colleagues on precision gravimetry using atomic sensors and from Dr Peter Becker on determination of the Avogadro constant via enriched silicon-28. I recommend setting up a free e-mail alert so that you can read them as soon as they are published! As many of you are already aware, our impact factor (a measure of the average number of times recent papers are referred to by others) has risen again to 1.297. This is often taken as an indication of the quality and relevance of recently published research, and although as readers we develop our own instinct for journals of high quality, it is gratifying as an Editor to see the data from an independent organization (Thomson ISI) agreeing with my own assessment. Of course the publication of high quality articles in the journal is dependent both on you the authors who trust us with the publication of your best work and on our referees and Editorial Board Members who we depend on to maintain the high standards you have grown to expect. I must also thank our referees for their rapid response when asked to review papers for Measurement Science and Technology. On average, authors receive a decision on their article in 45 days. Therefore I would like to end this message by saying thank you again to all those who have contributed to our success in the past year, and wish you all the best for a successful 2009!

  20. Characterization of the NPOD3 Detectors in MCNP5 and MCNP6

    SciTech Connect

    Clark, Kimberly L.; Hutchinson, Jesson D.; Sood, Avneet

    2014-01-21

    Researchers performed a series of measurements in May 2012 to characterize the NPOD3 detector systems. The detectors were placed in varying states of disassembly to determine the effect of individual components on detection efficiency. A 4.5 kg α-phase Pu sphere known as the Los Alamos BeRP Ball was used as the SNM source in both a bare configuration and reflected by varying thicknesses of polyethylene. A set of simulations matching the experimental setups were run and the data were compared to the measured data. The total and leakage multiplication and the inferred k values were determined for both the simulations and the measurements. Table 3 shows a comparison of the results from MCNP6 and MCNP5 with the list-mode patch to the measured results. The count rates for the calculated results were obtained by dividing the total line count in the list-mode file (equivalent to the total number of absorptions in the NPOD detectors) by the total run time. The count rates are identical for both codes, and they both produce the same multiplicity and inferred k values regardless of measurement time as expected.

  1. Performance of scientific computing platforms running MCNP4B

    SciTech Connect

    McLaughlin, H.E.; Hendricks, J.S.

    1997-11-01

    A performance study has been made for the MCNP4B Monte Carlo radiation transport code on a wide variety of scientific computing platforms ranging from personal computers to Cray mainframes. We present the timing study results using MCNP4B and its new test set and libraries. This timing study is unlike other timing studies because of its widespread reproducibility, its direct comparability to the predecessor study in 1993, and its focus upon a nuclear engineering code. Our results, derived from using the new 29-problem test set for MCNP4B, (1) use a highly versatile and readily available physics code; (2) show that timing studies are very problem dependent; (3) present the results as raw data allowing comparisons of performance to other computing platforms not included in this study to those platforms that were included; (4) are reproducible; and (5) provide a measure of improvement in performance with the MCNP code due to advancements in software and hardware over the past 4 years. In the 1993 predecessor study using MCNP4A, the performances were based on a 25 problem test set. We present our data based on MCNP4B`s new 29 problem test set which cover 97% of all the FORTRAN physics code lines in MCNP4B. Like the previous study the new test problems and the test data library are available from the Radiation Shielding and Information Computational Center (RSICC) in Oak Ridge, Tennessee. Our results are reproducible because anyone with the same workstation, compiler, and operating system can duplicate the results presented here. The computing platforms included in this study are the Sun Sparc2, Sun Sparc5, Cray YMP 8/128, HP C180,SGI origin 2000, DBC 3000/600, DBC AiphaStation 500(300 MHz), IBM RS/6000-590, HP /9000-735, Micron Milienia Pro 200 MHz PC, and the Cray T94/128.

  2. Panel Discussion With PR/PRL Editors

    NASA Astrophysics Data System (ADS)

    Blume, Martin

    2002-03-01

    Panelists: Peter Adams, Physical Review B Irwin Oppenheim, Physical Review E & Massachsetts Institute of Technology Jack Sandweiss, Physical Review Letters & Yale University Reinhardt Schuhmann, Physical Review Letters The panel will include Editors from Physical Review Letters, Physical Review B, and Physical Review E. They will briefly discuss some current issues facing the journals, such as raising the standards for PRL acceptance and the role of electronic media attachments (e.g., movies) to journal articles. Opinions on these issues from the audience will be solicited. The Editors will also respond to questions and comments from the audience.

  3. EDITORIAL: Letter from the Editor

    NASA Astrophysics Data System (ADS)

    Hauptmann, Peter

    2006-12-01

    Dear authors and reviewers of articles for Measurement Science and Technology, I would like to thank all those who have published papers with us in 2006, and special thanks go to those of you who have kindly reviewed articles for the journal this year. I would also like to take this opportunity to update you on some of the developments on the journal this year. As many of you are no doubt aware our impact factor (a measure of the average number of times recent papers are referred to by others) has remained above 1 for the second year in a row. This is often taken as an indication of the quality and relevance of recently published research, and although as readers we develop our own instinct for journals of high quality, it is gratifying as an Editor to see the data from an independent organization agreeing with my own assessment. This year we have welcomed several new faces to our Editorial Board and International Advisory Board. We are delighted to welcome Professor Hirofumi Yamada of the University of Kyoto as a representative from Japan. From China we have been joined by Professor Xuzong Chen of Peking University and Professor Zhiyi Wei of Chinese Academy of Sciences, Beijing. Professor Ivan Marusic from University of Minnesota and Dr Paul Williams of the National Institute of Standards and Technology in Boulder have joined as North American representatives. As usual you will be able to submit your articles through them or direct to the Editorial Office in Bristol, UK. As part of our ongoing initiative to give our authors' work the highest visibility, all articles are freely available online for 30 days from the date of publication, allowing all researchers to read and view the latest research as soon as it is published, and this year there have been many interesting articles to read! As regular readers are aware, Measurement Science and Technology publishes special issues and features, which highlight an area of current interest. This year's topics included

  4. Verification of the MCNP (TM) Perturbation Correction Feature for Cross-Section Dependent Tallies

    SciTech Connect

    A. K. Hess; G. W. McKinney; J. S. Hendricks; L. L. Carter

    1998-10-01

    The Monte Carlo N-Particle Transport Code MCNP version 4B perturbation capability has been extended to cross-section dependent tallies and to the track-length estimate of Iqff in criticality problems. We present the complete theory of the MCNP perturbation capability including the correction to MCNP4B which enables cross-section dependent perturbation tallies. We also present the MCNP interface as an upgrade to the MCNP4B manual. Finally, we present test results demonstrating the validity of the perturbation capability in MCNP, particularly cross-section dependent problems.

  5. Standard Neutron, Photon, and Electron Data Libraries for MCNP4C.

    Energy Science and Technology Software Center (ESTSC)

    2004-02-16

    Version 03 US DOE 10CFR810 Jurisdiction. DLC-200/MCNPDATA is for use with Versions 4C and and 4C2 of the MCNP transport code. This data library provides a comprehensive set of cross sections for a wide range of radiation transport applications using the Monte Carlo code package CCC-700/MCNP4C. See Appendix G of the MCNP report LA-13709-M for information on the libraries and how to select specific nuclides for use in MCNP. Newer MCNP cross sections from LANLmore » are included in CCC-710/MCNP5.« less

  6. Criticality calculations with MCNP{sup TM}: A primer

    SciTech Connect

    Mendius, P.W.; Harmon, C.D. II; Busch, R.D.; Briesmeister, J.F.; Forster, R.A.

    1994-08-01

    The purpose of this Primer is to assist the nuclear criticality safety analyst to perform computer calculations using the Monte Carlo code MCNP. Because of the closure of many experimental facilities, reliance on computer simulation is increasing. Often the analyst has little experience with specific codes available at his/her facility. This Primer helps the analyst understand and use the MCNP Monte Carlo code for nuclear criticality analyses. It assumes no knowledge of or particular experience with Monte Carlo codes in general or with MCNP in particular. The document begins with a Quickstart chapter that introduces the basic concepts of using MCNP. The following chapters expand on those ideas, presenting a range of problems from simple cylinders to 3-dimensional lattices for calculating keff confidence intervals. Input files and results for all problems are included. The Primer can be used alone, but its best use is in conjunction with the MCNP4A manual. After completing the Primer, a criticality analyst should be capable of performing and understanding a majority of the calculations that will arise in the field of nuclear criticality safety.

  7. Depletion analysis of the UMLRR reactor core using MCNP6

    NASA Astrophysics Data System (ADS)

    Odera, Dim Udochukwu

    Accurate knowledge of the neutron flux and temporal nuclide inventory in reactor physics calculations is necessary for a variety of application in nuclear engineering such as criticality safety, safeguards, and spent fuel storage. The Monte Carlo N- Particle (MCNP6) code with integrated buildup depletion code (CINDER90) provides a high-fidelity tool that can be used to perform 3D, full core simulation to evaluate fissile material utilization, and nuclide inventory calculations as a function of burnup. The University of Massachusetts Lowell Research Reactor (UMLRR) reactor has been modeled with the deterministic based code, VENTURE and with an older version of MCNP (MCNP5). The MIT developed MCODE (MCNP ORIGEN DEPLETION CODE) was used previously to perform some limited depletion calculations. This work chronicles the use of MCNP6, released in June 2013, to perform coupled neutronics and depletion calculation. The results are compared to previously benchmarked results. Furthermore, the code is used to determine the ratio of fission products 134Cs and 137Cs (burnup indicators), and the resultant ratio is compared to the burnup of the UMLRR.

  8. PWR Facility Dose Modeling Using MCNP5 and the CADIS/ADVANTG Variance-Reduction Methodology

    SciTech Connect

    Blakeman, Edward D; Peplow, Douglas E.; Wagner, John C; Murphy, Brian D; Mueller, Don

    2007-09-01

    The feasibility of modeling a pressurized-water-reactor (PWR) facility and calculating dose rates at all locations within the containment and adjoining structures using MCNP5 with mesh tallies is presented. Calculations of dose rates resulting from neutron and photon sources from the reactor (operating and shut down for various periods) and the spent fuel pool, as well as for the photon source from the primary coolant loop, were all of interest. Identification of the PWR facility, development of the MCNP-based model and automation of the run process, calculation of the various sources, and development of methods for visually examining mesh tally files and extracting dose rates were all a significant part of the project. Advanced variance reduction, which was required because of the size of the model and the large amount of shielding, was performed via the CADIS/ADVANTG approach. This methodology uses an automatically generated three-dimensional discrete ordinates model to calculate adjoint fluxes from which MCNP weight windows and source bias parameters are generated. Investigative calculations were performed using a simple block model and a simplified full-scale model of the PWR containment, in which the adjoint source was placed in various regions. In general, it was shown that placement of the adjoint source on the periphery of the model provided adequate results for regions reasonably close to the source (e.g., within the containment structure for the reactor source). A modification to the CADIS/ADVANTG methodology was also studied in which a global adjoint source is weighted by the reciprocal of the dose response calculated by an earlier forward discrete ordinates calculation. This method showed improved results over those using the standard CADIS/ADVANTG approach, and its further investigation is recommended for future efforts.

  9. Open Simulation Laboratories [Guest editors' introduction

    DOE PAGESBeta

    Alexander, Francis J.; Meneveau, Charles

    2015-09-01

    The introduction for the special issue on open simulation laboratories, the guest editors describe how OSLs will become more common as their potential is better understood and they begin providing access to valuable datasets to much larger segments of the scientific community. Moreover, new analysis tools and ways to do science will inevitably develop as a result.

  10. Are Editors Out of the Tenure Process?

    ERIC Educational Resources Information Center

    Howard, Jennifer

    2007-01-01

    University presses have complained for years that tenure committees unfairly expect their editors to be arbiters of what counts as tenure-worthy work. At the same time, the presses have been caught in a business-side squeeze between dwindling sales (and shrinking subsidies) and the ever-greater pressure on scholars to publish. In this article, the…

  11. Women's Page Editors: Self-Perceived Status.

    ERIC Educational Resources Information Center

    Chang, Won; And Others

    The focal points of this study are the role perceptions and the environments of women's page editors from daily and weekly newspapers across the United States. In the role perception areas, equal rights, discrimination, and the role of women in journalism are examined. Salaries, education, college major and minor, and years in the profession are…

  12. Editors' Ability and Willingness to Work Effectively.

    ERIC Educational Resources Information Center

    Dodd, Julie

    1978-01-01

    Suggests that student editors know their jobs, set a good example for the staff, have regular staff meetings, make assignments clear, not "hog" good assignments, be available to the staff, help the staff learn to rewrite, attend all staff or editorial board meetings, and accept decisions of the board. (TJ)

  13. 2009 Editors' Citations for Excellence in Refereeing

    NASA Astrophysics Data System (ADS)

    2010-09-01

    The reviewers listed on these pages have been cited by editors of AGU journals for excellence in refereeing. The editors’ citations recognize this special service to the Union. These individuals (photographs provided as available) are commended for consistently providing constructive and thoughtful reviews.

  14. Recent Developments in the MCNP-POLIMI Postprocessing Code

    SciTech Connect

    Pozzi, S.A.

    2004-12-17

    The design and analysis of measurements performed with organic scintillators rely on the use of Monte Carlo codes to simulate the interaction of neutrons and photons, originating from fission and other reactions, with the materials present in the system and the radiation detectors. MCNP-PoliMi is a modification of the MCNP-4c code that models the physics of secondary particle emission from fission and other processes realistically. This characteristic allows for the simulation of the higher moments of the distribution of the number of neutrons and photons in a multiplying system. The present report describes the recent additions to the MCNP-PoliMi post-processing code. These include the simulation of detector dead time, multiplicity, and third order statistics.

  15. MCNP load balancing and fault tolerance with PVM

    SciTech Connect

    McKinney, G.W.

    1995-07-01

    Version 4A of the Monte Carlo neutron, photon, and electron transport code MCNP, developed by LANL (Los Alamos National Laboratory), supports distributed-memory multiprocessing through the software package PVM (Parallel Virtual Machine, version 3.1.4). Using PVM for interprocessor communication, MCNP can simultaneously execute a single problem on a cluster of UNIX-based workstations. This capability provided system efficiencies that exceeded 80% on dedicated workstation clusters, however, on heterogeneous or multiuser systems, the performance was limited by the slowest processor (i.e., equal work was assigned to each processor). The next public release of MCNP will provide multiprocessing enhancements that include load balancing and fault tolerance which are shown to dramatically increase multiuser system efficiency and reliability.

  16. Features of MCNP6 Relevant to Medical Radiation Physics

    SciTech Connect

    Hughes, H. Grady III; Goorley, John T.

    2012-08-29

    MCNP (Monte Carlo N-Particle) is a general-purpose Monte Carlo code for simulating the transport of neutrons, photons, electrons, positrons, and more recently other fundamental particles and heavy ions. Over many years MCNP has found a wide range of applications in many different fields, including medical radiation physics. In this presentation we will describe and illustrate a number of significant recently-developed features in the current version of the code, MCNP6, having particular utility for medical physics. Among these are major extensions of the ability to simulate large, complex geometries, improvement in memory requirements and speed for large lattices, introduction of mesh-based isotopic reaction tallies, advances in radiography simulation, expanded variance-reduction capabilities, especially for pulse-height tallies, and a large number of enhancements in photon/electron transport.

  17. MCNP Analysis of a Phoswich Detector

    SciTech Connect

    Nathan Childress; William H. Miller

    2002-06-12

    A series of triple crystal phosphor sandwich detectors have been developed and constructed for testing at the University of Missouri-Columbia [1-7]. These detectors can simultaneously measure alpha, beta, and gamma radiation and utilize digital pulse shape discrimination to identify and separate radiation events coming from each of the separate phosphors. The research reported here uses Monte Carlo [8] software analysis to determine operating parameters for this detector system and optimizes its design for measuring trace amounts of alpha, beta and gamma-ray activity in effluent streams from nuclear waste cleanup processes. The previously designed, fabricated and tested phoswich detector [5] consisted of three scintillators placed on top of each other with a common diameter of 5.08 cm and viewed with a single photomultiplier tube. The scintillators (ZnS-0.00376 cm, CaF{sub 2}-0.254 cm and NaI-2.54 cm) interact preferentially with alpha, beta and gamma-ray radiation, respectively. This design allows preferential, but not exclusive, interaction of various radiations with specific layers. Taking into account and correcting for events that can occur in the ''wrong'' phosphor, this system was experimentally shown to have a 99% accuracy for properly identifying radiation coming from a mixed alpha/beta/gamma-ray source. In an attempt to better understand this system and provide design guidance for a detector system to be used in monitoring effluents from nuclear waste treatment facilities, this detector was modeled using MCNP [8]. This analysis [9] indicated that the thin ZnS layer adequately stops alpha particle energy, but greatly reduces beta detection efficiency to essentially zero at beta E{sub max} energies below 300 keV. The CaF{sub 2} layer, designed to keep any beta particle energy from entering the NaI detector results in an incorrect gamma-ray response that is approximately 23% of the NaI's response and is variable with energy. High energy beta events in the Ca

  18. MCNP speed advances for boron neutron capture therapy

    SciTech Connect

    Goorley, J.T.; McKinney, G.; Adams, K.; Estes, G.

    1998-04-01

    The Boron Neutron Capture Therapy (BNCT) treatment planning process of the Beth Israel Deaconess Medical Center-M.I.T team relies on MCNP to determine dose rates in the subject`s head for various beam orientations. In this time consuming computational process, four or five potential beams are investigated. Of these, one or two final beams are selected and thoroughly evaluated. Recent advances greatly decreased the time needed to do these MCNP calculations. Two modifications to the new MCNP4B source code, lattice tally and tracking enhancements, reduced the wall-clock run times of a typical one million source neutrons run to one hour twenty five minutes on a 200 MHz Pentium Pro computer running Linux and using the GNU FORTRAN compiler. Previously these jobs used a special version of MCNP4AB created by Everett Redmond, which completed in two hours two minutes. In addition to this 30% speedup, the MCNP4B version was adapted for use with Parallel Virtual Machine (PVM) on personal computers running the Linux operating system. MCNP, using PVM, can be run on multiple computers simultaneously, offering a factor of speedup roughly the same as the number of computers used. With two 200 MHz Pentium Pro machines, the run time was reduced to forty five minutes, a 1.9 factor of improvement over the single Linux computer. While the time of a single run was greatly reduced, the advantages associated with PVM derive from using computational power not already used. Four possible beams, currently requiring four separate runs, could be run faster when each is individually run on a single machine under Windows NT, rather than using Linux and PVM to run one after another with each multiprocessed across four computers. It would be advantageous, however, to use PVM to distribute the final two beam orientations over four computers.

  19. OPM Scheme Editor 2: A graphical editor for specifying object-protocol structures

    SciTech Connect

    Chen, I-Min A.; Markowitz, V.M.; Pang, F.; Ben-Shachar, O.

    1993-07-01

    This document describes an X-window based Schema Editor for the Object-Protocol Model (OPM). OPM is a data model that supports the specification of complex object and protocol classes. objects and protocols are qualified in OPM by attributes that are defined over (associated with) value classes. Connections of object and protocol classes are expressed in OPM via attributes. OPM supports the specification (expansion) of protocols in terms of alternative and sequences of component (sub) protocols. The OPM Schema Editor allows specifying, displaying, modifying, and browsing through OPM schemas. The OPM Schema Editor generates an output file that can be used as input to an OPM schema translation tool that maps OPM schemas into definitions for relational database management systems. The OPM Schema Editor was implemented using C++ and the X11 based Motif toolkit, on Sun SPARCstation under Sun Unix OS 4.1. This document consists of the following parts: (1) A tutorial consisting of seven introductory lessons for the OPM Schema Editor. (2) A reference manual describing all the windows and functions of the OPM Schema Editor. (3) An appendix with an overview of OPM.

  20. Cold neutron gain calculations for the NBSR using MCNP

    SciTech Connect

    Williams, R.E.; Rowe, J.M. ); Blau, M. )

    1993-01-01

    The existing D[sub 2]O-ice cold neutron source in the 20-MW National Bureau of Standards reactor (NBSR) will be replaced in 1994 with a liquid-hydrogen (LH2) source, to increase the yield of cold neutrons (X > 0.4 nm). Two series of Monte Carlo calculations using MCNP were performed to determine the optimum cold moderator geometry and to verify its performance. Only the region near the cryostat was modeled for the first series of calculations, leading to the choice of a spherical annulus for the LH[sub 2] source. A complete MCNP model of the core was subsequently developed.

  1. Calculation of cell volumes and surface areas in MCNP

    SciTech Connect

    Hendricks, J.S.

    1980-01-01

    MCNP is a general Monte Carlo neutron-photon particle transport code which treats an arbitrary three-dimensional configuration of materials in geometric cells bounded by first- and second-degree surfaces, and some special fourth-degree surfaces. It is necessary to calculate cell volumes and surface areas so that cell masses, fluxes, and other important information can be determined. The volume/area calculation in MCNP computes cell volumes and surface areas for cells and surfaces rotationally symmetric about any arbitrary axis. 5 figures, 1 table.

  2. Reactor physics verification of the MCNP6 unstructured mesh capability

    SciTech Connect

    Burke, T. P.; Kiedrowski, B. C.; Martz, R. L.; Martin, W. R.

    2013-07-01

    The Monte Carlo software package MCNP6 has the ability to transport particles on unstructured meshes generated from the Computed-Aided Engineering software Abaqus. Verification is performed using benchmarks with features relevant to reactor physics - Big Ten and the C5G7 computational benchmark. Various meshing strategies are tested and results are compared to reference solutions. Computational performance results are also given. The conclusions show MCNP6 is capable of producing accurate calculations for reactor physics geometries and the computational requirements for small lattice benchmarks are reasonable on modern computing platforms. (authors)

  3. Accelerating Pseudo-Random Number Generator for MCNP on GPU

    NASA Astrophysics Data System (ADS)

    Gong, Chunye; Liu, Jie; Chi, Lihua; Hu, Qingfeng; Deng, Li; Gong, Zhenghu

    2010-09-01

    Pseudo-random number generators (PRNG) are intensively used in many stochastic algorithms in particle simulations, artificial neural networks and other scientific computation. The PRNG in Monte Carlo N-Particle Transport Code (MCNP) requires long period, high quality, flexible jump and fast enough. In this paper, we implement such a PRNG for MCNP on NVIDIA's GTX200 Graphics Processor Units (GPU) using CUDA programming model. Results shows that 3.80 to 8.10 times speedup are achieved compared with 4 to 6 cores CPUs and more than 679.18 million double precision random numbers can be generated per second on GPU.

  4. An Electron/Photon/Relaxation Data Library for MCNP6

    SciTech Connect

    Hughes, III, H. Grady

    2015-08-07

    The capabilities of the MCNP6 Monte Carlo code in simulation of electron transport, photon transport, and atomic relaxation have recently been significantly expanded. The enhancements include not only the extension of existing data and methods to lower energies, but also the introduction of new categories of data and methods. Support of these new capabilities has required major additions to and redesign of the associated data tables. In this paper we present the first complete documentation of the contents and format of the new electron-photon-relaxation data library now available with the initial production release of MCNP6.

  5. From the Board of Editors: on Plagiarism

    NASA Astrophysics Data System (ADS)

    2005-04-01

    From the Board of Editors: on Plagiarism

    Dear Colleagues: There has been a significant increase in the number of duplicate submissions and plagiarism cases reported in all major journals, including the journals of the Optical Society of America. Duplicate submissions and plagiarism can take many forms, and all of them are violations of professional ethics, the copyright agreement that an author signs along with the submission of a paper, and OSA's published Author Guidelines. There must be a significant component of new science for a paper to be publishable. The copying of large segments of text from previously published or in-press papers with only minor cosmetic changes is not acceptable and can lead to the rejection of papers. Duplicate submission: Duplicate submission is the most common ethics violation encountered. Duplicate submission is the submission of substantially similar papers to more than one journal. There is a misperception in a small fraction of the scientific community that duplicate submission is acceptable because it sometimes takes a long time to get a paper reviewed and because one of the papers can be withdrawn at any time. This is a clear violation of professional ethics and of the copyright agreement that is signed on submission. Duplicate submission harms the whole community because editors and reviewers waste their time and in the process compound the time it takes to get a paper reviewed for all authors. In cases of duplicate submission, the Editor of the affected OSA journal will consult with the Editor of the other journal involved to determine the proper course of action. Often that action will be the rejection of both papers. Plagiarism: Plagiarism is a serious breach of ethics and is defined as the substantial replication, without attribution, of significant elements of another document already published by the same or other authors. Two types of plagiarism can occur

  6. Editor and Student Views on the Censorship Game.

    ERIC Educational Resources Information Center

    Raburn, Josephine

    Out of 200 newspaper editors randomly selected from a directory, 64 responded to a questionnaire eliciting their opinions on the subject materials most often censored by groups in the United States. The editors' responses were compared to those of 121 freshmen at Cameron University (Oklahoma). A majority of the editors supported the First…

  7. Science, Politics, and Peer Review: An Editor's Dilemma.

    ERIC Educational Resources Information Center

    McCarty, Richard

    2002-01-01

    Describes the controversy that arose over an editor's decision to overrule an ad hoc action editor's acceptance of a journal article and request for additional changes to the manuscript. This controversy played out in various Internet discussion groups. Presents the editor's perspective, highlighting the need to protect the integrity and…

  8. Monte Carlo N–Particle Transport Code System Including MCNP6.1.1BETA, MCNP6.1, MCNP5-1.60, MCNPX-2.7.0 and Data Libraries.

    Energy Science and Technology Software Center (ESTSC)

    2014-09-01

    Version 01 MCNP6™ is a general-purpose, continuous-energy, generalized-geometry, time-dependent, Monte Carlo radiation-transport code designed to track many particle types over broad ranges of energies. This MCNP6.1.1Beta is a follow-on to the MCNP6.1 production version which itself was the culmination of a multi-year effort to merge the MCNP5™ [X-503] and MCNPX™ [PEL11] codes into a single product. This MCNP6.1.1 beta has been released in order to provide the radiation transport community with the latest feature developmentsmore » and bug fixes in the code. MCNP6.1.1 has taken input from a group of people, residing in the Los Alamos National Laboratory's (LANL) X Computational Physics Division, Radiation Transport Group (XCP-3), and Nuclear Engineering and Nonproliferation Division, Systems Design and Analysis Group (NEN-5). They have combined their code development efforts to produce this next evolution of MCNP. For those familiar with previous versions of MCNP, you will discover the code has been expanded to handle a multitude of particles and to include model physics options for energies above the cross-section table range, a material burnup feature, and delayed particle production. Expanded and/or new tally, source, and variance-reduction options are available to the user as well as an improved plotting capability. The capability to calculate keff eigenvalues for fissile systems remains a standard feature. Although MCNP6 is simply and accurately described as the merger of MCNP5 and MCNPX capabilities, the result is much more than the sum of these two computer codes. MCNP6 is the result of five years of effort by the MCNP5 and MCNPX code development teams.« less

  9. Monte Carlo N–Particle Transport Code System Including MCNP6.1.1BETA, MCNP6.1, MCNP5-1.60, MCNPX-2.7.0 and Data Libraries.

    SciTech Connect

    2014-09-01

    Version 01 MCNP6™ is a general-purpose, continuous-energy, generalized-geometry, time-dependent, Monte Carlo radiation-transport code designed to track many particle types over broad ranges of energies. This MCNP6.1.1Beta is a follow-on to the MCNP6.1 production version which itself was the culmination of a multi-year effort to merge the MCNP5™ [X-503] and MCNPX™ [PEL11] codes into a single product. This MCNP6.1.1 beta has been released in order to provide the radiation transport community with the latest feature developments and bug fixes in the code. MCNP6.1.1 has taken input from a group of people, residing in the Los Alamos National Laboratory's (LANL) X Computational Physics Division, Radiation Transport Group (XCP-3), and Nuclear Engineering and Nonproliferation Division, Systems Design and Analysis Group (NEN-5). They have combined their code development efforts to produce this next evolution of MCNP. For those familiar with previous versions of MCNP, you will discover the code has been expanded to handle a multitude of particles and to include model physics options for energies above the cross-section table range, a material burnup feature, and delayed particle production. Expanded and/or new tally, source, and variance-reduction options are available to the user as well as an improved plotting capability. The capability to calculate keff eigenvalues for fissile systems remains a standard feature. Although MCNP6 is simply and accurately described as the merger of MCNP5 and MCNPX capabilities, the result is much more than the sum of these two computer codes. MCNP6 is the result of five years of effort by the MCNP5 and MCNPX code development teams.

  10. Impact of MCNP unresolved resonance probability-table treatment on uranium and plutonium benchmarks

    SciTech Connect

    Mosteller, R.D.; Little, R.C.

    1998-12-31

    Versions of MCNP up through and including 4B have not accurately modeled neutron self-shielding effects in the unresolved resonance energy region. Recently, a probability-table treatment has been incorporated into a developmental version of MCNP. This paper presents MCNP results for a variety of uranium and plutonium critical benchmarks, calculated with and without the probability-table treatment.

  11. Fission Matrix Capability for MCNP Monte Carlo

    SciTech Connect

    Carney, Sean E.; Brown, Forrest B.; Kiedrowski, Brian C.; Martin, William R.

    2012-09-05

    In a Monte Carlo criticality calculation, before the tallying of quantities can begin, a converged fission source (the fundamental eigenvector of the fission kernel) is required. Tallies of interest may include powers, absorption rates, leakage rates, or the multiplication factor (the fundamental eigenvalue of the fission kernel, k{sub eff}). Just as in the power iteration method of linear algebra, if the dominance ratio (the ratio of the first and zeroth eigenvalues) is high, many iterations of neutron history simulations are required to isolate the fundamental mode of the problem. Optically large systems have large dominance ratios, and systems containing poor neutron communication between regions are also slow to converge. The fission matrix method, implemented into MCNP[1], addresses these problems. When Monte Carlo random walk from a source is executed, the fission kernel is stochastically applied to the source. Random numbers are used for: distances to collision, reaction types, scattering physics, fission reactions, etc. This method is used because the fission kernel is a complex, 7-dimensional operator that is not explicitly known. Deterministic methods use approximations/discretization in energy, space, and direction to the kernel. Consequently, they are faster. Monte Carlo directly simulates the physics, which necessitates the use of random sampling. Because of this statistical noise, common convergence acceleration methods used in deterministic methods do not work. In the fission matrix method, we are using the random walk information not only to build the next-iteration fission source, but also a spatially-averaged fission kernel. Just like in deterministic methods, this involves approximation and discretization. The approximation is the tallying of the spatially-discretized fission kernel with an incorrect fission source. We address this by making the spatial mesh fine enough that this error is negligible. As a consequence of discretization we get a

  12. Millard coffin is appointed Eos Tectonophysics editor

    NASA Astrophysics Data System (ADS)

    Millard F. Coffin, of the University of Texas Institute for Geophysics (UTIG), has been named the Tectonophysics Editor of Eos for a term extending through 1998. He succeeds Louise Kellogg of the University of California-Davis.Recently, Coffin completed a term as associate editor for the solid Earth section of the Journal of Geophysical Research, and is looking forward to the move from a monthly to a weekly publication. His goal is are to serve the entire tectonophysics community, encompassing marine, terrestrial, and planetary research, through timely and frequent news items, a vigorous idea and results forum, and occasional review articles. He believes that the communication among field workers, experimentalists, and modelers afforded by Eos will benefit tectonophysicists strongly as well as effectively convey tectonophysics results to a broader audience.

  13. Evolutionary theory in letters to the editor.

    PubMed

    Silva, Eric Orion; Lowe, Clayton Cory

    2015-05-01

    This research note presents the results of a content analysis of 234 letters to the editors that discuss evolutionary theory and were published in American newspapers. We find that letters to the editor both support and hinder the cause of teaching evolutionary theory in American secondary schools. On the one hand, anti-evolutionary theory messages are marginalized in the letters section. This marginalization signals a low level of legitimacy for creationism. It might also contribute to the sense of tension that sustains creationist identities. On the other hand, relatively few letters explicitly note the fact that scientists or the scientific community accept evolution. Interestingly, the obscuration of the scientific community's support for evolutionary theory occurs both in letters supporting and opposing evolutionary theory. PMID:25540333

  14. From the Board of Editors: on Plagiarism

    NASA Astrophysics Data System (ADS)

    2005-05-01

    Dear Colleagues: There has been a significant increase in the number of duplicate submissions and plagiarism cases reported in all major journals, including the journals of the Optical Society of America. Duplicate submissions and plagiarism can take many forms, and all of them are violations of professional ethics, the copyright agreement that an author signs along with the submission of a paper, and OSA's published Author Guidelines. There must be a significant component of new science for a paper to be publishable. The copying of large segments of text from previously published or in-press papers with only minor cosmetic changes is not acceptable and can lead to the rejection of papers. Duplicate submission: Duplicate submission is the most common ethics violation encountered. Duplicate submission is the submission of substantially similar papers to more than one journal. There is a misperception in a small fraction of the scientific community that duplicate submission is acceptable because it sometimes takes a long time to get a paper reviewed and because one of the papers can be withdrawn at any time. This is a clear violation of professional ethics and of the copyright agreement that is signed on submission. Duplicate submission harms the whole community because editors and reviewers waste their time and in the process compound the time it takes to get a paper reviewed for all authors. In cases of duplicate submission, the Editor of the affected OSA journal will consult with the Editor of the other journal involved to determine the proper course of action. Often that action will be the rejection of both papers. Plagiarism: Plagiarism is a serious breach of ethics and is defined as the substantial replication, without attribution, of significant elements of another document already published by the same or other authors. Two types of plagiarism can occur-self-plagiarism and plagiarism from others' works. Self-plagiarism is the publication of substantially

  15. Four are named Editors of Earth Interactions

    NASA Astrophysics Data System (ADS)

    Eric J. Barron of the Earth System Science Center at The Pennsylvania State University has been named chief editor of the new electronic journal, Earth Interactions. This journal will be co-published by AGU, the American Meteorological Society, and the Association of American Geographers. The three societies jointly agreed on the appointment of Barron. Each of the societies also appointed an editor to the board. George F. Hepner for AAG is from the Department of Geography at the University of Utah, David T. Sandwell for AGU is at the Institute of Geophysics and Planetary Physics at Scripps Institution of Oceanography, and Kevin E. Trenberth for AMS is at the Climate and Global Dynamics Division at the National Center for Atmospheric Research.

  16. MCNP6. Simulating Correlated Data in Fission Events

    SciTech Connect

    Rising, Michael Evan; Sood, Avneet

    2015-12-03

    This report is a series of slides discussing the MCNP6 code and its status in simulating fission. Applications of interest include global security and nuclear nonproliferation, detection of special nuclear material (SNM), passive and active interrogation techniques, and coincident neutron and photon leakage.

  17. Certification of MCNP version 4A for WHC computer platforms

    SciTech Connect

    Carter, L.L., Westinghouse Hanford

    1996-05-07

    MCNP is a general-purpose Monte Carlo code that can be used for neutron, photon, or coupled neutron/photon transport, including the capability to calculate eigenvalues for critical systems. The code treats an arbitrary three-dimensional configuration of materials in geometric cells bounded by first- and second-degree surfaces, and some special fourth-degree surfaces (elliptical tori).

  18. Preliminary Benchmarking and MCNP Simulation Results for Homeland Security

    SciTech Connect

    Robert Hayes

    2008-03-01

    The purpose of this article is to create Monte Carlo N-Particle (MCNP) input stacks for benchmarked measurements sufficient for future perturbation studies and analysis. The approach was to utilize historical experimental measurements to recreate the empirical spectral results in MCNP, both qualitatively and quantitatively. Results demonstrate that perturbation analysis of benchmarked MCNP spectra can be used to obtain a better understanding of field measurement results which may be of national interest. If one or more spectral radiation measurements are made in the field and deemed of national interest, the potential source distribution, naturally occurring radioactive material shielding, and interstitial materials can only be estimated in many circumstances. The effects from these factors on the resultant spectral radiation measurements can be very confusing. If benchmarks exist which are sufficiently similar to the suspected configuration, these benchmarks can then be compared to the suspect measurements. Having these benchmarks with validated MCNP input stacks can substantially improve the predictive capability of experts supporting these efforts.

  19. MCNP6 enhancements of delayed-particle production

    SciTech Connect

    McKinney, G. W.

    2012-07-01

    Over the last decade, there has been an increased interest in the production of delayed-particle signatures from neutron and photon interactions with matter. To address this interest, various radiation transport codes have developed a wide range of delayed-particle physics packages. With the recent merger of the Monte Carlo transport codes MCNP5 and MCNPX, MCNP6 inherited the comprehensive model-based delayed-particle production capabilities developed in MCNPX over the last few years. An integral part of this capability consists of the depletion code CINDER90 which was incorporated into MCNPX in 2004. During this last year, significant improvements have been made to the MCNP6 physics and algorithms associated with delayed-particle production, including the development of a delayed-beta capability, an algorithm enhancement for the delayed-neutron treatment, and a database enhancement for delayed-gamma emission. The delayed-beta feature represents an important component in modeling background signals produced by active interrogation sources. Combined, these improvements provide MCNP6 with a flexible state-of-the-art physics package for generating high-fidelity signatures from fission and activation. This paper provides details of these enhancements and presents results for a variety of fission and activation examples. (authors)

  20. New “Editor's choice”: Online journals debut

    NASA Astrophysics Data System (ADS)

    Cole, Stephen

    With all AGU journal articles now published online in advance of the printed journal, AGU members have new options, in terms of how they access the latest research results. An innovative option for those with specific research interests that are covered in several journals is the " Editor's Choice" virtual journal. The first two "Editor's Choice" journals—Biogeosciences and Atmospheric Electricity— debuted in January and are, for a limited time, freely accessible to members on the AGU Web site.An "Editor's Choice" virtual journal is a collection of electronic articles recently published by AGU that have been specially selected for their relevance to a particular topic area. Everett Shock of Washington University St. Louis, is serving as the Collection Editor for "Editor's Choice: Biogeosciences." The "Editor's Choice: Atmospheric Electricity" Collection Editor is Richard E. Orville of Texas A&M University College Station, who is being assisted by advisors David Sentman, University of Alaska, and Vladimir Rakov, University of Florida.

  1. Implementation of on-the-fly doppler broadening in MCNP

    SciTech Connect

    Martin, W. R.; Wilderman, S.; Brown, F. B.; Yesilyurt, G.

    2013-07-01

    A new method to obtain Doppler broadened cross sections has been implemented into MCNP, removing the need to generate cross sections for isotopes at problem temperatures. When a neutron of energy E enters a material region that is at some temperature T, the cross sections for that material at temperature T are immediately obtained 'on-the-fly' (OTF) by interpolation using a high order functional expansion for the temperature dependence of the Doppler-broadened cross section for that isotope at the neutron energy E. The OTF cross sections agree with the NJOY-based cross sections for all neutron energies and all temperatures in the range specified by the user, e.g., 250 K - 3200 K. The OTF methodology has been successfully implemented into the MCNP Monte Carlo code and has been tested on several test problems by comparing MCNP with conventional ACE cross sections versus MCNP with OTF cross sections. The test problems include the Doppler defect reactivity benchmark suite and two full-core VHTR configurations, including one with multiphysics coupling using RELAP5-3D/ATHENA for the thermal-hydraulic analysis. The comparison has been excellent, verifying that the OTF libraries can be used in place of the conventional ACE libraries generated at problem temperatures. In addition, it has been found that the OTF methodology greatly reduces the complexity of the input for MCNP, resulting in an order of magnitude decrease in the number of input lines for full-core configurations. Finally, for full-core problems with multiphysics feedback, the memory required to store the cross section data is considerably reduced with OTF cross sections and the additional computational effort with OTF is modest, on the order of 10-15%. (authors)

  2. MCNP{sup TM} criticality primer and training experiences

    SciTech Connect

    Briesmeister, J.; Forster, R.A.; Busch, R.

    1995-09-01

    With the closure of many experimental facilities, the nuclear criticality safety analyst is increasingly required to rely on computer calculations to identify safe limits for the handling and storage of fissile materials. However, the analyst may have little experience with the specific codes available at his or her facility. Usually, the codes are quite complex, black boxes capable of analyzing numerous problems with a myriad of input options. Documentation for these codes is designed to cover all the possible configurations and types of analyses but does not give much detail on any particular type of analysis. For criticality calculations, the user of a code is primarily interested in the value of the effective multiplication factor for a system (k{sub eff}). Most codes will provide this, and truckloads of other information that may be less pertinent to criticality calculations. Based on discussions with code users in the nuclear criticality safety community, it was decided that a simple document discussing the ins and outs of criticality calculations with specific codes would be quite useful. The Transport Methods Group, XTM, at Los Alamos National Laboratory (LANL) decided to develop a primer for criticality calculations with their Monte Carlo code, MCNP. This was a joint task between LANL with a knowledge and understanding of the nuances and capabilities of MCNP and the University of New Mexico with a knowledge and understanding of nuclear criticality safety calculations and educating first time users of neutronics calculations. The initial problem was that the MCNP manual just contained too much information. Almost everything one needs to know about MCNP can be found in the manual; the problem is that there is more information than a user requires to do a simple k{sub eff} calculation. The basic concept of the primer was to distill the manual to create a document whose only focus was criticality calculations using MCNP.

  3. Possible Improvements to MCNP6 and its CEM/LAQGSM Event-Generators

    SciTech Connect

    Mashnik, Stepan Georgievich

    2015-08-04

    This report is intended to the MCNP6 developers and sponsors of MCNP6. It presents a set of suggested possible future improvements to MCNP6 and to its CEM03.03 and LAQGSM03.03 event-generators. A few suggested modifications of MCNP6 are quite simple, aimed at avoiding possible problems with running MCNP6 on various computers, i.e., these changes are not expected to change or improve any results, but should make the use of MCNP6 easier; such changes are expected to require limited man-power resources. On the other hand, several other suggested improvements require a serious further development of nuclear reaction models, are expected to improve significantly the predictive power of MCNP6 for a number of nuclear reactions; but, such developments require several years of work by real experts on nuclear reactions.

  4. From the Board of Editors: on Plagiarism

    NASA Astrophysics Data System (ADS)

    2005-04-01

    From the Board of Editors: on Plagiarism

    Dear Colleagues: There has been a significant increase in the number of duplicate submissions and plagiarism cases reported in all major journals, including the journals of the Optical Society of America. Duplicate submissions and plagiarism can take many forms, and all of them are violations of professional ethics, the copyright agreement that an author signs along with the submission of a paper, and OSA's published Author Guidelines. There must be a significant component of new science for a paper to be publishable. The copying of large segments of text from previously published or in-press papers with only minor cosmetic changes is not acceptable and can lead to the rejection of papers. Duplicate submission: Duplicate submission is the most common ethics violation encountered. Duplicate submission is the submission of substantially similar papers to more than one journal. There is a misperception in a small fraction of the scientific community that duplicate submission is acceptable because it sometimes takes a long time to get a paper reviewed and because one of the papers can be withdrawn at any time. This is a clear violation of professional ethics and of the copyright agreement that is signed on submission. Duplicate submission harms the whole community because editors and reviewers waste their time and in the process compound the time it takes to get a paper reviewed for all authors. In cases of duplicate submission, the Editor of the affected OSA journal will consult with the Editor of the other journal involved to determine the proper course of action. Often that action will be the rejection of both papers. Plagiarism: Plagiarism is a serious breach of ethics and is defined as the substantial replication, without attribution, of significant elements of another document already published by the same or other authors. Two types of plagiarism can occur

  5. MPS Editor - An Integrated Sequencing Environment

    NASA Technical Reports Server (NTRS)

    Streiffert, Barbara A.; O'Reilly, Taifun; Schrock, Mitchell; Catchen, Jaime

    2010-01-01

    In today's operations environment, the teams are smaller and need to be more efficient while still ensuring the safety and success of the mission. In addition, teams often begin working on a mission in its early development phases and continue on the team through actual operations. For these reasons the operations teams want to be presented with a software environment that integrates multiple needed software applications as well as providing them with context sensitive editing support for entering commands and sequences of commands. At Jet Propulsion Laboratory, the Multi-Mission Planning and Sequencing (MPS) Editor provided by the Multi-Mission Ground Systems and Services (MGSS) supports those operational needs.

  6. From the Board of Editors: on Plagiarism

    NASA Astrophysics Data System (ADS)

    2005-03-01

    Dear Colleagues: There has been a significant increase in the number of duplicate submissions and plagiarism cases reported in all major journals, including the journals of the Optical Society of America. Duplicate submissions and plagiarism can take many forms, and all of them are violations of professional ethics, the copyright agreement that an author signs along with the submission of a paper, and OSA's published Author Guidelines. There must be a significant component of new science for a paper to be publishable. The copying of large segments of text from previously published or in-press papers with only minor cosmetic changes is not acceptable and can lead to the rejection of papers. Duplicate submission is the most common ethics violation encountered. Duplicate submission is the submission of substantially similar papers to more than one journal. There is a misperception in a small fraction of the scientific community that duplicate submission is acceptable because it sometimes takes a long time to get a paper reviewed and because one of the papers can be withdrawn at any time. This is a clear violation of professional ethics and of the copyright agreement that is signed on submission. Duplicate submission harms the whole community because editors and reviewers waste their time and in the process compound the time it takes to get a paper reviewed for all authors. In cases of duplicate submission, the Editor of the affected OSA journal will consult with the Editor of the other journal involved to determine the proper course of action. Often that action will be the rejection of both papers. Plagiarism: Plagiarism is a serious breach of ethics and is defined as the substantial replication, without attribution, of significant elements of another document already published by the same or other authors. Two types of plagiarism can occur-self-plagiarism and plagiarism from others' works. Self-plagiarism is the publication of substantially similar scientific content

  7. A Verification of MCNP6 FMESH Tally Capabilities

    SciTech Connect

    Swift, Alicia L.; McKigney, Edward A.; Schirato, Richard C.; Robinson, Alex Philip; Temple, Brian Allen

    2015-02-10

    This work serves to verify the MCNP6 FMESH capability through comparison to two types of data. FMESH tallies, binned in time, were generated on an ideal detector face for neutrons undergoing a single scatter in a graphite target. For verification, FMESH results were compared to analytic calculations of the nonrelativistic TOF for elastic and inelastic single neutron scatters (TOF for the purposes of this paper is the time for a neutron to travel from its scatter location in the graphite target to the detector face). FMESH tally results were also compared to F4 tally results, an MNCP tally that calculates fluence in the same way as the FMESH tally. The FMESH tally results agree well with the analytic results and the F4 tally; hence, it is believed that, for simple geometries, MCNP6 FMESH tallies represent the physics of neutron scattering very well.

  8. The MCNP{trademark}/LCS{trademark} merger project

    SciTech Connect

    Hughes, H.G.; Adams, K.J.; Chadwick, M.B.

    1997-10-01

    The MCNP code is written and maintained by Group X-TM at Los Alamos National Laboratory. In response to a variety of needs, and particularly in support of the Accelerator Production of Tritium (APT) program, the authors have recently undertaken a major effort to expand the capabilities of MCNP to increase the set of transportable particles; to make use of newly evaluated high energy nuclear data tables for neutrons, protons, and potentially other particles; and to incorporate physics models for use where tabular data are unavailable. A preliminary version of the expanded code, called MCNPX, has now been issued for testing. The new code includes all existing LAHET physics modules, and has the ability to utilize the 150 MeV data libraries that have recently been released by LANL Group T-2.

  9. A Tisket, A Tasket--Out of the Editor's Basket

    NASA Astrophysics Data System (ADS)

    Williams, Kathryn R.

    2001-05-01

    In September 1940, the Journal introduced Out of the Editor's Basket for short items of interest: excerpts from letters, pamphlets, newspapers, and periodicals. By 1950, however, the Editor's Basket had evolved into a bulletin board for descriptions of new products and services, and it now contains almost exclusively press releases about recently marketed items. Now over 60 years old, the Editor's Basket still provides interesting tidbits for the Journal's broad readership.

  10. MCNP/X TRANSPORT IN THE TABULAR REGIME

    SciTech Connect

    HUGHES, H. GRADY

    2007-01-08

    The authors review the transport capabilities of the MCNP and MCNPX Monte Carlo codes in the energy regimes in which tabular transport data are available. Giving special attention to neutron tables, they emphasize the measures taken to improve the treatment of a variety of difficult aspects of the transport problem, including unresolved resonances, thermal issues, and the availability of suitable cross sections sets. They also briefly touch on the current situation in regard to photon, electron, and proton transport tables.

  11. From the Board of Editors: on Plagiarism

    NASA Astrophysics Data System (ADS)

    2005-05-01

    Dear Colleagues: There has been a significant increase in the number of duplicate submissions and plagiarism cases reported in all major journals, including the journals of the Optical Society of America. Duplicate submissions and plagiarism can take many forms, and all of them are violations of professional ethics, the copyright agreement that an author signs along with the submission of a paper, and OSA's published Author Guidelines. There must be a significant component of new science for a paper to be publishable. The copying of large segments of text from previously published or in-press papers with only minor cosmetic changes is not acceptable and can lead to the rejection of papers. Duplicate submission: Duplicate submission is the most common ethics violation encountered. Duplicate submission is the submission of substantially similar papers to more than one journal. There is a misperception in a small fraction of the scientific community that duplicate submission is acceptable because it sometimes takes a long time to get a paper reviewed and because one of the papers can be withdrawn at any time. This is a clear violation of professional ethics and of the copyright agreement that is signed on submission. Duplicate submission harms the whole community because editors and reviewers waste their time and in the process compound the time it takes to get a paper reviewed for all authors. In cases of duplicate submission, the Editor of the affected OSA journal will consult with the Editor of the other journal involved to determine the proper course of action. Often that action will be the rejection of both papers. Plagiarism: Plagiarism is a serious breach of ethics and is defined as the substantial replication, without attribution, of significant elements of another document already published by the same or other authors. Two types of plagiarism can occur-self-plagiarism and plagiarism from others' works. Self-plagiarism is the publication of substantially

  12. From the Board of Editors: on Plagiarism

    NASA Astrophysics Data System (ADS)

    2005-04-01

    Dear Colleagues: There has been a significant increase in the number of duplicate submissions and plagiarism cases reported in all major journals, including the journals of the Optical Society of America. Duplicate submissions and plagiarism can take many forms, and all of them are violations of professional ethics, the copyright agreement that an author signs along with the submission of a paper, and OSA's published Author Guidelines. There must be a significant component of new science for a paper to be publishable. The copying of large segments of text from previously published or in-press papers with only minor cosmetic changes is not acceptable and can lead to the rejection of papers. Duplicate submission: Duplicate submission is the most common ethics violation encountered. Duplicate submission is the submission of substantially similar papers to more than one journal. There is a misperception in a small fraction of the scientific community that duplicate submission is acceptable because it sometimes takes a long time to get a paper reviewed and because one of the papers can be withdrawn at any time. This is a clear violation of professional ethics and of the copyright agreement that is signed on submission. Duplicate submission harms the whole community because editors and reviewers waste their time and in the process compound the time it takes to get a paper reviewed for all authors. In cases of duplicate submission, the Editor of the affected OSA journal will consult with the Editor of the other journal involved to determine the proper course of action. Often that action will be the rejection of both papers. Plagiarism: Plagiarism is a serious breach of ethics and is defined as the substantial replication, without attribution, of significant elements of another document already published by the same or other authors. Two types of plagiarism can occur-self-plagiarism and plagiarism from others' works. Self-plagiarism is the publication of substantially

  13. Information Scientists: Between Editors and Data Centers

    NASA Astrophysics Data System (ADS)

    Brouty, M.; Woelfel, F.; Bruneau, C.; Brunet, C.; Claude, H.; Dubois, P.; Eisele, A.; Genova, F.; Lesteven, S.; Neuville, M.; Ochsenbein, F.; Perret, E.; Vannier, P.; Vonflie, P.; Chassagnard, G.

    2010-10-01

    Since the emergence of electronic publications in the early 1990s, astronomy has played a pioneering role in the development and implementation of new capabilities and services. As a data center, the CDS contributed significantly to this evolution: a synergy between data centers and journal editors started in the 1990s with the publication of large tables and data sets in electronic form and contributed to an efficient linking of publications with existing databases like SIMBAD or NED. This collaborative work, carried out in practice by information scientists, illustrates a new role for us who now have to deal with both editor and database requirements. After a short description of the CDS, we present our peculiar responsibilities related to the publication process: ensuring, prior to publication, that the link from selected objects quoted by the authors in their papers to the SIMBAD database is correct and maintained in the long term, that the tables and their complete descriptions are accessible through VizieR, and that the data and bibliography are correctly entered in SIMBAD. The Dictionary of Nomenclature, which plays an important role in these procedures, is briefly presented. Finally, the skills we developed for these activities are shortly discussed.

  14. Yankee Rowe isotopics benchmark using MCNP-XT

    SciTech Connect

    Xu, Z.; Whitmer, C.

    2013-07-01

    The Yankee Rowe spent fuel isotopic data provides a valuable source to benchmark the burnup calculations as part of verification and validation (V and V) efforts for the TerraPower's Monte Carlo depletion code, MCNP-XT. A total of 71 fuel rods were selected in the Yankee Rowe isotopic measurements covering a burnup range up to 44 MWd/kg ({approx}4.4%) under both the asymptotic spectrum and the non-asymptotic spectrum. The MCNP-XT pin cell depletion provides a comparison against the asymptotic spectrum measurement; and full assembly depletion with 322 depletion materials provides comparisons against various non-asymptotic depletion conditions. All calculations are performed based on the recent ENDF/B-VII.O data. Furthermore, the Monte Carlo depletion uncertainties and biases were examined showing their effect as insignificant. The set of burnup calculations cover the scattered experimental measurements demonstrating excellent agreement with the measured values. This benchmark exercise demonstrates the depletion analysis capability of the MCNP-XT code and validates the low burnup range. (authors)

  15. Characteristics of multiprocessing MCNP5 on small personal computer clusters

    SciTech Connect

    Robinson, Sean M.; McConn, Ronald J.; Pagh, Richard T.; Schweppe, John E.; Siciliano, Edward R.

    2006-06-05

    The feasibility and efficiency of performing MCNP5 calculations with a small, heterogeneous computing cluster built from Microsoft® Windows™ Personal Computers (PCs) are explored. The performance increases that may be expected with such clusters are estimated. Our results show that the speed increase from additional slave PCs is nearly linear up to 10 processors. Guidance is given as to the specific advantages of changing various parameters present in the system. Implementing load balancing, and reducing the overhead from the MCNP rendezvous mechanism add to heterogeneous cluster efficiency. Hyper-threading technology and matching the total number of slave processes to the total number of logical processors also yield modest speed increases in the range below 7 processors. Because of the ease of acquisition of heterogeneous desktop computers, and the peak in efficiency at the level of a few physical processors, a strong case is made for the use of small clusters as a tool for producing MCNP5 calculations rapidly, and detailed instructions for constructing such clusters are provided.

  16. Code System for Generation of Input Data for MCNP.

    Energy Science and Technology Software Center (ESTSC)

    1998-07-16

    Version 00 The MSM-SOURCE code was designed for quick and easy estimations of basic stopping characteristics of proton transmission, for generation of the source definition (SDEF) portion of the input data for MCNP (for 3b- and 4- versions) [2], simulating the set of single neutron sources, produced in the sample during the proton transmission. It does not generate the ful MCNP input file. The results of calculations well reproduce the experimental data [3]. It permitsmore » one to extend the possibilities of the MCNP code for consideration of secondary neutrons from the proton interaction with nuclei of the sample substance. The MSM-SOURCE code is applicable for calculations of the proton transport for the incident energies from 0.1 to 1 GeV and various targets 12 < A < 238. This code is based of the Moving Source Model (MSM) (using the original parametrization [3],[4]) and Bethe stopping theory with the relativistic corrections for protons. It allows the estimations of the proton range, the changes of the proton current and the neutron production versus the depth. The double differential spectra and the multiplicities of nucleons, produced in the primary proton-induced reactions, are obtained. For the evaluation of inelastic cross section the original parametrization is used [4].« less

  17. MCNP6 fragmentation of light nuclei at intermediate energies

    NASA Astrophysics Data System (ADS)

    Mashnik, Stepan G.; Kerby, Leslie M.

    2014-11-01

    Fragmentation reactions induced on light target nuclei by protons and light nuclei of energies around 1 GeV/nucleon and below are studied with the latest Los Alamos Monte Carlo transport code MCNP6 and with its cascade-exciton model (CEM) and Los Alamos version of the quark-gluon string model (LAQGSM) event generators, version 03.03, used as stand-alone codes. Such reactions are involved in different applications, like cosmic-ray-induced single event upsets (SEU's), radiation protection, and cancer therapy with proton and ion beams, among others; therefore, it is important that MCNP6 simulates them as well as possible. CEM and LAQGSM assume that intermediate-energy fragmentation reactions on light nuclei occur generally in two stages. The first stage is the intranuclear cascade (INC), followed by the second, Fermi breakup disintegration of light excited residual nuclei produced after the INC. Both CEM and LAQGSM account also for coalescence of light fragments (complex particles) up to 4He from energetic nucleons emitted during INC. We investigate the validity and performance of MCNP6, CEM, and LAQGSM in simulating fragmentation reactions at intermediate energies and discuss possible ways of further improving these codes.

  18. EDITORIAL: Incoming Editor-in-Chief

    NASA Astrophysics Data System (ADS)

    Lidström, Suzanne

    2012-04-01

    When Professor Anders Bárány took over as the Executive Editor of Physica Scripta, in 1986, he talked of his trepidation at having to 'dress himself' in his predecessor's 'editorial coveralls'. At that time, they had been worn by Professor Nils Robert Nilsson, a major figure in the physics community, for almost 20 years. Just one year prior to this, Professor Roger Wäppling had been recruited to the position of Subeditor in conjunction with a decision to expand the number of contributions in the field of condensed matter physics, to turn it into one of the dominant subjects in the broad-based journal. Physica Scripta had already gained a reputation for being a high quality journal with wide coverage of both experimental and theoretical physics. Interestingly, in the mid 1980s, the number of papers submitted had been growing and an impressive 250 submissions per year had been attained, with all of the manuscripts being handled in-house. Not many miles away in the town of Uppsala, a group of English students was stepping off a train on a magnificent snowy day in January to embark on their final year projects. A couple of us enjoyed ourselves so much that we stayed on afterwards as PhD students, thereby encountering the mixed pleasure of studying physics in a second language for the first time. I used to copy the notes down meticulously in Swedish, then try to work backwards with a textbook to improve my language skills. One day, returning from a particularly incomprehensible lecture on solid state physics, I showed my roommates my notes and asked if they could please explain what the lecture had been about: 'I don't know', they replied, 'but this bit is about sheep!' Meanwhile, back at Physica Scripta, the journal continued to flourish: 400 submissions were received in 1996, and the march of progress was well underway. Manuscripts could now be sent in on disks and Physica Scripta was available on the World Wide Web. Roger was appointed to manage the journal and

  19. Technical Note: Improved implementation of doppler broadening in MCNP5

    SciTech Connect

    Bartol, Laura J.; DeWerd, Larry A.

    2012-09-15

    Purpose: Incoherent scattering has a substantial effect on spectroscopic measurements and simulations. Many general-purpose Monte Carlo codes include models that account for the effects of bound electrons on incoherent scattering, including Doppler broadening (DB). This work investigates the DB model used in the Monte Carlo N-particle transport code (MCNP5). Methods: Simulations were run with three versions of MCNP5: v1.51, v1.60, and a modified form of v1.60 (v1.60m). All simulations used the MCPLIB04 photon data library, which presents the electron subshell data for incoherent scattering in the form of a probability density function. In v1.60m, the source code was altered to sample the electron subshell from a cumulative density function instead. Each version of the code was tested using an identical set of simulations that investigated DB in a slab of silicon at scattering angles of 15 Degree-Sign , 30 Degree-Sign , and 45 Degree-Sign . For each angle, simulations were run for multiple energies between 200 keV and 800 keV. The spectrum of singly-scattered photons at the exit of the slab was scored. Spectra were analytically calculated for comparison. Results: In v1.51, DB was modeled for incident photon energies below 760 keV, 384 keV, and 260 keV at scattering angles of 15 Degree-Sign , 30 Degree-Sign , and 45 Degree-Sign , respectively. Above these energy thresholds, v1.51 did not model DB. The spectra calculated using v1.60 and v1.60m exhibited DB for all energy-angle combinations; however, v1.60m, exhibited more energy broadening than did v1.60. The spectra calculated with v1.60m agreed with the analytical calculations. Conclusions: MCNP5 v1.51 and v1.60 model partial broadening when used with the MCPLIB04 data library. MCNP5 v1.60m models DB more accurately due to the form of the electron subshell data. In response to these results, Los Alamos National Laboratory has released a new photon data library, MCPLIB84, that presents the electron subshell data in

  20. Visualization of JPEG Metadata

    NASA Astrophysics Data System (ADS)

    Malik Mohamad, Kamaruddin; Deris, Mustafa Mat

    There are a lot of information embedded in JPEG image than just graphics. Visualization of its metadata would benefit digital forensic investigator to view embedded data including corrupted image where no graphics can be displayed in order to assist in evidence collection for cases such as child pornography or steganography. There are already available tools such as metadata readers, editors and extraction tools but mostly focusing on visualizing attribute information of JPEG Exif. However, none have been done to visualize metadata by consolidating markers summary, header structure, Huffman table and quantization table in a single program. In this paper, metadata visualization is done by developing a program that able to summarize all existing markers, header structure, Huffman table and quantization table in JPEG. The result shows that visualization of metadata helps viewing the hidden information within JPEG more easily.

  1. John F. Dewey—Tectonics Editor

    NASA Astrophysics Data System (ADS)

    Richman, Barbara T.

    ‘I want the journal to acquire a reputation for very rapid, fair, and accurate reviewing,’ asserted John F. Dewey, editor-in-chief of AGU's newest journal, Tectonics. Dewey said that he will rule the bimonthly, which will begin publication in February, ‘with a bit of a rod of iron’ to ensure that Tectonics is ‘where only original and important papers are published.’‘I'm going to be very strict with reviewers,’ Dewey explained in his quick British clip. ‘If the review does not come back to me within 10 days to 2 weeks, I'll review the paper myself. I'm also going to have a system whereby, if a paper needs major surgery after being refereed, it will be rejected. Papers will have to be in virtually publishable condition before they are first submitted,’ he said.

  2. The RAE and Publications: A Review of Journal Editors.

    ERIC Educational Resources Information Center

    Talib, Ameen Ali

    2000-01-01

    Surveyed editors of academic journals about publication issues related to Britain's Research Assessment Exercise (RAE), a process of grading and funding universities based on published research output. Editors were asked about research quality and output, publication practices, academics' willingness to referee manuscripts, and proliferation of…

  3. How Newspaper Editors Reacted to "Post's" Pulitzer Prize Hoax.

    ERIC Educational Resources Information Center

    Anderson, Douglas A.

    1982-01-01

    Reports the findings of a nationwide survey of newspaper editors, revealing that most thought that the Janet Cooke hoax had been poorly handled by the "Washington Post." Notes that most of the editors said their newspapers had systems of review for stories coming from anonymous sources. (FL)

  4. Peer reviews and the role of a journal editor

    Technology Transfer Automated Retrieval System (TEKTRAN)

    Obtaining peer reviews for manuscripts submitted to scientific journals is becoming increasingly difficult. Changes to the system are necessary, and editors must cultivate and maintain a solid base of reviewers to help evaluate journal submissions. This article outlines some steps editors can and sh...

  5. Editors and author resource centers actively used by attendees

    NASA Astrophysics Data System (ADS)

    Major, Barbara

    2012-02-01

    At the 2011 Fall Meeting, as in previous years, the Editors Resource Center located on the second floor of Moscone West was buzzing with activity: editors talking with other editors, collaborating with associate editors, speaking with authors, and meeting with students. In addition, several editors took part in "Meet the Editor" informal sessions, a new feature introduced for the 2011 meeting to strengthen the partnership between authors and editors. The map "Where are you from?" (see photo), outside the Editors Resource Center, drew the attention of many attendees who were eager to place their colored dots on the map. The Author Resource Center, located in the AGU Marketplace, became a hub for AGU veteran authors and potential authors alike. Staff were there to answer both editorial and technical questions, especially the most frequent one: What happens after my paper is accepted? The running slideshow that described all aspects of the AGU publications program sparked a myriad of questions, which AGU staff were happy to answer.

  6. Advisers, Editors and Principals Judge First Amendment Cases.

    ERIC Educational Resources Information Center

    Broussard, E. Joseph; Blackmon, C. Robert

    1978-01-01

    A test of the knowledge of 378 high school publications advisers, editors, and principals regarding First Amendment rights revealed that advisers had the most knowledge, followed by editors and then by principals. Characteristics of the most knowledgeable advisers were then identified. (GT)

  7. Technical Writing Style: Preferences of Scientists, Editors, and Students.

    ERIC Educational Resources Information Center

    Donnellan, LaRae M.

    To determine whether scientists and science students would accept a simplified writing style, two studies were conducted. In the first study, respondents--1,089 scientists from agricultural experiment stations, 20 station editors, and 59 editors of scientific journals--answered a questionnaire requesting biographical information and reactions to a…

  8. Journal Editor Perceptions of Universities: Some Empirical Evidence

    ERIC Educational Resources Information Center

    Mainardes, Emerson Wagner; Raposo, Mario; Alves, Helena

    2012-01-01

    Out of considerations as to the importance of university relationships with their various stakeholders, the primary objective of this research project was to identify the perceptions of academic journal editors regarding universities. Editors were asked to provide their perceptions on: (a) the relevance of universities to academic publications;…

  9. Academic Degradation and the Retreat of the Editors: Academic Irregularities and the Spreading of Academic Corruption from an Editor's Perspective

    ERIC Educational Resources Information Center

    Xun, Gong

    2007-01-01

    Against the backdrop of the grave academic crisis in China, editors have become the objects of wooing, favor-currying, connections-seeking, and collusions; they have been targeted for attacks, plots, extortions, and encroachments. Editing and publishing have become avenues for academic irregularities and academic corruption. Editors have the power…

  10. Monte Carlo N–Particle Transport Code System Including MCNP6.1, MCNP5-1.60, MCNPX-2.7.0 and Data Libraries.

    Energy Science and Technology Software Center (ESTSC)

    2013-07-16

    Version 01 US DOE 10CFR810 Jurisdiction. MCNP6™ is a general-purpose, continuous-energy, generalized-geometry, time-dependent, Monte Carlo radiation-transport code designed to track many particle types over broad ranges of energies. MCNP6 represents the culmination of a multi-year effort to merge the MCNP5™ [X-503] and MCNPX™ [PEL11] codes into a single product comprising all features of both. For those familiar with previous versions of MCNP, you will discover the code has been expanded to handle a multitude ofmore » particles and to include model physics options for energies above the cross-section table range, a material burnup feature, and delayed particle production. Expanded and/or new tally, source, and variance-reduction options are available to the user as well as an improved plotting capability. The capability to calculate keff eigenvalues for fissile systems remains a standard feature. Although MCNP6 is simply and accurately described as the merger of MCNP5 and MCNPX capabilities, the result is much more than the sum of these two computer codes. MCNP6 is the result of five years of effort by the MCNP5 and MCNPX code development teams. These groups of people, residing in the Los Alamos National Laboratory's (LANL) X Computational Physics Division, Monte Carlo Codes Group (XCP-3), and Nuclear Engineering and Nonproliferation Division, Systems Design and Analysis Group (NEN-5, formerly D-5), have combined their code development efforts to produce the next evolution of MCNP. While maintenance and bug fixes will continue for MCNP5 v.1.60 and MCNPX v.2.7.0 for upcoming years, new code development capabilities will be developed and released only in MCNP6. In fact, this initial production release of MCNP6 (v. 1.0) contains 16 new features not previously found in either code. These new features include (among others) the abilities to import unstructured mesh geometries from the finite element code Abaqus, to transport photons down to 1.0 eV, to model

  11. Monte Carlo N–Particle Transport Code System Including MCNP6.1, MCNP5-1.60, MCNPX-2.7.0 and Data Libraries.

    Energy Science and Technology Software Center (ESTSC)

    2013-07-16

    Version 00 US DOE 10CFR810 Jurisdiction. MCNP6™ is a general-purpose, continuous-energy, generalized-geometry, time-dependent, Monte Carlo radiation-transport code designed to track many particle types over broad ranges of energies. MCNP6 represents the culmination of a multi-year effort to merge the MCNP5™ [X-503] and MCNPX™ [PEL11] codes into a single product comprising all features of both. For those familiar with previous versions of MCNP, you will discover the code has been expanded to handle a multitude ofmore » particles and to include model physics options for energies above the cross-section table range, a material burnup feature, and delayed particle production. Expanded and/or new tally, source, and variance-reduction options are available to the user as well as an improved plotting capability. The capability to calculate keff eigenvalues for fissile systems remains a standard feature. Although MCNP6 is simply and accurately described as the merger of MCNP5 and MCNPX capabilities, the result is much more than the sum of these two computer codes. MCNP6 is the result of five years of effort by the MCNP5 and MCNPX code development teams. These groups of people, residing in the Los Alamos National Laboratory's (LANL) X Computational Physics Division, Monte Carlo Codes Group (XCP-3), and Nuclear Engineering and Nonproliferation Division, Systems Design and Analysis Group (NEN-5, formerly D-5), have combined their code development efforts to produce the next evolution of MCNP. While maintenance and bug fixes will continue for MCNP5 v.1.60 and MCNPX v.2.7.0 for upcoming years, new code development capabilities will be developed and released only in MCNP6. In fact, this initial production release of MCNP6 (v. 1.0) contains 16 new features not previously found in either code. These new features include (among others) the abilities to import unstructured mesh geometries from the finite element code Abaqus, to transport photons down to 1.0 eV, to model

  12. Monte Carlo N–Particle Transport Code System Including MCNP6.1, MCNP5-1.60, MCNPX-2.7.0 and Data Libraries.

    SciTech Connect

    GOORLEY, TIM

    2013-07-16

    Version 00 US DOE 10CFR810 Jurisdiction. MCNP6™ is a general-purpose, continuous-energy, generalized-geometry, time-dependent, Monte Carlo radiation-transport code designed to track many particle types over broad ranges of energies. MCNP6 represents the culmination of a multi-year effort to merge the MCNP5™ [X-503] and MCNPX™ [PEL11] codes into a single product comprising all features of both. For those familiar with previous versions of MCNP, you will discover the code has been expanded to handle a multitude of particles and to include model physics options for energies above the cross-section table range, a material burnup feature, and delayed particle production. Expanded and/or new tally, source, and variance-reduction options are available to the user as well as an improved plotting capability. The capability to calculate keff eigenvalues for fissile systems remains a standard feature. Although MCNP6 is simply and accurately described as the merger of MCNP5 and MCNPX capabilities, the result is much more than the sum of these two computer codes. MCNP6 is the result of five years of effort by the MCNP5 and MCNPX code development teams. These groups of people, residing in the Los Alamos National Laboratory's (LANL) X Computational Physics Division, Monte Carlo Codes Group (XCP-3), and Nuclear Engineering and Nonproliferation Division, Systems Design and Analysis Group (NEN-5, formerly D-5), have combined their code development efforts to produce the next evolution of MCNP. While maintenance and bug fixes will continue for MCNP5 v.1.60 and MCNPX v.2.7.0 for upcoming years, new code development capabilities will be developed and released only in MCNP6. In fact, this initial production release of MCNP6 (v. 1.0) contains 16 new features not previously found in either code. These new features include (among others) the abilities to import unstructured mesh geometries from the finite element code Abaqus, to transport photons down to 1.0 eV, to model complete atomic

  13. Monte Carlo N–Particle Transport Code System Including MCNP6.1, MCNP5-1.60, MCNPX-2.7.0 and Data Libraries.

    SciTech Connect

    GOORLEY, TIM

    2013-07-16

    Version 01 US DOE 10CFR810 Jurisdiction. MCNP6™ is a general-purpose, continuous-energy, generalized-geometry, time-dependent, Monte Carlo radiation-transport code designed to track many particle types over broad ranges of energies. MCNP6 represents the culmination of a multi-year effort to merge the MCNP5™ [X-503] and MCNPX™ [PEL11] codes into a single product comprising all features of both. For those familiar with previous versions of MCNP, you will discover the code has been expanded to handle a multitude of particles and to include model physics options for energies above the cross-section table range, a material burnup feature, and delayed particle production. Expanded and/or new tally, source, and variance-reduction options are available to the user as well as an improved plotting capability. The capability to calculate keff eigenvalues for fissile systems remains a standard feature. Although MCNP6 is simply and accurately described as the merger of MCNP5 and MCNPX capabilities, the result is much more than the sum of these two computer codes. MCNP6 is the result of five years of effort by the MCNP5 and MCNPX code development teams. These groups of people, residing in the Los Alamos National Laboratory's (LANL) X Computational Physics Division, Monte Carlo Codes Group (XCP-3), and Nuclear Engineering and Nonproliferation Division, Systems Design and Analysis Group (NEN-5, formerly D-5), have combined their code development efforts to produce the next evolution of MCNP. While maintenance and bug fixes will continue for MCNP5 v.1.60 and MCNPX v.2.7.0 for upcoming years, new code development capabilities will be developed and released only in MCNP6. In fact, this initial production release of MCNP6 (v. 1.0) contains 16 new features not previously found in either code. These new features include (among others) the abilities to import unstructured mesh geometries from the finite element code Abaqus, to transport photons down to 1.0 eV, to model complete atomic

  14. EDITORIAL: Incoming Editor-in-Chief

    NASA Astrophysics Data System (ADS)

    Lidström, Suzanne

    2012-04-01

    When Professor Anders Bárány took over as the Executive Editor of Physica Scripta, in 1986, he talked of his trepidation at having to 'dress himself' in his predecessor's 'editorial coveralls'. At that time, they had been worn by Professor Nils Robert Nilsson, a major figure in the physics community, for almost 20 years. Just one year prior to this, Professor Roger Wäppling had been recruited to the position of Subeditor in conjunction with a decision to expand the number of contributions in the field of condensed matter physics, to turn it into one of the dominant subjects in the broad-based journal. Physica Scripta had already gained a reputation for being a high quality journal with wide coverage of both experimental and theoretical physics. Interestingly, in the mid 1980s, the number of papers submitted had been growing and an impressive 250 submissions per year had been attained, with all of the manuscripts being handled in-house. Not many miles away in the town of Uppsala, a group of English students was stepping off a train on a magnificent snowy day in January to embark on their final year projects. A couple of us enjoyed ourselves so much that we stayed on afterwards as PhD students, thereby encountering the mixed pleasure of studying physics in a second language for the first time. I used to copy the notes down meticulously in Swedish, then try to work backwards with a textbook to improve my language skills. One day, returning from a particularly incomprehensible lecture on solid state physics, I showed my roommates my notes and asked if they could please explain what the lecture had been about: 'I don't know', they replied, 'but this bit is about sheep!' Meanwhile, back at Physica Scripta, the journal continued to flourish: 400 submissions were received in 1996, and the march of progress was well underway. Manuscripts could now be sent in on disks and Physica Scripta was available on the World Wide Web. Roger was appointed to manage the journal and

  15. Martin Stutzmann: Editor, Teacher, Scientist and Friend

    NASA Astrophysics Data System (ADS)

    Cardona, Manuel

    2005-03-01

    On 2 January 1995 Martin Stutzmann became Editor-in-Chief of physica status solidi, replacing Professor E. Gutsche, who had led the journal through the stormy period involving the fall of the Iron Curtain, the unification of Germany and the change in its Eastern part, where physica status solidi was based, from socialism as found in the real world (a German concept) to real world capitalism. In 1995 it was thought that the process had been completed (we should have known better!) and after the retirement of Prof. Gutsche the new owners of physica status solidi (Wiley-VCH) decided that a change in scientific management was desirable to adapt to the new socio-political facts and to insure the scientific continuity of the journal.Martin had moved in 1993 from my department at the Max-Planck-Institute to Munich where he soon displayed a tremendous amount of science man- agement ability during the build-up of the Walter Schottky Institute. The search for a successor as Edi- tor-in-Chief was not easy: the job was not very glamorous after the upheavals which had taken place in the editorial world following the political changes. Somebody in the Editorial Boards must have suggested Martin Stutzmann. I am sure that there was opposition: one usually looks for a well-established person ready to leave his direct involvement in science and take up a new endeavor of a more administrative nature. Nevertheless, the powers that be soon realized that Martin was an excellent, if somewhat unconventional candidate who had enough energy to remain a topnotch scientist and to lead the journal in the difficult times ahead: he was offered the job. In the negotiations that followed, he insisted in getting the administrative structures that would allow him to improve the battered quality of the journal and to continue his scientific productivity. Today we are happy to see that he succeeded in both endeavors. The journal has since grown in size and considerably improved its quality

  16. Modelling of dynamic experiments in MCNP5 environment.

    PubMed

    Mosorov, Volodymyr; Zych, Marcin; Hanus, Robert; Petryka, Leszek

    2016-06-01

    The design of radiation measurement systems includes a modelling phase which ascertains the best 3D geometry for a projected gauge. To simulate measured counts by a detector, the widely-used rigorous phenomenological model is used. However, this model does not consider possible source or/and detector movement during a measurement interval. Therefore, the phenomenological model has been successfully modified in order to consider such a displacement during the time sampling interval in dynamic experiments. To validate the proposed model, a simple radiation system was accurately implemented in the MCNP5 code. The experiments confirmed the accuracy of the proposed model. PMID:27058321

  17. Heart simulation with surface equations for using on MCNP code

    SciTech Connect

    Rezaei-Ochbelagh, D.; Salman-Nezhad, S.; Asadi, A.; Rahimi, A.

    2011-12-26

    External photon beam radiotherapy is carried out in a way to achieve an 'as low as possible' a dose in healthy tissues surrounding the target. One of these surroundings can be heart as a vital organ of body. As it is impossible to directly determine the absorbed dose by heart, using phantoms is one way to acquire information around it. The other way is Monte Carlo method. In this work we have presented a simulation of heart geometry by introducing of different surfaces in MCNP code. We used 14 surface equations in order to determine human heart modeling. Those surfaces are borders of heart walls and contents.

  18. Radiation calculations using LAHET/MCNP/CINDER90

    SciTech Connect

    Waters, L.

    1994-10-01

    The LAHET monte carlo code system has recently been expanded to include high energy hadronic interactions via the FLUKA code, while retaining the original Los Alamos versions of HETC and ISABEL at lower energies. Electrons and photons are transported with EGS4 or ITS, while the MCNP coupled neutron/photon monte carlo code provides analysis of neutrons with kinetic energies less than 20 MeV. An interface with the CINDER activation code is now in common use. Various other changes have been made to facilitate analysis of high energy accelerator radiation environments and experimental physics apparatus, such as those found at SSC and RHIC. Current code developments and applications are reviewed.

  19. Radiation calculations using LAHET/MCNP/CINDER90

    SciTech Connect

    Waters, L.S.

    1993-08-01

    The LAHET Monte Carlo code system has recently been expanded to include high energy hadronic interactions via the FLUKA code, while retaining the original Los Alamos versions of HETC and ISABEL at lower energies. Electrons and photons are transported with EGS4 or ITS, while the MCNP coupled neutron/photon Monte Carlo code provides analysis of neutrons with kinetic energies less than 20 MeV. An interface with the CINDER activation code is now in common use. Various other changes have been made to facilitate analysis of high energy accelerator radiation environments and experimental physics apparatus, such as those found at SSC and RHIC. Current code developments and applications are reviewed.

  20. Heart simulation with surface equations for using on MCNP code

    NASA Astrophysics Data System (ADS)

    Rezaei-Ochbelagh, D.; Salman-Nezhad, S.; Asadi, A.; Rahimi, A.

    2011-12-01

    External photon beam radiotherapy is carried out in a way to achieve an "as low as possible" a dose in healthy tissues surrounding the target. One of these surroundings can be heart as a vital organ of body. As it is impossible to directly determine the absorbed dose by heart, using phantoms is one way to acquire information around it. The other way is Monte Carlo method. In this work we have presented a simulation of heart geometry by introducing of different surfaces in MCNP code. We used 14 surface equations in order to determine human heart modeling. Those surfaces are borders of heart walls and contents.

  1. MCNP5 CALCULATIONS REPLICATING ARH-600 NITRATE DATA

    SciTech Connect

    FINFROCK SH

    2011-10-25

    This report serves to extend the previous document: 'MCNP Calculations Replicating ARH-600 Data' by replicating the nitrate curves found in ARH-600. This report includes the MCNP models used, the calculated critical dimension for each analyzed parameter set, and the resulting data libraries for use with the CritView code. As with the ARH-600 data, this report is not meant to replace the analysis of the fissile systems by qualified criticality personnel. The M CNP data is presented without accounting for the statistical uncertainty (although this is typically less than 0.001) or bias and, as such, the application of a reasonable safety margin is required. The data that follows pertains to the uranyl nitrate and plutonium nitrate spheres, infinite cylinders, and infinite slabs of varying isotopic composition, reflector thickness, and molarity. Each of the cases was modeled in MCNP (version 5.1.40), using the ENDF/B-VI cross section set. Given a molarity, isotopic composition, and reflector thickness, the fissile concentration and diameter (or thicknesses in the case of the slab geometries) were varied. The diameter for which k-effective equals 1.00 for a given concentration could then be calculated and graphed. These graphs are included in this report. The pages that follow describe the regions modeled, formulas for calculating the various parameters, a list of cross-sections used in the calculations, a description of the automation routine and data, and finally the data output. The data of most interest are the critical dimensions of the various systems analyzed. This is presented graphically, and in table format, in Appendix B. Appendix C provides a text listing of the same data in a format that is compatible with the CritView code. Appendices D and E provide listing of example Template files and MCNP input files (these are discussed further in Section 4). Appendix F is a complete listing of all of the output data (i.e., all of the analyzed dimensions and the

  2. NGSView: an extensible open source editor for next-generation sequencing data

    PubMed Central

    Arner, Erik; Hayashizaki, Yoshihide; Daub, Carsten O.

    2010-01-01

    Summary:High-throughput sequencing technologies introduce novel demands on tools available for data analysis. We have developed NGSView (Next Generation Sequence View), a generally applicable, flexible and extensible next-generation sequence alignment editor. The software allows for visualization and manipulation of millions of sequences simultaneously on a desktop computer, through a graphical interface. NGSView is available under an open source license and can be extended through a well documented API. Availability: http://ngsview.sourceforge.net Contact: arner@gsc.riken.jp PMID:19855106

  3. Standard Neutron, Photon, and Electron Data Libraries for MCNP4B.

    Energy Science and Technology Software Center (ESTSC)

    1997-04-01

    Version 00 US DOE 10CFR810 Jurisdiction. DLC-189/MCNPXS is for use with Version 4B and later of the MCNP transport code. This data library provides a comprehensive set of cross sections for a wide range of radiation transport applications using the Monte Carlo code package CCC-660/MCNP4B.

  4. Application of MCNP{trademark} to storage facility dose rate assessment

    SciTech Connect

    Urban, W.T.; Roberts, R.R.; Estes, G.P.; Taylor, W.M.

    1996-12-31

    The MCNP code is widely used in the determination of neutral particle dose rate analyses. In this paper we examine the application of MCNP to several storage facilities containing special nuclear material, SNM, wherein the neutron dose rate is the primary quantity of interest. In particular, we describe the special geometry, modeling assumptions, and physics considerations encountered in each of three applications.

  5. MCNP: a general Monte Carlo code for neutron and photon transport

    SciTech Connect

    Forster, R.A.; Godfrey, T.N.K.

    1985-01-01

    MCNP is a very general Monte Carlo neutron photon transport code system with approximately 250 person years of Group X-6 code development invested. It is extremely portable, user-oriented, and a true production code as it is used about 60 Cray hours per month by about 150 Los Alamos users. It has as its data base the best cross-section evaluations available. MCNP contains state-of-the-art traditional and adaptive Monte Carlo techniques to be applied to the solution of an ever-increasing number of problems. Excellent user-oriented documentation is available for all facets of the MCNP code system. Many useful and important variants of MCNP exist for special applications. The Radiation Shielding Information Center (RSIC) in Oak Ridge, Tennessee is the contact point for worldwide MCNP code and documentation distribution. A much improved MCNP Version 3A will be available in the fall of 1985, along with new and improved documentation. Future directions in MCNP development will change the meaning of MCNP to Monte Carlo N Particle where N particle varieties will be transported.

  6. The MCNP-DSP code for calculations of time and frequency analysis parameters for subcritical systems

    SciTech Connect

    Valentine, T.E.; Mihalczo, J.T.

    1995-12-31

    This paper describes a modified version of the MCNP code, the MCNP-DSP. Variance reduction features were disabled to have strictly analog particle tracking in order to follow fluctuating processes more accurately. Some of the neutron and photon physics routines were modified to better represent the production of particles. Other modifications are discussed.

  7. Electron photon verification calculations using MCNP4B

    SciTech Connect

    Gierga, D.P.; Adams, K.J.

    1998-07-01

    MCNP4B was released in February 1997 with significant enhancements to electron/photon transport methods. These enhancements have been verified against a wide range of published electron/photon experiments, spanning high energy bremsstrahlung production to electron transmission and reflection. Three sets of bremsstrahlung experiments were simulated. The first verification calculations for bremsstrahlung production used the experimental results in Faddegon for 15 MeV electrons incident on lead, aluminum, and beryllium targets. The calculated integrated bremsstrahlung yields, the bremsstrahlung energy spectra, and the mean energy of the bremsstrahlung beam were compared with experiment. The impact of several MCNP tally options and physics parameters was explored in detail. The second was the experiment of O`Dell which measured the bremsstrahlung spectra from 10 and 20.9 MeV electrons incident on a gold/tungsten target. The final set was a comparison of relative experimental spectra with calculated results for 9.66 MeV electrons incident on tungsten based on the experiment of Starfelt and Koch. The transmission experiments of Ebert were also studied, including comparisons of transmission coefficients for 10.2 MeV electrons incident on carbon, silver, and uranium foils. The agreement between experiment and simulation was usually within two standard deviations of the experimental and calculational errors.

  8. MCNP/MCNPX model of the annular core research reactor.

    SciTech Connect

    DePriest, Kendall Russell; Cooper, Philip J.; Parma, Edward J., Jr.

    2006-10-01

    Many experimenters at the Annular Core Research Reactor (ACRR) have a need to predict the neutron/gamma environment prior to testing. In some cases, the neutron/gamma environment is needed to understand the test results after the completion of an experiment. In an effort to satisfy the needs of experimenters, a model of the ACRR was developed for use with the Monte Carlo N-Particle transport codes MCNP [Br03] and MCNPX [Wa02]. The model contains adjustable safety, transient, and control rods, several of the available spectrum-modifying cavity inserts, and placeholders for experiment packages. The ACRR model was constructed such that experiment package models can be easily placed in the reactor after being developed as stand-alone units. An addition to the 'standard' model allows the FREC-II cavity to be included in the calculations. This report presents the MCNP/MCNPX model of the ACRR. Comparisons are made between the model and the reactor for various configurations. Reactivity worth curves for the various reactor configurations are presented. Examples of reactivity worth calculations for a few experiment packages are presented along with the measured reactivity worth from the reactor test of the experiment packages. Finally, calculated neutron/gamma spectra are presented.

  9. A Python-based IRAF Task Parameter Editor

    NASA Astrophysics Data System (ADS)

    de La Peña, M. D.

    As part of the development of a new Python-based CL for IRAF tasks by the Science Software Group at STScI, we have developed a GUI-based parameter editor for IRAF tasks using Tkinter. This new parameter editor is intended to provide the equivalent functionality of the IRAF EPAR task, but to make parameter editing easier by using appropriate user interface elements, such as menu choice lists, action buttons, and file browsers. This paper describes the design and functionality of the parameter editor as well as planned enhancements.

  10. Retirement of J. Gary Eden as Editor-in-Chief

    NASA Astrophysics Data System (ADS)

    Jagadish, Chennupati; Jelinkova, Helena; Fainman, Yeshaiahu; Dawson, Martin; Ermers, Ysabel

    2016-01-01

    After nine years of dedicated service as Editor-in-Chief of Progress in Quantum Electronics (PQE), J. Gary Eden has retired at the end of December 2015. During his term as the Editor-in-Chief, PQE has grown significantly in size and quality and he has given generously of his time in advising authors, referees, editors, and the journal staff. Gary is an exceptional scientist and a generous individual who has given so much to the community. He is always very positive in every situation, and has created positive environment and supported people with utmost enthusiasm.

  11. Team of three JGR-Space Physics editors appointed

    NASA Astrophysics Data System (ADS)

    Three editors from the United States, Europe, and Asia have been appointed to lead JGR-Space Physics into the new millennium. This new team will recognize and foster the substantial contributions that scientists from the international community make to the journal. Janet Luhmann, a Senior Fellow at the Space Sciences Laboratory, University of California, Berkeley, will serve as Senior Editor. Luhmann will play a coordinating role for the regional editors, which will be especially important as the Union moves into electronic publishing and adopts new ways of using the technology to publish research findings.

  12. EDITORIAL: Incoming Editor-in-Chief

    NASA Astrophysics Data System (ADS)

    Webb, Steve

    2006-01-01

    Physics in Medicine and Biology (PMB) is a journal that originated in the UK but is now rightly regarded as one of the pre-eminent international journals for the publication of material coming within its remit. It is 50 years old and its maturity is an outcome of the consistent support of high performing authors, a supportive and professional publishing house, dedicated referees, many vigorous and conscientious editorial boards and the collective input of the 10 previous Editors as listed in his incoming editorial (January 2000 issue) by the retiring Editor, Professor Alun Beddoe. The scientific climate and it associated publication modus operandi in the 1950s was very different from that at the current time and the journal has evolved to reflect this. Hence today the scope of content is somewhat broader, the size of the journal is vastly greater, the whole publication process is slicker and more efficient and a paper in PMB is highly prized by its authors and those who look to quality factors and impact. The quality of the journal still relies on the voluntary labour and expertise of its busy international referees and Board members. For many years I have tried to place my own research material in PMB and encourage my teams to do likewise, not only acknowledging the prestige of the journal but also because of the extraordinarily fast turnaround time of all the processes without any loss of quality. This serves us very well and the publishing team are to be congratulated. Some things seem to change more slowly or not at all, however. The prediction, when I started my research career, that books and journals would be dinosaurs by now has manifestly not come true and, whilst most of us are addicted (and why not?) to the electronic ways of doing things that can be done by more traditional ways, PMB and a packet of reprints from time to time arriving by post still has a reassuring feel despite the fact that the papers have been `on-line' for a while before. An incoming

  13. ESDAPT - APT PROGRAMMING EDITOR AND INTERPRETER

    NASA Technical Reports Server (NTRS)

    Premack, T.

    1994-01-01

    ESDAPT is a graphical programming environment for developing APT (Automatically Programmed Tool) programs for controlling numerically controlled machine tools. ESDAPT has a graphical user interface that provides the user with an APT syntax sensitive text editor and windows for displaying geometry and tool paths. APT geometry statement can also be created using menus and screen picks. ESDAPT interprets APT geometry statements and displays the results in its view windows. Tool paths are generated by batching the APT source to an APT processor (COSMIC P-APT recommended). The tool paths are then displayed in the view windows. Hardcopy output of the view windows is in color PostScript format. ESDAPT is written in C-language, yacc, lex, and XView for use on Sun4 series computers running SunOS. ESDAPT requires 4Mb of disk space, 7Mb of RAM, and MIT's X Window System, Version 11 Release 4, or OpenWindows version 3 for execution. Program documentation in PostScript format and an executable for OpenWindows version 3 are provided on the distribution media. The standard distribution medium for ESDAPT is a .25 inch streaming magnetic tape cartridge (Sun QIC-24) in UNIX tar format. This program was developed in 1992.

  14. Introduction of our new associate editor.

    PubMed

    Desjardins, Annick; Gunawardana, Roshaine

    2014-01-01

    Annick Desjardins, MD, FRCPC, speaks to Roshaine Gunawardana, Managing Commissioning Editor: Annick Desjardins is Associate Professor within the Department of Neurology and is the Director of Clinical Research at The Preston Robert Tisch Brain Tumor Center at Duke. In 2003, Dr Desjardins completed her residency in Adult Neurology at the Universite de Sherbrooke, Quebec, Canada. Following a 2-year fellowship in neuro-oncology at The Preston Robert Tisch Brain Tumor Center at Duke, she joined the Center as faculty, in July 2005. She is a Fellow of the Royal College of Physicians of Canada. She has been the Principal Investigator on over 30 therapeutic trials in neuro-oncology, including investigator initiated and international multicenter studies, and has held several Investigational New Drug applications. She has over 80 peer-review publications and six book chapters. She has written invited expert reviews for Hospital Pharmacy Europe, Nature Reviews Neurology, Clinical Care Options and MEDscape CME. She is reviewer for Neuro-Oncology, Cancer, Journal of Neuro-Oncology, Clinical Cancer Research, Expert Review of Anticancer Therapy, Cancer Research, Molecular Cancer Therapeutics and Future Oncology. PMID:25363004

  15. Testing the Delayed Gamma Capability in MCNP6

    SciTech Connect

    Weldon, Robert A.; Fensin, Michael L.; McKinney, Gregg W.

    2015-10-28

    . We examine five different decay chains (two-stage decay to stable) and show the predictability of the MCNP6 delayed gamma feature. Results do show that while the default delayed gamma calculations available in the MCNP6 1.0 release can give accurate results for some isotopes (e.g., 137Ba), the percent differences between the closed form analytic solutions and the MCNP6 calculations were often >40% (28Mg, 28Al, 42K, 47Ca, 47Sc, 60Co). With the MCNP6 1.1 Beta release, the tenth entry on the DBCN card allows improved calculation within <5% as compared to the closed form analytic solutions for immediate parent emissions and transient equilibrium systems. While the tenth entry on the DBCN card for MCNP6 1.1 gives much better results for transient equilibrium systems and parent emissions in general, it does little to improve daughter emissions of secular equilibrium systems. Finally, hypotheses were presented as to why daughter emissions of secular equilibrium systems might be mispredicted in some cases and not in others.

  16. EDITORIAL: Incoming Editor-in-Chief

    NASA Astrophysics Data System (ADS)

    Webb, Steve

    2006-01-01

    Physics in Medicine and Biology (PMB) is a journal that originated in the UK but is now rightly regarded as one of the pre-eminent international journals for the publication of material coming within its remit. It is 50 years old and its maturity is an outcome of the consistent support of high performing authors, a supportive and professional publishing house, dedicated referees, many vigorous and conscientious editorial boards and the collective input of the 10 previous Editors as listed in his incoming editorial (January 2000 issue) by the retiring Editor, Professor Alun Beddoe. The scientific climate and it associated publication modus operandi in the 1950s was very different from that at the current time and the journal has evolved to reflect this. Hence today the scope of content is somewhat broader, the size of the journal is vastly greater, the whole publication process is slicker and more efficient and a paper in PMB is highly prized by its authors and those who look to quality factors and impact. The quality of the journal still relies on the voluntary labour and expertise of its busy international referees and Board members. For many years I have tried to place my own research material in PMB and encourage my teams to do likewise, not only acknowledging the prestige of the journal but also because of the extraordinarily fast turnaround time of all the processes without any loss of quality. This serves us very well and the publishing team are to be congratulated. Some things seem to change more slowly or not at all, however. The prediction, when I started my research career, that books and journals would be dinosaurs by now has manifestly not come true and, whilst most of us are addicted (and why not?) to the electronic ways of doing things that can be done by more traditional ways, PMB and a packet of reprints from time to time arriving by post still has a reassuring feel despite the fact that the papers have been `on-line' for a while before. An incoming

  17. Martin Stutzmann: Editor, Teacher, Scientist and Friend

    NASA Astrophysics Data System (ADS)

    Cardona, Manuel

    2005-02-01

    On 2 January 1995 Martin Stutzmann became Editor-in-Chief of physica status solidi, replacing Professor E. Gutsche, who had led the journal through the stormy period involving the fall of the Iron Curtain, the unification of Germany and the change in its Eastern part, where physica status solidi was based, from socialism as found in the real world (a German concept) to real world capitalism. In 1995 it was thought that the process had been completed (we should have known better!) and after the retirement of Prof. Gutsche the new owners of physica status solidi (Wiley-VCH) decided that a change in scientific management was desirable to adapt to the new socio-political facts and to insure the scientific continuity of the journal.Martin had moved in 1993 from my department at the Max-Planck-Institute to Munich where he soon displayed a tremendous amount of science man- agement ability during the build-up of the Walter Schottky Institute. The search for a successor as Edi- tor-in-Chief was not easy: the job was not very glamorous after the upheavals which had taken place in the editorial world following the political changes. Somebody in the Editorial Boards must have suggested Martin Stutzmann. I am sure that there was opposition: one usually looks for a well-established person ready to leave his direct involvement in science and take up a new endeavor of a more administrative nature. Nevertheless, the powers that be soon realized that Martin was an excellent, if somewhat unconventional candidate who had enough energy to remain a topnotch scientist and to lead the journal in the difficult times ahead: he was offered the job. In the negotiations that followed, he insisted in getting the administrative structures that would allow him to improve the battered quality of the journal and to continue his scientific productivity. Today we are happy to see that he succeeded in both endeavors. The journal has since grown in size and considerably improved its quality

  18. Editorial independence and the editor-owner relationship: good editors never die, they just cross the line.

    PubMed

    Lapeña, J F

    2009-12-01

    The concept of editorial freedom or independence is examined in the light of the editor-owner relationship. Like individual and national freedom or independence, it is a rhetorical concept whose realisation flows from internal achievement as much as it depends on external validation. This freedom entails roles and responsibilities embodied in specific codes of practice for editors, such as the guidelines espoused by the International Committee of Medical Journal Editors and the World Association of Medical Editors. The calling to embody these guidelines makes editing a vocation that demands isolation and distancing, separation and solitude. It involves bracketing one's biases, prejudgments and preconceptions. With such detachment comes real freedom; one that requires a moral fibre and trustworthiness that uphold truth and right, whether in full view of public scrutiny, or in the aloneness of private secrecy. The stereotypical tension between academic and commercial concerns highlights the editor-owner relationship, and bears directly on editorial independence. In practice, journal owners overstep their prerogatives. The absence of clear contracts defining editorial independence and the lack of established mechanisms governing the editor-owner relationship affect many small- to medium-sized journals in developing countries. Even large journals in developed and democratic nations or totalitarian states and societies are not spared. At the end of the day, editorial freedom exists only insofar as it is tolerated, or until editors cross the line. PMID:20087545

  19. Distributed visualization framework architecture

    NASA Astrophysics Data System (ADS)

    Mishchenko, Oleg; Raman, Sundaresan; Crawfis, Roger

    2010-01-01

    An architecture for distributed and collaborative visualization is presented. The design goals of the system are to create a lightweight, easy to use and extensible framework for reasearch in scientific visualization. The system provides both single user and collaborative distributed environment. System architecture employs a client-server model. Visualization projects can be synchronously accessed and modified from different client machines. We present a set of visualization use cases that illustrate the flexibility of our system. The framework provides a rich set of reusable components for creating new applications. These components make heavy use of leading design patterns. All components are based on the functionality of a small set of interfaces. This allows new components to be integrated seamlessly with little to no effort. All user input and higher-level control functionality interface with proxy objects supporting a concrete implementation of these interfaces. These light-weight objects can be easily streamed across the web and even integrated with smart clients running on a user's cell phone. The back-end is supported by concrete implementations wherever needed (for instance for rendering). A middle-tier manages any communication and synchronization with the proxy objects. In addition to the data components, we have developed several first-class GUI components for visualization. These include a layer compositor editor, a programmable shader editor, a material editor and various drawable editors. These GUI components interact strictly with the interfaces. Access to the various entities in the system is provided by an AssetManager. The asset manager keeps track of all of the registered proxies and responds to queries on the overall system. This allows all user components to be populated automatically. Hence if a new component is added that supports the IMaterial interface, any instances of this can be used in the various GUI components that work with this

  20. Validation of the MCNP-DSP Monte Carlo code for calculating source-driven noise parameters of subcritical systems

    SciTech Connect

    Valentine, T.E.; Mihalczo, J.T.

    1995-12-31

    This paper describes calculations performed to validate the modified version of the MCNP code, the MCNP-DSP, used for: the neutron and photon spectra of the spontaneous fission of californium 252; the representation of the detection processes for scattering detectors; the timing of the detection process; and the calculation of the frequency analysis parameters for the MCNP-DSP code.

  1. Horatio Alger in the Newsroom: Social Origins of American Editors

    ERIC Educational Resources Information Center

    Hart, Jack R.

    1976-01-01

    Concludes that American newspaper editors of the late nineteenth and early twentieth centuries came from elite social backgrounds, which is contrary to the rags-to-riches image fostered by previous historians. (RB)

  2. Flagrant Misconduct of Reviewers and Editor: A Case Study.

    PubMed

    Kotchoubey, Boris; Bütof, Sarah; Sitaram, Ranganatha

    2015-08-01

    A case of a particularly severe misbehavior in a review process is described. Two reviewers simply copied and pasted their critical comments from their previous reviews without reading the reviewed manuscript. The editor readily accepted the reviewers' opinion and rejected the manuscript. These facts give rise to some general questions about possible factors affecting the ethical behavior of reviewers and editors, as well as possible countermeasures to prevent ethical violations. PMID:25156788

  3. Addressing Fission Product Validation in MCNP Burnup Credit Criticality Calculations

    SciTech Connect

    Mueller, Don; Bowen, Douglas G; Marshall, William BJ J

    2015-01-01

    The US Nuclear Regulatory Commission (NRC) Division of Spent Fuel Storage and Transportation issued Interim Staff Guidance (ISG) 8, Revision 3 in September 2012. This ISG provides guidance for NRC staff members’ review of burnup credit (BUC) analyses supporting transport and dry storage of pressurized water reactor spent nuclear fuel (SNF) in casks. The ISG includes guidance for addressing validation of criticality (keff) calculations crediting the presence of a limited set of fission products and minor actinides (FP&MAs). Based on previous work documented in NRC Regulatory Guide (NUREG) Contractor Report (CR)-7109, the ISG recommends that NRC staff members accept the use of either 1.5 or 3% of the FP&MA worth—in addition to bias and bias uncertainty resulting from validation of keff calculations for the major actinides in SNF—to conservatively account for the bias and bias uncertainty associated with the specified unvalidated FP&MAs. The ISG recommends (1) use of 1.5% of the FP&MA worth if a modern version of SCALE and its nuclear data are used and (2) 3% of the FP&MA worth for well qualified, industry standard code systems other than SCALE with the Evaluated Nuclear Data Files, Part B (ENDF/B),-V, ENDF/B-VI, or ENDF/B-VII cross sections libraries. The work presented in this paper provides a basis for extending the use of the 1.5% of the FP&MA worth bias to BUC criticality calculations performed using the Monte Carlo N-Particle (MCNP) code. The extended use of the 1.5% FP&MA worth bias is shown to be acceptable by comparison of FP&MA worths calculated using SCALE and MCNP with ENDF/B-V, -VI, and -VII–based nuclear data. The comparison supports use of the 1.5% FP&MA worth bias when the MCNP code is used for criticality calculations, provided that the cask design is similar to the hypothetical generic BUC-32 cask model and that the credited FP&MA worth is no more than 0.1 Δkeff (ISG-8, Rev. 3, Recommendation 4).

  4. ZED- A LINE EDITOR FOR THE DEC VAX

    NASA Technical Reports Server (NTRS)

    Scott, P. J.

    1994-01-01

    The ZED editor for the DEC VAX is a simple, yet powerful line editor for text, program source code, and non-binary data. Line editors can be superior to screen editors in some cases, such as executing complex multiple or conditional commands, or editing via slow modem lines. ZED excels in the area of text processing by using procedure files. For example, such procedures can reformat a file of addresses or remove all comment lines from a FORTRAN program. In addition to command files, ZED also features versatile search qualifiers, global changes, conditionals, on-line help, hexadecimal mode, space compression, looping, logical combinations of search strings, journaling, visible control characters, and automatic detabbing. The ZED editor was originally developed at Cambridge University in London and has been continuously enhanced since 1976. Users of the Cambridge implementation have devised such elaborate ZED procedures as chess games, calculators, and programs for evaluating Pi. This implementation of ZED strives to maintain the characteristics of the Cambridge editor. A complete ZED manual is included on the tape. ZED is written entirely in C for either batch or interactive execution on the DEC VAX under VMS 4.X and requires 80,896 bytes of memory. This program was released in 1988 and updated in 1989.

  5. Experimental validation of lead cross sections for scale and MCNP

    SciTech Connect

    Henrikson, D.J.

    1995-12-01

    Moving spent nuclear fuel between facilities often requires the use of lead-shielded casks. Criticality safety that is based upon calculations requires experimental validation of the fuel matrix and lead cross section libraries. A series of critical experiments using a high-enriched uranium-aluminum fuel element with a variety of reflectors, including lead, has been identified. Twenty-one configurations were evaluated in this study. The fuel element was modelled for KENO V.a and MCNP 4a using various cross section sets. The experiments addressed in this report can be used to validate lead-reflected calculations. Factors influencing calculated k{sub eff} which require further study include diameters of styrofoam inserts and homogenization.

  6. MCNP simulation of a Theratron 780 radiotherapy unit.

    PubMed

    Miró, R; Soler, J; Gallardo, S; Campayo, J M; Díez, S; Verdú, G

    2005-01-01

    A Theratron 780 (MDS Nordion) 60Co radiotherapy unit has been simulated with the Monte Carlo code MCNP. The unit has been realistically modelled: the cylindrical source capsule and its housing, the rectangular collimator system, both the primary and secondary jaws and the air gaps between the components. Different collimator openings, ranging from 5 x 5 cm2 to 20 x 20 cm2 (narrow and broad beams) at a source-surface distance equal to 80 cm have been used during the study. In the present work, we have calculated spectra as a function of field size. A study of the variation of the electron contamination of the 60Co beam has also been performed. PMID:16604598

  7. Fuel Element Transfer Cask Modelling Using MCNP Technique

    NASA Astrophysics Data System (ADS)

    Darmawan, Rosli; Topah, Budiman Naim

    2010-01-01

    After operating for more than 25 years, some of the Reaktor TRIGA Puspati (RTP) fuel elements would have been depleted. A few addition and fuel reconfiguration exercises have to be conducted in order to maintain RTP capacity. Presently, RTP spent fuels are stored at the storage area inside RTP tank. The need to transfer the fuel element outside of RTP tank may be prevalence in the near future. The preparation shall be started from now. A fuel element transfer cask has been designed according to the recommendation by the fuel manufacturer and experience of other countries. A modelling using MCNP code has been conducted to analyse the design. The result shows that the design of transfer cask fuel element is safe for handling outside the RTP tank according to recent regulatory requirement.

  8. Fuel Element Transfer Cask Modelling Using MCNP Technique

    SciTech Connect

    Darmawan, Rosli; Topah, Budiman Naim

    2010-01-05

    After operating for more than 25 years, some of the Reaktor TRIGA Puspati (RTP) fuel elements would have been depleted. A few addition and fuel reconfiguration exercises have to be conducted in order to maintain RTP capacity. Presently, RTP spent fuels are stored at the storage area inside RTP tank. The need to transfer the fuel element outside of RTP tank may be prevalence in the near future. The preparation shall be started from now. A fuel element transfer cask has been designed according to the recommendation by the fuel manufacturer and experience of other countries. A modelling using MCNP code has been conducted to analyse the design. The result shows that the design of transfer cask fuel element is safe for handling outside the RTP tank according to recent regulatory requirement.

  9. Treating electron transport in MCNP{sup trademark}

    SciTech Connect

    Hughes, H.G.

    1996-12-31

    The transport of electrons and other charged particles is fundamentally different from that of neutrons and photons. A neutron, in aluminum slowing down from 0.5 MeV to 0.0625 MeV will have about 30 collisions; a photon will have fewer than ten. An electron with the same energy loss will undergo 10{sup 5} individual interactions. This great increase in computational complexity makes a single- collision Monte Carlo approach to electron transport unfeasible for many situations of practical interest. Considerable theoretical work has been done to develop a variety of analytic and semi-analytic multiple-scattering theories for the transport of charged particles. The theories used in the algorithms in MCNP are the Goudsmit-Saunderson theory for angular deflections, the Landau an theory of energy-loss fluctuations, and the Blunck-Leisegang enhancements of the Landau theory. In order to follow an electron through a significant energy loss, it is necessary to break the electron`s path into many steps. These steps are chosen to be long enough to encompass many collisions (so that multiple-scattering theories are valid) but short enough that the mean energy loss in any one step is small (for the approximations in the multiple-scattering theories). The energy loss and angular deflection of the electron during each step can then be sampled from probability distributions based on the appropriate multiple- scattering theories. This subsumption of the effects of many individual collisions into single steps that are sampled probabilistically constitutes the ``condensed history`` Monte Carlo method. This method is exemplified in the ETRAN series of electron/photon transport codes. The ETRAN codes are also the basis for the Integrated TIGER Series, a system of general-purpose, application-oriented electron/photon transport codes. The electron physics in MCNP is similar to that of the Integrated TIGER Series.

  10. Comparisons between MCNP, EGS4 and experiment for clinical electron beams.

    PubMed

    Jeraj, R; Keall, P J; Ostwald, P M

    1999-03-01

    Understanding the limitations of Monte Carlo codes is essential in order to avoid systematic errors in simulations, and to suggest further improvement of the codes. MCNP and EGS4, Monte Carlo codes commonly used in medical physics, were compared and evaluated against electron depth dose data and experimental backscatter results obtained using clinical radiotherapy beams. Different physical models and algorithms used in the codes give significantly different depth dose curves and electron backscattering factors. The default version of MCNP calculates electron depth dose curves which are too penetrating. The MCNP results agree better with experiment if the ITS-style energy-indexing algorithm is used. EGS4 underpredicts electron backscattering for high-Z materials. The results slightly improve if optimal PRESTA-I parameters are used. MCNP simulates backscattering well even for high-Z materials. To conclude the comparison, a timing study was performed. EGS4 is generally faster than MCNP and use of a large number of scoring voxels dramatically slows down the MCNP calculation. However, use of a large number of geometry voxels in MCNP only slightly affects the speed of the calculation. PMID:10211804

  11. Performance upgrades to the MCNP6 burnup capability for large scale depletion calculations

    DOE PAGESBeta

    Fensin, M. L.; Galloway, J. D.; James, M. R.

    2015-04-11

    The first MCNP based inline Monte Carlo depletion capability was officially released from the Radiation Safety Information and Computational Center as MCNPX 2.6.0. With the merger of MCNPX and MCNP5, MCNP6 combined the capability of both simulation tools, as well as providing new advanced technology, in a single radiation transport code. The new MCNP6 depletion capability was first showcased at the International Congress for Advancements in Nuclear Power Plants (ICAPP) meeting in 2012. At that conference the new capabilities addressed included the combined distributive and shared memory parallel architecture for the burnup capability, improved memory management, physics enhancements, and newmore » predictability as compared to the H.B Robinson Benchmark. At Los Alamos National Laboratory, a special purpose cluster named “tebow,” was constructed such to maximize available RAM per CPU, as well as leveraging swap space with solid state hard drives, to allow larger scale depletion calculations (allowing for significantly more burnable regions than previously examined). As the MCNP6 burnup capability was scaled to larger numbers of burnable regions, a noticeable slowdown was realized.This paper details two specific computational performance strategies for improving calculation speedup: (1) retrieving cross sections during transport; and (2) tallying mechanisms specific to burnup in MCNP. To combat this slowdown new performance upgrades were developed and integrated into MCNP6 1.2.« less

  12. Performance upgrades to the MCNP6 burnup capability for large scale depletion calculations

    SciTech Connect

    Fensin, M. L.; Galloway, J. D.; James, M. R.

    2015-04-11

    The first MCNP based inline Monte Carlo depletion capability was officially released from the Radiation Safety Information and Computational Center as MCNPX 2.6.0. With the merger of MCNPX and MCNP5, MCNP6 combined the capability of both simulation tools, as well as providing new advanced technology, in a single radiation transport code. The new MCNP6 depletion capability was first showcased at the International Congress for Advancements in Nuclear Power Plants (ICAPP) meeting in 2012. At that conference the new capabilities addressed included the combined distributive and shared memory parallel architecture for the burnup capability, improved memory management, physics enhancements, and new predictability as compared to the H.B Robinson Benchmark. At Los Alamos National Laboratory, a special purpose cluster named “tebow,” was constructed such to maximize available RAM per CPU, as well as leveraging swap space with solid state hard drives, to allow larger scale depletion calculations (allowing for significantly more burnable regions than previously examined). As the MCNP6 burnup capability was scaled to larger numbers of burnable regions, a noticeable slowdown was realized.This paper details two specific computational performance strategies for improving calculation speedup: (1) retrieving cross sections during transport; and (2) tallying mechanisms specific to burnup in MCNP. To combat this slowdown new performance upgrades were developed and integrated into MCNP6 1.2.

  13. An enhanced geometry-independent mesh weight window generator for MCNP

    SciTech Connect

    Evans, T.M.; Hendricks, J.S.

    1997-12-31

    A new, enhanced, weight window generator suite has been developed for MCNP{trademark}. The new generator correctly estimates importances in either an user-specified, geometry-independent orthogonal grid or in MCNP geometric cells. The geometry-independent option alleviates the need to subdivide the MCNP cell geometry for variance reduction purposes. In addition, the new suite corrects several pathologies in the existing MCNP weight window generator. To verify the correctness of the new implementation, comparisons are performed with the analytical solution for the cell importance. Using the new generator, differences between Monte Carlo generated and analytical importances are less than 0.1%. Also, assumptions implicit in the original MCNP generator are shown to be poor in problems with high scattering media. The new generator is fully compatible with MCNP`s AVATAR{trademark} automatic variance reduction method. The new generator applications, together with AVATAR, gives MCNP an enhanced suite of variance reduction methods. The flexibility and efficacy of this suite is demonstrated in a neutron porosity tool well-logging problem.

  14. MCNP(TM) Release 6.1.1 beta: Creating and Testing the Code Distribution

    SciTech Connect

    Cox, Lawrence J.; Casswell, Laura

    2014-06-12

    This report documents the preparations for and testing of the production release of MCNP6™1.1 beta through RSICC at ORNL. It addresses tests on supported operating systems (Linux, MacOSX, Windows) with the supported compilers (Intel, Portland Group and gfortran). Verification and Validation test results are documented elsewhere. This report does not address in detail the overall packaging of the distribution. Specifically, it does not address the nuclear and atomic data collection, the other included software packages (MCNP5, MCNPX and MCNP6) and the collection of reference documents.

  15. Impact of MCNP unresolved resonance probability-table treatment on {sup 233}U benchmarks

    SciTech Connect

    Mosteller, R.D.

    1999-06-01

    Previous versions of the MCNP Monte Carlo code, up through and including MCNP4B, have not accurately modeled neutron self-shielding effects in the unresolved resonance energy region. Recently, a probability-table treatment has been incorporated into an intermediate version called MCNP4XS, and compatible continuous-energy cross-section libraries have been developed for 27 different isotopes. Preliminary results for a variety of uranium and plutonium benchmarks have been presented previously, and this paper extends those results to include several {sup 233}U benchmarks. The objective of the current study is to assess the reactivity impact of the probability-table treatment on {sup 233}U systems.

  16. Impact of MCNP Unresolved Resonance Probability-Table Treatment on Uranium and Plutonium Benchmarks

    SciTech Connect

    Mosteller, R.D.; Little, R.C.

    1999-09-20

    A probability-table treatment recently has been incorporated into an intermediate version of the MCNP Monte Carlo code named MCNP4XS. This paper presents MCNP4XS results for a variety of uranium and plutonium criticality benchmarks, calculated with and without the probability-table treatment. It is shown that the probability-table treatment can produce small but significant reactivity changes for plutonium and {sup 233}U systems with intermediate spectra. More importantly, it can produce substantial reactivity increases for systems with large amounts of {sup 238}U and intermediate spectra.

  17. EDITORIAL: Incoming Editor-in-Chief Incoming Editor-in-Chief

    NASA Astrophysics Data System (ADS)

    Birch, David

    2012-01-01

    It is a pleasure and an honour for me to be taking over as Editor-in-Chief of Measurement Science and Technology. MST is well known across research communities worldwide as a leading journal in which to publish new techniques and instrumentation. It has gained this enviable position largely because of the excellent guidance of its Editorial Board and dedicated staff at Institute of Physics Publishing over many years. I want to highlight in particular the contribution of the outgoing Editor Peter Hauptmann, and other Editors before him, in making the journal truly international. We thank Peter immensely for all his hard work in leading the journal, having exceptionally served two terms, each of five years. I come into the post of Editor at a very interesting and challenging time for research. The global recession is leading to cuts in research funding in many countries, researchers and their outputs are coming under closer scrutiny than ever before, and more is being expected of them. Journals play a critical role in monitoring and maintaining research standards, but we should be careful not to assume that journal Impact Factor is the sole measure of research quality. Although expediency may sometimes demand it, Impact Factor, as practitioners know, is subject dependent. One of the great things about science and technology for me is its level playing field. The key point is still innovation no matter where the work is done or where it is published. MST has a long pedigree of being the natural home of the highest quality papers from leading researchers wishing to report novel instrumentation and techniques. 2013 will mark the 90th anniversary of MST and we look forward to celebrating in style its sustained success. I recall with pride the first paper I published in Journal of Physics E: Scientific Instruments (as MST was previously titled) back in 1977. The paper reported the design and application of an early fluorescence lifetime spectrometer that I had constructed

  18. A Patch to MCNP5 for Multiplication Inference: Description and User Guide

    SciTech Connect

    Solomon, Jr., Clell J.

    2014-05-05

    A patch to MCNP5 has been written to allow generation of multiple neutrons from a spontaneous-fission event and generate list-mode output. This report documents the implementation and usage of this patch.

  19. Current status of MCNP6 as a simulation tool useful for space and accelerator applications

    SciTech Connect

    Mashnik, Stepan G; Bull, Jeffrey S; Hughes, H. Grady; Prael, Richard E; Sierk, Arnold J

    2012-07-20

    For the past several years, a major effort has been undertaken at Los Alamos National Laboratory (LANL) to develop the transport code MCNP6, the latest LANL Monte-Carlo transport code representing a merger and improvement of MCNP5 and MCNPX. We emphasize a description of the latest developments of MCNP6 at higher energies to improve its reliability in calculating rare-isotope production, high-energy cumulative particle production, and a gamut of reactions important for space-radiation shielding, cosmic-ray propagation, and accelerator applications. We present several examples of validation and verification of MCNP6 compared to a wide variety of intermediate- and high-energy experimental data on reactions induced by photons, mesons, nucleons, and nuclei at energies from tens of MeV to about 1 TeV/nucleon, and compare to results from other modern simulation tools.

  20. Comparisons of TORT and MCNP dose calculations for BNCT treatment planning

    SciTech Connect

    Ingersol, D.T.; Slater, C.O.; Williams, L.R.; Redmond, E.L., II; Zamenhof, R.G.

    1996-12-31

    The relative merit of using a deterministic code to calculate dose distributions for BNCT applications were examined. The TORT discrete deterministic ordinated code was used in comparison to MCNP4A to calculate dose distributions for BNCT applications

  1. SIRE: A Simple Interactive Rule Editor for NICBES

    NASA Astrophysics Data System (ADS)

    Bykat, Alex

    1988-12-01

    To support evolution of domain expertise, and its representation in an expert system knowledge base, a user-friendly rule base editor is mandatory. The Nickel Cadmium Battery Expert System (NICBES), a prototype of an expert system for the Hubble Space Telescope power storage management system, does not provide such an editor. In the following, a description of a Simple Interactive Rule Base Editor (SIRE) for NICBES is described. The SIRE provides a consistent internal representation of the NICBES knowledge base. It supports knowledge presentation and provides a user-friendly and code language independent medium for rule addition and modification. The SIRE is integrated with NICBES via an interface module. This module provides translation of the internal representation to Prolog-type rules (Horn clauses), latter rule assertion, and a simple mechanism for rule selection for its Prolog inference engine.

  2. Writing filter processes for the SAGA editor, appendix G

    NASA Technical Reports Server (NTRS)

    Kirslis, Peter A.

    1985-01-01

    The SAGA editor provides a mechanism by which separate processes can be invoked during an editing session to traverse portions of the parse tree being edited. These processes, termed filter processes, read, analyze, and possibly transform the parse tree, returning the result to the editor. By defining new commands with the editor's user defined command facility, which invoke filter processes, authors of filter can provide complex operations as simple commands. A tree plotter, pretty printer, and Pascal tree transformation program were already written using this facility. The filter processes are introduced, parse tree structure is described and the library interface made available to the programmer. Also discussed is how to compile and run filter processes. Examples are presented to illustrate aspect of each of these areas.

  3. SIRE: A Simple Interactive Rule Editor for NICBES

    NASA Technical Reports Server (NTRS)

    Bykat, Alex

    1988-01-01

    To support evolution of domain expertise, and its representation in an expert system knowledge base, a user-friendly rule base editor is mandatory. The Nickel Cadmium Battery Expert System (NICBES), a prototype of an expert system for the Hubble Space Telescope power storage management system, does not provide such an editor. In the following, a description of a Simple Interactive Rule Base Editor (SIRE) for NICBES is described. The SIRE provides a consistent internal representation of the NICBES knowledge base. It supports knowledge presentation and provides a user-friendly and code language independent medium for rule addition and modification. The SIRE is integrated with NICBES via an interface module. This module provides translation of the internal representation to Prolog-type rules (Horn clauses), latter rule assertion, and a simple mechanism for rule selection for its Prolog inference engine.

  4. Analysis of JSI TRIGA MARK II reactor physical parameters calculated with TRIPOLI and MCNP.

    PubMed

    Henry, R; Tiselj, I; Snoj, L

    2015-03-01

    New computational model of the JSI TRIGA Mark II research reactor was built for TRIPOLI computer code and compared with existing MCNP code model. The same modelling assumptions were used in order to check the differences of the mathematical models of both Monte Carlo codes. Differences between the TRIPOLI and MCNP predictions of keff were up to 100pcm. Further validation was performed with analyses of the normalized reaction rates and computations of kinetic parameters for various core configurations. PMID:25576735

  5. Methodology, verification, and performance of the continuous-energy nuclear data sensitivity capability in MCNP6

    SciTech Connect

    Kiedrowski, B. C.; Brown, F. B.

    2013-07-01

    A continuous-energy sensitivity coefficient capability has been introduced into MCNP6. The methods for generating energy-resolved and energy-integrated sensitivity profiles are discussed. Results from the verification exercises that were performed are given, and these show that MCNP6 compares favorably with analytic solutions, direct density perturbations, and comparisons to TSUNAMI-3D and MONK. Run-time and memory requirements are assessed for typical applications, and these are shown to be reasonable with modern computing resources. (authors)

  6. Validating MCNP for LEU Fuel Design via Power Distribution Comparisons

    SciTech Connect

    Primm, Trent; Maldonado, G Ivan; Chandler, David

    2008-11-01

    The mission of the Reduced Enrichment for Research and Test Reactors (RERTR) Program is to minimize and, to the extent possible, eliminate the use of highly enriched uranium (HEU) in civilian nuclear applications by working to convert research and test reactors, as well as radioisotope production processes, to low enriched uranium (LEU) fuel and targets. Oak Ridge National Lab (ORNL) is reviewing the design bases and key operating criteria including fuel operating parameters, enrichment-related safety analyses, fuel performance, and fuel fabrication in regard to converting the fuel of the High Flux Isotope Reactor (HFIR) from HEU to LEU. The purpose of this study is to validate Monte Carlo methods currently in use for conversion analyses. The methods have been validated for the prediction of flux values in the reactor target, reflector, and beam tubes, but this study focuses on the prediction of the power density profile in the core. A current 3-D Monte Carlo N-Particle (MCNP) model was modified to replicate the HFIR Critical Experiment 3 (HFIRCE-3) core of 1965. In this experiment, the power profile was determined by counting the gamma activity at selected locations in the core. Foils (chunks of fuel meat and clad) were punched out of the fuel elements in HFIRCE-3 following irradiation and experimental relative power densities were obtained by measuring the activity of these foils and comparing each foil s activity to the activity of a normalizing foil. The current work consisted of calculating corresponding activities by inserting volume tallies into the modified MCNP model to represent the punchings. The average fission density was calculated for each foil location and then normalized to the normalizing foil. Power distributions were obtained for the clean core (no poison in moderator and symmetrical rod position at 17.5 inches) and fully poisoned-moderator (1.35 g B/liter in moderator and rods fully withdrawn) conditions. The observed deviations between the

  7. MCNP-based computational model for the Leksell Gamma Knife

    SciTech Connect

    Trnka, Jiri; Novotny, Josef Jr.; Kluson, Jaroslav

    2007-01-15

    We have focused on the usage of MCNP code for calculation of Gamma Knife radiation field parameters with a homogenous polystyrene phantom. We have investigated several parameters of the Leksell Gamma Knife radiation field and compared the results with other studies based on EGS4 and PENELOPE code as well as the Leksell Gamma Knife treatment planning system Leksell GammaPlan (LGP). The current model describes all 201 radiation beams together and simulates all the sources in the same time. Within each beam, it considers the technical construction of the source, the source holder, collimator system, the spherical phantom, and surrounding material. We have calculated output factors for various sizes of scoring volumes, relative dose distributions along basic planes including linear dose profiles, integral doses in various volumes, and differential dose volume histograms. All the parameters have been calculated for each collimator size and for the isocentric configuration of the phantom. We have found the calculated output factors to be in agreement with other authors' works except the case of 4 mm collimator size, where averaging over the scoring volume and statistical uncertainties strongly influences the calculated results. In general, all the results are dependent on the choice of the scoring volume. The calculated linear dose profiles and relative dose distributions also match independent studies and the Leksell GammaPlan, but care must be taken about the fluctuations within the plateau, which can influence the normalization, and accuracy in determining the isocenter position, which is important for comparing different dose profiles. The calculated differential dose volume histograms and integral doses have been compared with data provided by the Leksell GammaPlan. The dose volume histograms are in good agreement as well as integral doses calculated in small calculation matrix volumes. However, deviations in integral doses up to 50% can be observed for large

  8. MCNP-based computational model for the Leksell gamma knife.

    PubMed

    Trnka, Jiri; Novotny, Josef; Kluson, Jaroslav

    2007-01-01

    We have focused on the usage of MCNP code for calculation of Gamma Knife radiation field parameters with a homogenous polystyrene phantom. We have investigated several parameters of the Leksell Gamma Knife radiation field and compared the results with other studies based on EGS4 and PENELOPE code as well as the Leksell Gamma Knife treatment planning system Leksell GammaPlan (LGP). The current model describes all 201 radiation beams together and simulates all the sources in the same time. Within each beam, it considers the technical construction of the source, the source holder, collimator system, the spherical phantom, and surrounding material. We have calculated output factors for various sizes of scoring volumes, relative dose distributions along basic planes including linear dose profiles, integral doses in various volumes, and differential dose volume histograms. All the parameters have been calculated for each collimator size and for the isocentric configuration of the phantom. We have found the calculated output factors to be in agreement with other authors' works except the case of 4 mm collimator size, where averaging over the scoring volume and statistical uncertainties strongly influences the calculated results. In general, all the results are dependent on the choice of the scoring volume. The calculated linear dose profiles and relative dose distributions also match independent studies and the Leksell GammaPlan, but care must be taken about the fluctuations within the plateau, which can influence the normalization, and accuracy in determining the isocenter position, which is important for comparing different dose profiles. The calculated differential dose volume histograms and integral doses have been compared with data provided by the Leksell GammaPlan. The dose volume histograms are in good agreement as well as integral doses calculated in small calculation matrix volumes. However, deviations in integral doses up to 50% can be observed for large

  9. MCNP6 Simulation of Light and Medium Nuclei Fragmentation at Intermediate Energies

    SciTech Connect

    Mashnik, Stepan Georgievich; Kerby, Leslie Marie

    2015-05-22

    MCNP6, the latest and most advanced LANL Monte Carlo transport code, representing a merger of MCNP5 and MCNPX, is actually much more than the sum of those two computer codes; MCNP6 is available to the public via RSICC at Oak Ridge, TN, USA. In the present work, MCNP6 was validated and verified (V&V) against different experimental data on intermediate-energy fragmentation reactions, and results by several other codes, using mainly the latest modifications of the Cascade-Exciton Model (CEM) and of the Los Alamos version of the Quark-Gluon String Model (LAQGSM) event generators CEM03.03 and LAQGSM03.03. It was found that MCNP6 using CEM03.03 and LAQGSM03.03 describes well fragmentation reactions induced on light and medium target nuclei by protons and light nuclei of energies around 1 GeV/nucleon and below, and can serve as a reliable simulation tool for different applications, like cosmic-ray-induced single event upsets (SEU’s), radiation protection, and cancer therapy with proton and ion beams, to name just a few. Future improvements of the predicting capabilities of MCNP6 for such reactions are possible, and are discussed in this work.

  10. Validation and verification of MCNP6 as a new simulation tool useful for medical applications

    SciTech Connect

    Mashnik, Stepan G

    2011-01-06

    MCNP6, the latest and most advanced LANL transport code, representing a merger of MCNP5 and MCNPX has been Validated and Verified (V&V) against different experimental data and results by other codes relevant to medical applications. In the present work, we V&V MCNP6 using mainly the latest modifications of the Cascade-Exciton Model (CEM) and of the Los Alamos version of the Quark-Gluon String Model (LAQGSM) event generators CEM03.02 and LAQGSM03.03. We found that MCNP6 describes well data of interest for medical applications measured on both thin and thick targets and agrees very well with similar results obtained with other codes; MCNP6 may be a very useful tool for medical applications We plan to make MCNP6 available to the public via RSICC at Oak Ridge in the middle of 2011 but we are allowed to provide it to friendly US Beta-users outside LANL already now.

  11. Verification of Unstructured Mesh Capabilities in MCNP6 for Reactor Physics Problems

    SciTech Connect

    Burke, Timothy P.; Martz, Roger L.; Kiedrowski, Brian C.; Martin, William R.

    2012-08-22

    New unstructured mesh capabilities in MCNP6 (developmental version during summer 2012) show potential for conducting multi-physics analyses by coupling MCNP to a finite element solver such as Abaqus/CAE[2]. Before these new capabilities can be utilized, the ability of MCNP to accurately estimate eigenvalues and pin powers using an unstructured mesh must first be verified. Previous work to verify the unstructured mesh capabilities in MCNP was accomplished using the Godiva sphere [1], and this work attempts to build on that. To accomplish this, a criticality benchmark and a fuel assembly benchmark were used for calculations in MCNP using both the Constructive Solid Geometry (CSG) native to MCNP and the unstructured mesh geometry generated using Abaqus/CAE. The Big Ten criticality benchmark [3] was modeled due to its geometry being similar to that of a reactor fuel pin. The C5G7 3-D Mixed Oxide (MOX) Fuel Assembly Benchmark [4] was modeled to test the unstructured mesh capabilities on a reactor-type problem.

  12. Ethics and the psychiatry journal editor: responsibilities and dilemmas.

    PubMed

    Greenberg, David; D Strous, Rael

    2014-01-01

    An array of potential ethical stumbling blocks awaits the editors of scientific journals. There are issues of particular relevance to mental health journals, and others unique to local journals with a relatively small circulation and low impact factor. The blind review system, conflict of interests, redundant publication, fraud and plagiarism, guest and ghost authorship and ghost writing, advertising, language and stigma, patient consent, and "rigging" the Impact Factor are all issues of importance. It is critical that editors are aware and informed of these important issues, and have an accessible forum for evaluating problems as they arise. PMID:25618285

  13. EDITORIAL: New Editor-in-Chief for Nanotechnology New Editor-in-Chief for Nanotechnology

    NASA Astrophysics Data System (ADS)

    Couzin, Nina

    2009-01-01

    Nanotechnology is proud to announce the appointment of Professor Mark Reed, Yale University, as the new Editor-in-Chief from January 2009. Mark Reed holds the Harold Hodgkinson Chair of Engineering and Applied Science at Yale University. He has made significant contributions in the areas of quantum dots, electronic transport in nanoscale and mesoscopic systems, artificially structured materials and devices, and molecular electronics. Professor Reed has been associated with the journal as an Editorial Board member for a number of years and we are delighted that he has agreed to take on the scientific leadership of the journal in its 20th year. We also take the opportunity to thank Professor Mark Welland, Cambridge University, for his work as Editor-in-Chief since 2001, and for presiding over the re-launch and remarkable growth of the journal since then. Nanotechnology is unique in that it was the first peer-reviewed journal in the area of nanoscience, the first issue appearing in 1990. Since then it has established a distinguished publication record and has become a leading journal covering all aspects of nanoscale science and technology, as well as specializing in in-depth, comprehensive articles not seen in letter format journals. Published weekly and featuring subject sections, the journal is truly multidisciplinary in nature and is an excellent medium to quickly deliver your research results to readers worldwide. Nanotechnology is proud to be offering some of the fastest publication times around (less than three months on average from receipt to online publication). We offer free online access to all published papers for 30 days, ensuring that anyone with access to the internet will be able to read your paper. We were also the first journal to give our authors the opportunity to communicate their research to a wider audience through nanotechweb.org and other IOP websites. See the journal's homepage at www.iop.org/Journals/nano for more details. We are looking

  14. Martin Stutzmann: Editor, Teacher, Scientist and Friend

    NASA Astrophysics Data System (ADS)

    Cardona, Manuel

    2005-02-01

    On 2 January 1995 Martin Stutzmann became Editor-in-Chief of physica status solidi, replacing Professor E. Gutsche, who had led the journal through the stormy period involving the fall of the Iron Curtain, the unification of Germany and the change in its Eastern part, where physica status solidi was based, from socialism as found in the real world (a German concept) to real world capitalism. In 1995 it was thought that the process had been completed (we should have known better!) and after the retirement of Prof. Gutsche the new owners of physica status solidi (Wiley-VCH) decided that a change in scientific management was desirable to adapt to the new socio-political facts and to insure the scientific continuity of the journal.Martin had moved in 1993 from my department at the Max-Planck-Institute to Munich where he soon displayed a tremendous amount of science man- agement ability during the build-up of the Walter Schottky Institute. The search for a successor as Edi- tor-in-Chief was not easy: the job was not very glamorous after the upheavals which had taken place in the editorial world following the political changes. Somebody in the Editorial Boards must have suggested Martin Stutzmann. I am sure that there was opposition: one usually looks for a well-established person ready to leave his direct involvement in science and take up a new endeavor of a more administrative nature. Nevertheless, the powers that be soon realized that Martin was an excellent, if somewhat unconventional candidate who had enough energy to remain a topnotch scientist and to lead the journal in the difficult times ahead: he was offered the job. In the negotiations that followed, he insisted in getting the administrative structures that would allow him to improve the battered quality of the journal and to continue his scientific productivity. Today we are happy to see that he succeeded in both endeavors. The journal has since grown in size and considerably improved its quality

  15. Martin Stutzmann: Editor, Teacher, Scientist and Friend

    NASA Astrophysics Data System (ADS)

    Cardona, Manuel

    2005-03-01

    On 2 January 1995 Martin Stutzmann became Editor-in-Chief of physica status solidi, replacing Professor E. Gutsche, who had led the journal through the stormy period involving the fall of the Iron Curtain, the unification of Germany and the change in its Eastern part, where physica status solidi was based, from socialism as found in the real world (a German concept) to real world capitalism. In 1995 it was thought that the process had been completed (we should have known better!) and after the retirement of Prof. Gutsche the new owners of physica status solidi (Wiley-VCH) decided that a change in scientific management was desirable to adapt to the new socio-political facts and to insure the scientific continuity of the journal.Martin had moved in 1993 from my department at the Max-Planck-Institute to Munich where he soon displayed a tremendous amount of science man- agement ability during the build-up of the Walter Schottky Institute. The search for a successor as Edi- tor-in-Chief was not easy: the job was not very glamorous after the upheavals which had taken place in the editorial world following the political changes. Somebody in the Editorial Boards must have suggested Martin Stutzmann. I am sure that there was opposition: one usually looks for a well-established person ready to leave his direct involvement in science and take up a new endeavor of a more administrative nature. Nevertheless, the powers that be soon realized that Martin was an excellent, if somewhat unconventional candidate who had enough energy to remain a topnotch scientist and to lead the journal in the difficult times ahead: he was offered the job. In the negotiations that followed, he insisted in getting the administrative structures that would allow him to improve the battered quality of the journal and to continue his scientific productivity. Today we are happy to see that he succeeded in both endeavors. The journal has since grown in size and considerably improved its quality

  16. IER-163 Post-Experiment MCNP Calculations (U)

    SciTech Connect

    Favorite, Jeffrey A.

    2012-06-04

    IER-163 has been modeled with high fidelity in MCNP6. The model k{sub eff} was high, as in other similar calculations. The fission ratio {sup 238}U(n,f)/{sup 235}U(n,f) was 12.6% too small compared with measurements; the ratio {sup 239}Pu(n,f)/{sup 235}U(n,f) was 11.5% too small compared with measurements; the iridium ratio {sup 193}Ir(n,n{prime})/{sup 191}Ir(n,{gamma}) was 16.4% too large; and the gold ratios {sup 197}Au(n,2n)/{sup 197}Au(n,{gamma}), {sup 197}Au(n,2n)/{sup 235}U(n,f), and {sup 197}Au(n,{gamma})/{sup 235}U(n,f) were within one standard deviation of the measured values. It is suggested that the calculated {sup 235}U fission rate is too large and the calculated {sup 238}U fission rate is too small.

  17. Automated variance reduction for Monte Carlo shielding analyses with MCNP

    NASA Astrophysics Data System (ADS)

    Radulescu, Georgeta

    Variance reduction techniques are employed in Monte Carlo analyses to increase the number of particles in the space phase of interest and thereby lower the variance of statistical estimation. Variance reduction parameters are required to perform Monte Carlo calculations. It is well known that adjoint solutions, even approximate ones, are excellent biasing functions that can significantly increase the efficiency of a Monte Carlo calculation. In this study, an automated method of generating Monte Carlo variance reduction parameters, and of implementing the source energy biasing and the weight window technique in MCNP shielding calculations has been developed. The method is based on the approach used in the SAS4 module of the SCALE code system, which derives the biasing parameters from an adjoint one-dimensional Discrete Ordinates calculation. Unlike SAS4 that determines the radial and axial dose rates of a spent fuel cask in separate calculations, the present method provides energy and spatial biasing parameters for the entire system that optimize the simulation of particle transport towards all external surfaces of a spent fuel cask. The energy and spatial biasing parameters are synthesized from the adjoint fluxes of three one-dimensional Discrete Ordinates adjoint calculations. Additionally, the present method accommodates multiple source regions, such as the photon sources in light-water reactor spent nuclear fuel assemblies, in one calculation. With this automated method, detailed and accurate dose rate maps for photons, neutrons, and secondary photons outside spent fuel casks or other containers can be efficiently determined with minimal efforts.

  18. Fission matrix capability for MCNP, Part I - Theory

    SciTech Connect

    Brown, F. B.; Carney, S. E.; Kiedrowski, B. C.; Martin, W. R.

    2013-07-01

    The theory underlying the fission matrix method is derived using a rigorous Green's function approach. The method is then used to investigate fundamental properties of the transport equation for a continuous-energy physics treatment. We provide evidence that an infinite set of discrete, real eigenvalues and eigenfunctions exist for the continuous-energy problem, and that the eigenvalue spectrum converges smoothly as the spatial mesh for the fission matrix is refined. We also derive equations for the adjoint solution. We show that if the mesh is sufficiently refined so that both forward and adjoint solutions are valid, then the adjoint fission matrix is identical to the transpose of the forward matrix. While the energy-dependent transport equation is strictly bi-orthogonal, we provide surprising results that the forward modes are very nearly self-adjoint for a variety of continuous-energy problems. A companion paper (Part II - Applications) describes the initial experience and results from implementing this fission matrix capability into the MCNP Monte Carlo code. (authors)

  19. Announcement: New Editor-In-Chief, Robert C. Kennicutt, Jr.

    NASA Astrophysics Data System (ADS)

    Abt, Helmut A.

    1999-06-01

    Effective 1999 July 1, all new manuscripts for Part 1 of The Astrophysical Journal and The Astrophysical Journal Supplement Series should be sent to Dr. Robert C. Kennicutt, Jr., Editor-in-Chief The Astrophysical Journal Steward Observatory University of Arizona Tucson, AZ 85721-0065 The other means of contact are telephone, (520) 621-5145 FAX, (520) 621-5153 and e-mail, apj@as.arizona.edu. For express packages please use the street address of 933 North Cherry Avenue. Dr. Kennicutt will be assisted by several of my loyal coworkers, who will move across the street. Manuscripts received before July 1 will be handled by the current editor until most of their problems have been resolved, at which point the remainder will be sent to Dr. Kennicutt's office. Manuscripts for the Letters should, as before, be sent directly to Dr. Alex Dalgarno at the Center for Astrophysics in Cambridge, MA. We are fortunate that a person with as much experience in research and proven good judgment as Dr. Kennicutt is willing to accept this difficult and time-consuming responsibility. He will be only the seventh Managing Editor or Editor-in-Chief that this Journal has had in its 104 years. Please give him the cooperation and help that you have given the current editor. It has been my privilege to work for 28 years with many of the best astrophysicists in the world and to publish their papers. This was done with the help of the AAS Publications Board and AAS officers, the efforts of Peter Boyce and Evan Owens who made the on-line edition of the Journal possible, three Associate Editors, a score of Scientific Editors, a hardworking staff of six in Tucson, up to 25 production controllers and manuscript editors at the University of Chicago Press, and the thousands of astronomers throughout the world who served as referees. The original masthead called this journal ``An International Review of Spectroscopy and Astronomical Physics.'' That subtitle is no longer appropriate because we do not

  20. Announcement: New Editor-In Robert C. Kennicutt

    NASA Astrophysics Data System (ADS)

    Abt, Helmut A.

    1999-06-01

    Effective 1999 July 1, all new manuscripts for Part 1 of The Astrophysical Journal and The Astrophysical Journal Supplement Series should be sent to Dr. Robert C. Kennicutt, Editor-in-Chief The Astrophysical Journal Steward Observatory University of Arizona Tucson, AZ 85721-0065 The other means of contact are telephone, (520) 621-5145 FAX, (520) 621-5153 and e-mail, apj@as.arizona.edu. For express packages please use the street address of 933 North Cherry Avenue. Dr. Kennicutt will be assisted by several of my loyal coworkers, who will move across the street. Manuscripts received before July 1 will be handled by the current editor until most of their problems have been resolved, at which point the remainder will be sent to Dr. Kennicutt's office. Manuscripts for the Letters should, as before, be sent directly to Dr. Alex Dalgarno at the Center for Astrophysics in Cambridge, MA. We are fortunate that a person with as much experience in research and proven good judgment as Dr. Kennicutt is willing to accept this difficult and time-consuming responsibility. He will be only the seventh Managing Editor or Editor-in-Chief that this Journal has had in its 104 years. Please give him the cooperation and help that you have given the current editor. It has been my privilege to work for 28 years with many of the best astrophysicists in the world and to publish their papers. This was done with the help of the AAS Publications Board and AAS officers, the efforts of Peter Boyce and Evan Owens who made the on-line edition of the Journal possible, three Associate Editors, a score of Scientific Editors, a hardworking staff of six in Tucson, up to 25 production controllers and manuscript editors at the University of Chicago Press, and the thousands of astronomers throughout the world who served as referees. The original masthead called this journal ``An International Review of Spectroscopy and Astronomical Physics.'' That subtitle is no longer appropriate because we do not publish

  1. Announcement: New Editor-in-Chief Robert C. Kennicutt

    NASA Astrophysics Data System (ADS)

    Abt, Helmut A.

    1999-05-01

    Effective 1999 July 1, all new manuscripts for Part 1 of The Astrophysical Journal and The Astrophysical Journal Supplement Series should be sent to Dr. Robert C. Kennicutt, Editor-in-Chief The Astrophysical Journal Steward Observatory University of Arizona Tucson, AZ 85721-0065 The other means of contact are telephone, (520) 621-5145 FAX, (520) 621-5153 and e-mail, apj@as.arizona.edu. For express packages please use the street address of 933 North Cherry Avenue. Dr. Kennicutt will be assisted by several of my loyal coworkers, who will move across the street. Manuscripts received before July 1 will be handled by the current editor until most of their problems have been resolved, at which point the remainder will be sent to Dr. Kennicutt's office. Manuscripts for the Letters should, as before, be sent directly to Dr. Alex Dalgarno at the Center for Astrophysics in Cambridge, MA. We are fortunate that a person with as much experience in research and proven good judgment as Dr. Kennicutt is willing to accept this difficult and time-consuming responsibility. He will be only the seventh Managing Editor or Editor-in-Chief that this Journal has had in its 104 years. Please give him the cooperation and help that you have given the current editor. It has been my privilege to work for 28 years with many of the best astrophysicists in the world and to publish their papers. This was done with the help of the AAS Publications Board and AAS officers, the efforts of Peter Boyce and Evan Owens who made the on-line edition of the Journal possible, three Associate Editors, a score of Scientific Editors, a hardworking staff of six in Tucson, up to 25 production controllers and manuscript editors at the University of Chicago Press, and the thousands of astronomers throughout the world who served as referees. The original masthead called this journal ``An International Review of Spectroscopy and Astronomical Physics.'' That subtitle is no longer appropriate because we do not publish

  2. LACE: A Web-Based, Structured Editor for PDS Metadata

    NASA Astrophysics Data System (ADS)

    Rose, M.; Keller, R.; Sarram, P.

    2015-06-01

    PDS has moved to XML-based metadata, but many scientists are not familiar with XML and find its structure complicated. For these reasons, we have created LACE, an editor for PDS metadata that hides the complexity of XML from the user.

  3. September 2016 Letter to the Editor-in-Chief.

    PubMed

    2016-09-01

    Letter to the Editor-in-Chief of JOSPT as follows: "One More Cause of Failure to Validate a CPR: Overfitting" with Author's Response J Orthop Sports Phys Ther 2016;46(9):811-812. doi:10.2519/jospt.2016.0202. PMID:27581182

  4. Females' participation in psychopharmacology research as authors, editors, and subjects.

    PubMed

    Poling, Alan; Durgin, Amy; Bradley, Kelly P; Porter, Lindsay K; Van Wagner, Karen; Weeden, Marc; Panos, John J

    2009-04-01

    This study determined the involvement of women as first authors and other authors for every article published in Experimental and Clinical Psychopharmacology, Pharmacology Biochemistry and Behavior, and Psychopharmacology in 1991, 1996, 2001, and 2006. Their involvement as editors also was determined. Women's participation as authors, but not as editors, slightly increased over time. In 2006, 43% of first authors, 38% of other authors, and 24% of editors were women. The gender of subjects was examined for the same years and journals, but could not be determined for 6% and 9% of articles employing nonhuman and human subjects, respectively. In 2006, when subjects' gender could be determined, 77% of articles involving nonhuman subjects used only males, 9% only females, and 14% both males and females. In articles using human subjects in that same year, 17% involved only males, 6% only females, and 77% both males and females. Women researchers clearly make substantial contributions to the psychopharmacology literature, but are nonetheless underrepresented as editors. Findings regarding subjects indicate that there is growing recognition of the importance of gender as a determinant of drug effects, although the vast majority of nonhuman studies continue to involve only male subjects. PMID:19331487

  5. Publishing in Educational Psychology Journals: Comments from Editors

    ERIC Educational Resources Information Center

    Nihalani, Priya K.; Mayrath, Michael C.

    2008-01-01

    The following paper emphasizes the importance of publishing and learning how to publish in educational psychology journals. We have compiled a set of recommendations based on advice from editors in the field and several other sources on how to publish. Additionally, this paper provides a step-by-step guide that graduate students and junior faculty…

  6. Using a Computerized Text-Editor in Freshman Composition.

    ERIC Educational Resources Information Center

    Gerrard, Lisa

    To determine how useful a computerized text editor would be in helping students to revise their papers, an interactive text manipulation system (Wylbur) was made available to two classes of freshman composition students at the University of California, Los Angeles. Since the course received no advance publicity, students did not know when they…

  7. Most Business Editors Find Journalism Graduates Still Unprepared

    ERIC Educational Resources Information Center

    Pardue, Mary Jane

    2014-01-01

    In 2002, a study was published in "Newspaper Research Journal" that explored the preparedness of graduating journalism students to cover business news. In 2012, a follow-up survey of business editors at the nation's daily newspapers was done to see whether progress had been made in the training of journalism students for the…

  8. An Editor's View of Analytical Chemistry (the Discipline)

    NASA Astrophysics Data System (ADS)

    Murray, Royce W.

    2010-07-01

    The author recounts progress observed in analytical chemistry (the discipline) from the vantage point of a 20-year editor of Analytical Chemistry (the journal). The recounting draws liberally from the journal's monthly editorials. A complete listing of the editorials can be found in Supplemental Material .

  9. IN DEFENSE OF ECORISK ASSESSMENT (LETTER TO EDITOR)

    EPA Science Inventory

    Dear Editor: We are writing to convey a more accurate portrayal of the status of ecological ("environmental" in Europe) risk assessment that was presented in the recent article by M. Power and L.S. McCarty (Fallacies in Ecological Risk Assessment Practices," August 1997, pp 370A-...

  10. Attention in Schizophrenia: An Analysis of Selectivity in the Functional Visual Field

    ERIC Educational Resources Information Center

    Cegalis, John A.; And Others

    1977-01-01

    A visual-spatial approach to the study of attention dysfunction was presented. The hypotheses of broadened and narrowed attention were tested by comparing peripheral visual discrimination of acute schizophrenic, chronic schizophrenic, and normal subjects within two regions of the functional visual field. (Editor)

  11. MCNP (Monte Carlo Neutron Photon) capabilities for nuclear well logging calculations

    SciTech Connect

    Forster, R.A.; Little, R.C.; Briesmeister, J.F.

    1989-01-01

    The Los Alamos Radiation Transport Code System (LARTCS) consists of state-of-the-art Monte Carlo and discrete ordinates transport codes and data libraries. The general-purpose continuous-energy Monte Carlo code MCNP (Monte Carlo Neutron Photon), part of the LARTCS, provides a computational predictive capability for many applications of interest to the nuclear well logging community. The generalized three-dimensional geometry of MCNP is well suited for borehole-tool models. SABRINA, another component of the LARTCS, is a graphics code that can be used to interactively create a complex MCNP geometry. Users can define many source and tally characteristics with standard MCNP features. The time-dependent capability of the code is essential when modeling pulsed sources. Problems with neutrons, photons, and electrons as either single particle or coupled particles can be calculated with MCNP. The physics of neutron and photon transport and interactions is modeled in detail using the latest available cross-section data. A rich collections of variance reduction features can greatly increase the efficiency of a calculation. MCNP is written in FORTRAN 77 and has been run on variety of computer systems from scientific workstations to supercomputers. The next production version of MCNP will include features such as continuous-energy electron transport and a multitasking option. Areas of ongoing research of interest to the well logging community include angle biasing, adaptive Monte Carlo, improved discrete ordinates capabilities, and discrete ordinates/Monte Carlo hybrid development. Los Alamos has requested approval by the Department of Energy to create a Radiation Transport Computational Facility under their User Facility Program to increase external interactions with industry, universities, and other government organizations. 21 refs.

  12. Utilization of new 150-MeV neutron and proton evaluations in MCNP

    SciTech Connect

    Little, R.C.; Frankle, S.C.; Hughes, H.G. III; Prael, R.E.

    1997-10-01

    MCNP{trademark} and LAHET{trademark} are two of the codes included in the LARAMIE (Los Alamos Radiation Modeling Interactive Environment) code system. Both MCNP and LAHET are three-dimensional continuous-energy Monte Carlo radiation transport codes. The capabilities of MCNP and LAHET are currently being merged into one code for the Accelerator Production of Tritium (APT) program at Los Alamos National Laboratory. Concurrently, a significant effort is underway to improve the accuracy of the physics in the merged code. In particular, full nuclear-data evaluations (in ENDF6 format) for many materials of importance to APT are being produced for incident neutrons and protons up to an energy of 150-MeV. After processing, cross-section tables based on these new evaluations will be available for use fin the merged code. In order to utilize these new cross-section tables, significant enhancements are required for the merged code. Neutron cross-section tables for MCNP currently specify emission data for neutrons and photons only; the new evaluations also include complete neutron-induced data for protons, deuterons, tritons, and alphas. In addition, no provision in either MCNP or LAHET currently exists for the use of incident charged-particle tables other than for electrons. To accommodate the new neutron-induced data, it was first necessary to expand the format definition of an MCNP neutron cross-section table. The authors have prepared a 150-MeV neutron cross-section library in this expanded format for 15 nuclides. Modifications to MCNP have been implemented so that this expanded neutron library can be utilized.

  13. Criticality Benchmark Results Using Various MCNP Data Libraries

    SciTech Connect

    Stephanie C. Frankle

    1999-07-01

    A suite of 86 criticality benchmarks has been recently implemented in MCNP{trademark} as part of the nuclear data validation effort. These benchmarks have been run using two sets of MCNP continuous-energy neutron data: ENDF/B-VI based data through Release 2 (ENDF60) and the ENDF/B-V based data. New evaluations were completed for ENDF/B-VI for a number of the important nuclides such as the isotopes of H, Be, C, N, O, Fe, Ni, {sup 235,238}U, {sup 237}Np, and {sup 239,240}Pu. When examining the results of these calculations for the five manor categories of {sup 233}U, intermediate-enriched {sup 235}U (IEU), highly enriched {sup 235}U (HEU), {sup 239}Pu, and mixed metal assembles, we find the following: (1) The new evaluations for {sup 9}Be, {sup 12}C, and {sup 14}N show no net effect on k{sub eff}; (2) There is a consistent decrease in k{sub eff} for all of the solution assemblies for ENDF/B-VI due to {sup 1}H and {sup 16}O, moving k{sub eff} further from the benchmark value for uranium solutions and closer to the benchmark value for plutonium solutions; (3) k{sub eff} decreased for the ENDF/B-VI Fe isotopic data, moving the calculated k{sub eff} further from the benchmark value; (4) k{sub eff} decreased for the ENDF/B-VI Ni isotopic data, moving the calculated k{sub eff} closer to the benchmark value; (5) The W data remained unchanged and tended to calculate slightly higher than the benchmark values; (6) For metal uranium systems, the ENDF/B-VI data for {sup 235}U tends to decrease k{sub eff} while the {sup 238}U data tends to increase k{sub eff}. The net result depends on the energy spectrum and material specifications for the particular assembly; (7) For more intermediate-energy systems, the changes in the {sup 235,238}U evaluations tend to increase k{sub eff}. For the mixed graphite and normal uranium-reflected assembly, a large increase in k{sub eff} due to changes in the {sup 238}U evaluation moved the calculated k{sub eff} much closer to the benchmark value. (8

  14. EDITORIAL: Farewell from the outgoing Editor-in-Chief Farewell from the outgoing Editor-in-Chief

    NASA Astrophysics Data System (ADS)

    Rost, Jan Michael

    2011-01-01

    I am very pleased to announce that Professor Paul Corkum will be taking on the position of Editor-in-Chief at Journal of Physics B: Atomic, Molecular and Optical Physics (J. Phys. B) from the beginning of January 2011. During my term as Editor-in-Chief atomic, molecular and optical science has continued to change rapidly: we have seen ultracold physics widening its original emphasis on Bose-Einstein condensates to the entanglement of light and matter in the most general sense towards a science of information. At the same time attosecond science and interaction of matter with short x-ray pulses develops rapidly. I am very happy that J. Phys. B with Paul Corkum as Editor-in-Chief will play a central role in publishing exciting results from this field. I would like to thank the publishing team at J. Phys. B for their fantastic job, in particular for the quality of the refereeing system the team has been able to maintain while at the same time bringing down the publication times considerably. I thank them all for the help and support they have given me in the role of Editor-in-Chief and wish them the very best for the future. Last and certainly not least I would like to thank you, the authors, referees and readers, for the support of J. Phys. B.

  15. EDITORIAL: Outgoing Editor-in-Chief Outgoing Editor-in-Chief

    NASA Astrophysics Data System (ADS)

    Hauptmann, Peter

    2012-01-01

    I started in 2002 as Editor-in-Chief of a well established journal—MST (Measurement Science and Technology). It was a time when modern means of communication offered new opportunities for the scientific community—for all scientists and engineers whether at universities, in industry or at other institutions—to access better quality information in a shorter time. This development helped us to be more efficient in our daily scientific work and to anticipate new trends faster than before. A flood of information was created by different search engines. A few online journals or journals published in emerging countries with a similar profile to MST appeared on the market. MST had to provide new answers in response to these developments. In 2002 I postulated two requirements to the journal. Firstly, the publisher has to be up to date. My impression over the years has been that IOPP is excellently organized. That has made it easier for the board members and all our reviewers to concentrate on the scientific aspects of our input to the journal. During all my visits to Bristol or my contacts with the IOPP staff I always met very professional and enthusiastic staff members. They have not only supported and encouraged the ideas and initiatives of the Editorial Board members, but they have also worked hard on establishing one of the most effective journal operations in the field of measurement science and technology. Many authors are well aware of this. Thus I am able to declare that the first requirement for a successful journal has been met. Secondly, the scientific level has to be high and the journal should attract readers from all over the world. This task was the responsibility of the Editorial Board members and of myself. Our strategy was on the one hand to ensure continuity in MST but on the other hand to be open to new trends and developments. Examples of these new aspects of the journal are fields like micro- and nanometrology, measurement techniques for

  16. FLAn: A Free Hypermedia Editor to Create Foreign Language Learning Units

    ERIC Educational Resources Information Center

    Kilickaya, Ferit, Ed.

    2011-01-01

    Glossing words is done via special software called multimedia editors. Foreign Language Annotator (FLAn), created by Thibeault (2011), is one of these multimedia editors. FLAn (Foreign Language Annotator), a free hypermedia editor that works on both Macs and PCs, allows instructors to turn static texts into dynamic learning units by attaching…

  17. MCNP-REN - A Monte Carlo Tool for Neutron Detector Design Without Using the Point Model

    SciTech Connect

    Abhold, M.E.; Baker, M.C.

    1999-07-25

    The development of neutron detectors makes extensive use of the predictions of detector response through the use of Monte Carlo techniques in conjunction with the point reactor model. Unfortunately, the point reactor model fails to accurately predict detector response in common applications. For this reason, the general Monte Carlo N-Particle code (MCNP) was modified to simulate the pulse streams that would be generated by a neutron detector and normally analyzed by a shift register. This modified code, MCNP - Random Exponentially Distributed Neutron Source (MCNP-REN), along with the Time Analysis Program (TAP) predict neutron detector response without using the point reactor model, making it unnecessary for the user to decide whether or not the assumptions of the point model are met for their application. MCNP-REN is capable of simulating standard neutron coincidence counting as well as neutron multiplicity counting. Measurements of MOX fresh fuel made using the Underwater Coincidence Counter (UWCC) as well as measurements of HEU reactor fuel using the active neutron Research Reactor Fuel Counter (RRFC) are compared with calculations. The method used in MCNP-REN is demonstrated to be fundamentally sound and shown to eliminate the need to use the point model for detector performance predictions.

  18. PREFACE: Introductory remarks from the Editors Introductory remarks from the Editors

    NASA Astrophysics Data System (ADS)

    Knobloch, E.; Meseguer, A.; Marques, F.

    2012-06-01

    The local organizers of the 4th BIFD (Bifurcations and Instabilities in Fluid Dynamics) Symposium held in Barcelona on 18-21 July 2011 would like to thank the editors of Fluid Dynamics Research for offering us the opportunity of publishing a peer-reviewed special issue of the journal with a selection of the contributions presented at this conference. We thank both the authors and the referees for working with us on the rather tight schedule necessary to release the issue within one year of the date of the conference. We also thank the invited speakers, B Eckhardt, L Tuckerman, and J M Vega, for contributing keynote papers to this special issue. The series of BIFD symposia started as a small workshop in Madeira, Portugal, in 2004 with no more than 20 participants. This number increased rapidly during the second and third symposia held in 2006 (Denmark) and 2009 (United Kingdom), with 40 and 110 participants, respectively. The 4th BIFD symposium has consolidated this event as one of the leading conferences in hydrodynamic stability, with nearly 200 participants from around the world. The main goal of this conference is to bring together scientists and engineers from different disciplines directly or indirectly related to fluid dynamics, bifurcation theory and hydrodynamic stability theory. The conference covered many research areas within the aforementioned fields, ranging from thermal, shear and centrifugal flows to biofluids, films, drops, viscoelastic flows and magnetohydrodynamics. The structure of the conference, with invited plenary talks and focused sessions, helped the participants find their home in the conference and share state-of-the-art knowledge within the field of hydrodynamic instabilities. The financial support from MICINN (Spanish Ministry of Science and Innovation, Grant no FIS2009-08065-E) and UPC (Universitat Politècnica de Catalunya) is greatly appreciated. The local organizers would also like to thank ETSAB (Barcelona School of Architecture

  19. Progress with On-The-Fly Neutron Doppler Broadening in MCNP

    SciTech Connect

    Brown, Forrest B.; Martin, William R.; Yesilyurt, Gokhan; Wilderman, Scott

    2012-06-18

    The University of Michigan, ANL, and LANL have been collaborating on a US-DOE-NE University Programs project 'Implementation of On-the-Fly Doppler Broadening in MCNP5 for Multiphysics Simulation of Nuclear Reactors.' This talk describes the project and provides results from the initial implementation of On-The-Fly Doppler broadening (OTF) in MCNP and testing. The OTF methodology involves high precision fitting of Doppler broadened cross-sections over a wide temperature range (the target for reactor calculations is 250-3200K). The temperature dependent fits are then used within MCNP during the neutron transport, for OTF broadening based on cell temperatures. It is straightforward to extend this capability to cover any temperature range of interest, allowing the Monte Carlo simulation to account for a continuous distribution of temperature ranges throughout the problem geometry.

  20. Verification of MCNP simulation of neutron flux parameters at TRIGA MK II reactor of Malaysia.

    PubMed

    Yavar, A R; Khalafi, H; Kasesaz, Y; Sarmani, S; Yahaya, R; Wood, A K; Khoo, K S

    2012-10-01

    A 3-D model for 1 MW TRIGA Mark II research reactor was simulated. Neutron flux parameters were calculated using MCNP-4C code and were compared with experimental results obtained by k(0)-INAA and absolute method. The average values of φ(th),φ(epi), and φ(fast) by MCNP code were (2.19±0.03)×10(12) cm(-2)s(-1), (1.26±0.02)×10(11) cm(-2)s(-1) and (3.33±0.02)×10(10) cm(-2)s(-1), respectively. These average values were consistent with the experimental results obtained by k(0)-INAA. The findings show a good agreement between MCNP code results and experimental results. PMID:22885391

  1. Hiroshima Air-Over-Ground Analysis: Comparison of DORT and MCNP Calculations

    SciTech Connect

    Santoro, RT

    2001-09-04

    Monte Carlo (MCNP4B) and Discrete Ordinates (DORT) calculations were carried out to estimate {sup 60}Co and {sup 152}Eu activation as a function of ground range due to neutrons emitted from the Hiroshima A-bomb. Results of ORNL DORT and MCNP calculations using RZ cylindrical air-over-ground models are compared with LANL MCNP results obtained with an XYZ air-over-ground model. All of the calculations were carried out using ENDF/B-VI cross-section data and detailed angle and energy resolved neutron emission spectra from the weapon. Favorable agreement was achieved for the {sup 60}Co and {sup 152}Eu activation for ground ranges out to 1000m from the three calculations.

  2. Simulation of Photon energy Spectra Using MISC, SOURCES, MCNP and GADRAS

    SciTech Connect

    Tucker, Lucas P.; Shores, Erik F.; Myers, Steven C.; Felsher, Paul D.; Garner, Scott E.; Solomon, Clell J. Jr.

    2012-08-14

    The detector response functions included in the Gamma Detector Response and Analysis Software (GADRAS) are a valuable resource for simulating radioactive source emission spectra. Application of these response functions to the results of three-dimensional transport calculations is a useful modeling capability. Using a 26.2 kg shell of depleted uranium (DU) as a simple test problem, this work illustrates a method for manipulating current tally results from MCNP into the GAM file format necessary for a practical link to GADRAS detector response functions. MISC (MCNP Intrinsic Source Constructor) and SOURCES 4C were used to develop photon and neutron source terms for subsequent MCNP transport, and the resultant spectrum is shown to be in good agreement with that from GADRAS. A 1 kg DU sphere was also modeled with the method described here and showed similarly encouraging results.

  3. Correction to the MCNP{trademark} perturbation feature for cross-section dependent tallies

    SciTech Connect

    Densmore, J.D.; McKinney, G.W.; Hendricks, J.S.

    1997-10-01

    The differential operator perturbation technique is a new feature of the Monte Carlo N-Particle Transport Code MCNP version 4B that will allow users to calculate the effects of cross-section data perturbations on tallies. The implementation of the differential operator perturbation technique in MCNP assumes that the tally is independent of any perturbed cross-section data, an assumption that may not be valid for some tallies. The authors provide derivations of both the first- and second-order corrected perturbations. In addition, the appropriate perturbation corrections are demonstrated so users may accurately calculate perturbation effects for any cross-section dependent tally. Finally, corrected perturbations from six example problems are compared to actual MCNP results.

  4. MCNP capabilities at the dawn of the 21st century: Neutron-gamma applications

    SciTech Connect

    Selcow, E.C.; McKinney, G.W.

    2000-10-01

    The Los Alamos National Laboratory Monte Carlo N-Particle radiation transport code, MCNP, has become an international standard for a wide spectrum of neutron-gamma radiation transport applications. These include nuclear criticality safety, radiation shielding, nuclear safeguards, nuclear well-logging, fission and fusion reactor design, accelerator target design, detector design and analysis, health physics, medical radiation therapy and imaging, radiography, decontamination and decommissioning, and waste storage and disposal. The latest version of the code, MCNP4C, was released to the Radiation Safety Information Computational Center (RSICC) in February 2000.This paper described the new features and capabilities of the code, and discusses the specific applicability to neutron-gamma problems. We will also discuss the future directions for MCNP code development, including rewriting the code in Fortran 90.

  5. MCNP Capabilities at the Dawn of the 21st Century: Neutron-Gamma Applications

    NASA Astrophysics Data System (ADS)

    Selcow, E. C.; McKinney, G. W.; Booth, T. E.; Briesmeister, J. F.; Cox, L. J.; Forster, R. A.; Hendricks, J. S.; Mosteller, R. D.; Prael, R. E.; Sood, A.; White, S. W.

    The Los Alamos National Laboratory Monte Carlo N-Particle radiation transport code, MCNP, has become an international standard for a wide spectrum of neutron-gamma radiation transport applications. These include nuclear criticality safety, radiation shielding, nuclear safeguards, nuclear oil-well logging, fission and fusion reactor design, accelerator target design, detector design and analysis, health physics, medical radiation therapy and imaging, radiography, decontamination and decommissioning, and waste storage and disposal. The latest version of the code, MCNP4C [1], was released to the Radiation Safety Information Computational Center (RSICC) in February 2000. This paper describes the new features and capabilities of the code, and discusses the specific applicability to neutron-gamma problems. We will also discuss some of the future directions for MCNP code development.

  6. Benchmark analysis of MCNP{trademark} ENDF/B-VI iron

    SciTech Connect

    Court, J.D.; Hendricks, J.S.

    1994-12-01

    The MCNP ENDF/B-VI iron cross-section data was subjected to four benchmark studies as part of the Hiroshima/Nagasaki dose re-evaluation for the National Academy of Science and the Defense Nuclear Agency. The four benchmark studies were: (1) the iron sphere benchmarks from the Lawrence Livermore Pulsed Spheres; (2) the Oak Ridge National Laboratory Fusion Reactor Shielding Benchmark; (3) a 76-cm diameter iron sphere benchmark done at the University of Illinois; (4) the Oak Ridge National Laboratory Benchmark for Neutron Transport through Iron. MCNP4A was used to model each benchmark and computational results from the ENDF/B-VI iron evaluations were compared to ENDF/B-IV, ENDF/B-V, the MCNP Recommended Data Set (which includes Los Alamos National Laboratory Group T-2 evaluations), and experimental data. The results show that the ENDF/B-VI iron evaluations are as good as, or better than, previous data sets.

  7. Monte Carlo importance sampling for the MCNP{trademark} general source

    SciTech Connect

    Lichtenstein, H.

    1996-01-09

    Research was performed to develop an importance sampling procedure for a radiation source. The procedure was developed for the MCNP radiation transport code, but the approach itself is general and can be adapted to other Monte Carlo codes. The procedure, as adapted to MCNP, relies entirely on existing MCNP capabilities. It has been tested for very complex descriptions of a general source, in the context of the design of spent-reactor-fuel storage casks. Dramatic improvements in calculation efficiency have been observed in some test cases. In addition, the procedure has been found to provide an acceleration to acceptable convergence, as well as the benefit of quickly identifying user specified variance-reduction in the transport that effects unstable convergence.

  8. MCNP benchmark analyses of critical experiments for the Space Nuclear Thermal Propulsion program

    SciTech Connect

    Selcow, E.C.; Cerbone, R.J.; Ludewig, H.; Mughabghab, S.F.; Schmidt, E.; Todosow, M. ); Parma, E.J. ); Ball, R.M.; Hoovler, G.S. )

    1993-01-15

    Benchmark analyses have been performed of Particle Bed Reactor (PBR) critical experiments (CX) using the MCNP radiation transport code. The experiments have been conducted at the Sandia National Laboratory reactor facility in support of the Space Nuclear Thermal Propulsion (SNTP) program. The test reactor is a nineteen element water moderated and reflected thermal system. A series of integral experiments have been carried out to test the capabilities of the radiation transport codes to predict the performance of PBR systems. MCNP was selected as the preferred radiation analysis tool for the benchmark experiments. Comparison between experimental and calculational results indicate close agreement. This paper describes the analyses of benchmark experiments designed to quantify the accuracy of the MCNP radiation transport code for predicting the performance characteristics of PBR reactors.

  9. MCNP benchmark analyses of critical experiments for the Space Nuclear Thermal Propulsion program

    SciTech Connect

    Selcow, E.C.; Cerbone, R.J.; Ludewig, H.; Mughabghab, S.F.; Schmidt, E.; Todosow, M.; Parma, E.J.; Ball, R.M.; Hoovler, G.S.

    1993-06-01

    Benchmark analyses have been performed of Particle Bed Reactor (PBR) critical experiments (CX) using the MCNP radiation transport code. The experiments have been conducted at the Sandia National Laboratory reactor facility in support of the Space Nuclear Thermal Propulsion (SNTP) program. The test reactor is a nineteen element water moderated and reflected thermal system. A series of integral experiments have been carried out to test the capabilities of the radiation transport codes to predict the performance of PBR systems. MCNP was selected as the preferred radiation analysis tool for the benchmark experiments. Comparison between experimental and calculational results indicate very good agreement. This paper describes the analyses of benchmark experiments designed to quantify the accuracy of the MCNP radiation transport code for predicting the performance characteristics of PBR reactors.

  10. MCNP Modeling Results for Location of Buried TRU Waste Drums

    NASA Astrophysics Data System (ADS)

    Steinman, D. K.; Schweitzer, J. S.

    2006-05-01

    In the 1960's, fifty-five gallon drums of TRU waste were buried in shallow pits on remote U.S. Government facilities such as the Idaho National Engineering Laboratory (now split into the Idaho National Laboratory and the Idaho Completion Project [ICP]). Subsequently, it was decided to remove the drums and the material that was in them from the burial pits and send the material to the Waste Isolation Pilot Plant in New Mexico. Several technologies have been tried to locate the drums non-intrusively with enough precision to minimize the chance for material to be spread into the environment. One of these technologies is the placement of steel probe holes in the pits into which wireline logging probes can be lowered to measure properties and concentrations of material surrounding the probe holes for evidence of TRU material. There is also a concern that large quantities of volatile organic compounds (VOC) are also present that would contaminate the environment during removal. In 2001, the Idaho National Engineering and Environmental Laboratory (INEEL) built two pulsed neutron wireline logging tools to measure TRU and VOC around the probe holes. The tools are the Prompt Fission Neutron (PFN) and the Pulsed Neutron Gamma (PNG), respectively. They were tested experimentally in surrogate test holes in 2003. The work reported here estimates the performance of the tools using Monte-Carlo modelling prior to field deployment. A MCNP model was constructed by INEEL personnel. It was modified by the authors to assess the ability of the tools to predict quantitatively the position and concentration of TRU and VOC materials disposed around the probe holes. The model was used to simulate the tools scanning the probe holes vertically in five centimetre increments. A drum was included in the model that could be placed near the probe hole and at other locations out to forty-five centimetres from the probe-hole in five centimetre increments. Scans were performed with no chlorine in the

  11. From the desk of the Editor-in-Chief

    NASA Astrophysics Data System (ADS)

    Hei, Tom K.

    2015-07-01

    Life Sciences in Space Research had a prominent presence at the International Congress of Radiation Research (ICRR) meeting held in Kyoto, Japan from May 25th-29th, with seven of the eleven editors attending the meeting. A journal booth was also put up at the pre-ICRR satellite meeting on Space Radiation and Heavy Ions in Therapy (SRHITS) held a few days earlier in Osaka. Since the inception of LSSR last year, the editors and publisher have promoted the journal at a number of major conferences including COSPAR 2014 in Moscow, the annual meeting of the Radiation Research Society and the NASA Space Radiation Investigators Meeting. These efforts have increased awareness of the journal among investigators in space life sciences and related fields. The number of monthly downloads of articles from the journal website averages 2000, a respectable number for a brand new journal.

  12. Wysession begins term as Eos Section Editor for Seismology

    NASA Astrophysics Data System (ADS)

    Wysession, Michael

    In mid-April, Michael Wysession, an associate professor in the Department of Earth and Planetary Sciences at Washington University, embarked on a 3-year term as section editor of Eos for seismology. Wysession brings to the position a strong background in research and teaching. Below are a few remarks from Wysession.“I recently became the new seismology editor for Eos. I look forward to presenting the many exciting areas of seismological research to the entire geophysical community. I have taught at Washington University since obtaining my Ph.D. at Northwestern University in 1991. My interest in seismology began during my undergraduate years at Brown University (Sc.B., 1984), but my experience as an educator began after I graduated and taught high school math and physics in Staten Island, N.Y.

  13. Towards a document structure editor for software requirements analysis

    NASA Technical Reports Server (NTRS)

    Kowalski, Vincent J.; Lekkos, Anthony A.

    1986-01-01

    Of the six or seven phases of the software engineering life cycle, requirements analysis tends to be the least understood and the least formalized. Correspondingly, a scarcity of useful software tools exist which aid in the development of user and system requirements. It is proposed that requirements analysis should culminate in a set of documents similar to those that usually accompany a delivered Software product. The design of a software tool, the Document Structure Editor, which facilitates the development of such documentation.

  14. Radiation Transport Analysis in Chalcogenide-Based Devices and a Neutron Howitzer Using MCNP

    NASA Astrophysics Data System (ADS)

    Bowler, Herbert

    As photons, electrons, and neutrons traverse a medium, they impart their energy in ways that are analytically difficult to describe. Monte Carlo methods provide valuable insight into understanding this behavior, especially when the radiation source or environment is too complex to simplify. This research investigates simulating various radiation sources using the Monte Carlo N-Particle (MCNP) transport code, characterizing their impact on various materials, and comparing the simulation results to general theory and measurements. A total of five sources were of interest: two photon sources of different incident particle energies (3.83 eV and 1.25 MeV), two electron sources also of different energies (30 keV and 100 keV), and a californium-252 (Cf-252) spontaneous fission neutron source. Lateral and vertical programmable metallization cells (PMCs) were developed by other researchers for exposure to these photon and electron sources, so simplified PMC models were implemented in MCNP to estimate the doses and fluences. Dose rates measured around the neutron source and the predicted maximum activity of activation foils exposed to the neutrons were determined using MCNP and compared to experimental results obtained from gamma-ray spectroscopy. The analytical fluence calculations for the photon and electron cases agreed with MCNP results, and differences are due to MCNP considering particle movements that hand calculations do not. Doses for the photon cases agreed between the analytical and simulated results, while the electron cases differed by a factor of up to 4.8. Physical dose rate measurements taken from the neutron source agreed with MCNP within the 10% tolerance of the measurement device. The activity results had a percent error of up to 50%, which suggests a need to further evaluate the spectroscopy setup.

  15. Statement on Publication Ethics for Editors and Publishers

    PubMed Central

    2016-01-01

    The digitization and related developments in journal editing and publishing necessitate increasing the awareness of all stakeholders of science communication in the emerging global problems and possible solutions. Journal editors and publishers are frequently encountered with the fast-growing problems of authorship, conflicts of interest, peer review, research misconduct, unethical citations, and inappropriate journal impact metrics. While the number of erroneous and unethical research papers and wasteful, or 'predatory', journals is increasing exponentially, responsible editors are urged to 'clean' the literature by correcting or retracting related articles. Indexers are advised to implement measures for accepting truly influential and ethical journals and delisting sources with predatory publishing practices. Updating knowledge and skills of authors, editors and publishers, developing and endorsing recommendations of global editorial associations, and (re)drafting journal instructions can be viewed as potential tools for improving ethics of academic journals. The aim of this Statement is to increase awareness of all stakeholders of science communication of the emerging ethical issues in journal editing and publishing and initiate a campaign of upgrading and enforcing related journal instructions. PMID:27510376

  16. Statement on Publication Ethics for Editors and Publishers.

    PubMed

    Gasparyan, Armen Yuri; Yessirkepov, Marlen; Voronov, Alexander A; Gorin, Sergey V; Koroleva, Anna M; Kitas, George D

    2016-09-01

    The digitization and related developments in journal editing and publishing necessitate increasing the awareness of all stakeholders of science communication in the emerging global problems and possible solutions. Journal editors and publishers are frequently encountered with the fast-growing problems of authorship, conflicts of interest, peer review, research misconduct, unethical citations, and inappropriate journal impact metrics. While the number of erroneous and unethical research papers and wasteful, or 'predatory', journals is increasing exponentially, responsible editors are urged to 'clean' the literature by correcting or retracting related articles. Indexers are advised to implement measures for accepting truly influential and ethical journals and delisting sources with predatory publishing practices. Updating knowledge and skills of authors, editors and publishers, developing and endorsing recommendations of global editorial associations, and (re)drafting journal instructions can be viewed as potential tools for improving ethics of academic journals. The aim of this Statement is to increase awareness of all stakeholders of science communication of the emerging ethical issues in journal editing and publishing and initiate a campaign of upgrading and enforcing related journal instructions. PMID:27510376

  17. EDITORIAL: Farewell from the outgoing Editor-in-Chief

    NASA Astrophysics Data System (ADS)

    Burnett, Keith

    2005-01-01

    I am very pleased to announce that Professor Jan-Michael Rost will be taking on the position of Editor-in-Chief at Journal of Physics B: Atomic, Molecular and Optical Physics (J. Phys. B) from the beginning of January 2005. As Editor-in-Chief I have seen the journal respond to the rapid and exciting developments in atomic, molecular and optical physics of recent years. There will, I am sure, be a great deal of new and important science in our field in the years ahead. I am also sure that Jan-Michael will do a fantastic job in guiding the journal through these times. The publishing team at J. Phys. B is a superbly responsive and effective one that does a great job in publishing the science we do. I want to thank them all for the help and support they have given me in the role of Editor-in-Chief and wish them the very best for the future. Last and certainly not least I would like to thank you, the authors, referees and readers, for making J. Phys. B such a great journal to have been a part of.

  18. A perspective on computer documentation: System developer vs. technical editor

    SciTech Connect

    Carnes, E.T.; Truett, L.F.

    1995-12-31

    Between the computer-knowledgeable {open_quotes}techie{close_quotes} and the technical writer is a chasm created by differences in knowledge bases and skills. Although this gap is widened by misunderstandings and misconceptions of system development roles, it is bridged by mutual need and dual appreciation. Often the editor/writer is {open_quotes}behind{close_quotes} from beginning to end. The writer normally joins the team after the programmers are well into system development and do not want to {open_quotes}waste time{close_quotes} discussing fundamentals. The writer is usually excluded from technical discussions because it is assumed that he/she would not understand anyway. Later in the system development cycle, the writer has no time to polish the documentation before a new version of the software is issued which implies that the documentation must be revised. Nevertheless, the editor/writer`s product is critical for the end-user`s appreciation of the software, a fact which promotes unity to complete the comprehensive package of software and documentation. This paper explores the planks in the bridge that spans the chasm between developers and their fundamental PR agents, the technical editors/writers. This paper defines approaches (e.g., The Circling Theory) and techniques (Bold Thrust!) employed for effective communication -- between software developer and technical writer as well as between the software and the end-user.

  19. Preliminary results of 3D dose calculations with MCNP-4B code from a SPECT image.

    PubMed

    Rodríguez Gual, M; Lima, F F; Sospedra Alfonso, R; González González, J; Calderón Marín, C

    2004-01-01

    Interface software was developed to generate the input file to run Monte Carlo MCNP-4B code from medical image in Interfile format version 3.3. The software was tested using a spherical phantom of tomography slides with known cumulated activity distribution in Interfile format generated with IMAGAMMA medical image processing system. The 3D dose calculation obtained with Monte Carlo MCNP-4B code was compared with the voxel S factor method. The results show a relative error between both methods less than 1 %. PMID:15625058

  20. Verification of MCNP and DANT/sys With the Analytic Benchmark Test Set

    SciTech Connect

    Parsons, D.K.; Sood, A.; Forster, R.A.; Little, R.C.

    1999-09-20

    The recently published analytic benchmark test set has been used to verify the multigroup option of MCNP and also the deterministic DANT/sys series of codes for criticality calculations. All seventy-five problems of the test set give values for K{sub eff} accurate to at least five significant digits. Flux ratios and flux shapes are also available for many of the problems. All seventy-five problems have been run by both the MCNP and DANT/sys codes and comparisons to K{sub eff} and flux shapes have been made. Results from this verification exercise are given below.

  1. Wikipedia and Medicine: Quantifying Readership, Editors, and the Significance of Natural Language

    PubMed Central

    West, Andrew G

    2015-01-01

    Background Wikipedia is a collaboratively edited encyclopedia. One of the most popular websites on the Internet, it is known to be a frequently used source of health care information by both professionals and the lay public. Objective This paper quantifies the production and consumption of Wikipedia’s medical content along 4 dimensions. First, we measured the amount of medical content in both articles and bytes and, second, the citations that supported that content. Third, we analyzed the medical readership against that of other health care websites between Wikipedia’s natural language editions and its relationship with disease prevalence. Fourth, we surveyed the quantity/characteristics of Wikipedia’s medical contributors, including year-over-year participation trends and editor demographics. Methods Using a well-defined categorization infrastructure, we identified medically pertinent English-language Wikipedia articles and links to their foreign language equivalents. With these, Wikipedia can be queried to produce metadata and full texts for entire article histories. Wikipedia also makes available hourly reports that aggregate reader traffic at per-article granularity. An online survey was used to determine the background of contributors. Standard mining and visualization techniques (eg, aggregation queries, cumulative distribution functions, and/or correlation metrics) were applied to each of these datasets. Analysis focused on year-end 2013, but historical data permitted some longitudinal analysis. Results Wikipedia’s medical content (at the end of 2013) was made up of more than 155,000 articles and 1 billion bytes of text across more than 255 languages. This content was supported by more than 950,000 references. Content was viewed more than 4.88 billion times in 2013. This makes it one of if not the most viewed medical resource(s) globally. The core editor community numbered less than 300 and declined over the past 5 years. The members of this

  2. Greetings from the new Editor-in-Chief, Ronald Stambaugh Greetings from the new Editor-in-Chief, Ronald Stambaugh

    NASA Astrophysics Data System (ADS)

    Stambaugh, Ronald

    2012-04-01

    I am very pleased to join the outstanding leadership team for the journal Nuclear Fusion as Scientific Editor. The journal's high position in the field of fusion energy research derives in no small measure from the efforts of the IAEA team in Vienna, the production and marketing of IOP Publishing, the Board of Editors led by its chairman Mitsuru Kikuchi, the Associate Editor for Inertial Confinement Max Tabak and the outgoing Scientific Editor, Paul Thomas. During Paul's five year tenure submissions have grown by over 40%. The usage of the electronic journal has grown year by year with about 300 000 full text downloads of Nuclear Fusion articles in 2011, an impressive figure due in part to the launch of the full 50 year archive. High quality has been maintained while times for peer review and publishing have been reduced and the journal achieved some of the highest impact factors ever (as high as 4.27). The journal has contributed greatly to building the international scientific basis for fusion. I was privileged to serve from 2003 to 2010 as chairman of the Coordinating Committee for the International Tokamak Physics Activity (ITPA) which published in Nuclear Fusion the first ITER Physics Basis (1999) and its later update (2007). The scientific basis that has been developed to date for fusion has led to the construction of major facilities to demonstrate the production of power-plant relevant levels of fusion reactions. We look forward to the journal continuing to play a key role in the international effort toward fusion energy as these exciting major facilities and the various approaches to fusion continue to be developed. It is clear that Nuclear Fusion maintains its position in the field because of the perceived high quality of the submissions, the refereeing and the editorial processes, and the availability and utility of the online journal. The creation of the Nuclear Fusion Prize, led by the Board of Editors chairman Mitsuru Kikuchi, for the most outstanding

  3. Visual field

    MedlinePlus

    Perimetry; Tangent screen exam; Automated perimetry exam; Goldmann visual field exam; Humphrey visual field exam ... Confrontation visual field exam : This is a quick and basic check of the visual field. The health care provider ...

  4. Visual Learning.

    ERIC Educational Resources Information Center

    Kirrane, Diane E.

    1992-01-01

    An increasingly visual culture is affecting work and training. Achievement of visual literacy means acquiring competence in critical analysis of visual images and in communicating through visual media. (SK)

  5. Visual field

    MedlinePlus

    Perimetry; Tangent screen exam; Automated perimetry exam; Goldmann visual field exam; Humphrey visual field exam ... Confrontation visual field exam : This is a quick and basic check of the visual field. The health care provider sits directly in front ...

  6. TALYS-Based Cross Section Library for Use with MCNP(X).

    Energy Science and Technology Software Center (ESTSC)

    2009-11-11

    Version 00 The TENDL-2008 library has been checked with the CHECKR, FIZCON and PSYCHE checking programs and successfully processed with NJOY-99.161 into ACE format to create this library for use in MCNP5 and MCNPX calculations. ACE files are provided for neutrons, protons, deuterons, tritons, helions and alpha particles.

  7. Validation of the MCNP computational model for neutron flux distribution with the neutron activation analysis measurement

    NASA Astrophysics Data System (ADS)

    Tiyapun, K.; Chimtin, M.; Munsorn, S.; Somchit, S.

    2015-05-01

    The objective of this work is to demonstrate the method for validating the predication of the calculation methods for neutron flux distribution in the irradiation tubes of TRIGA research reactor (TRR-1/M1) using the MCNP computer code model. The reaction rate using in the experiment includes 27Al(n, α)24Na and 197Au(n, γ)198Au reactions. Aluminium (99.9 wt%) and gold (0.1 wt%) foils and the gold foils covered with cadmium were irradiated in 9 locations in the core referred to as CT, C8, C12, F3, F12, F22, F29, G5, and G33. The experimental results were compared to the calculations performed using MCNP which consisted of the detailed geometrical model of the reactor core. The results from the experimental and calculated normalized reaction rates in the reactor core are in good agreement for both reactions showing that the material and geometrical properties of the reactor core are modelled very well. The results indicated that the difference between the experimental measurements and the calculation of the reactor core using the MCNP geometrical model was below 10%. In conclusion the MCNP computational model which was used to calculate the neutron flux and reaction rate distribution in the reactor core can be used for others reactor core parameters including neutron spectra calculation, dose rate calculation, power peaking factors calculation and optimization of research reactor utilization in the future with the confidence in the accuracy and reliability of the calculation.

  8. Comparison of scientific computing platforms for MCNP4A Monte Carlo calculations

    SciTech Connect

    Hendricks, J.S.; Brockhoff, R.C. . Applied Theoretical Physics Division)

    1994-04-01

    The performance of seven computer platforms is evaluated with the widely used and internationally available MCNP4A Monte Carlo radiation transport code. All results are reproducible and are presented in such a way as to enable comparison with computer platforms not in the study. The authors observed that the HP/9000-735 workstation runs MCNP 50% faster than the Cray YMP 8/64. Compared with the Cray YMP 8/64, the IBM RS/6000-560 is 68% as fast, the Sun Sparc10 is 66% as fast, the Silicon Graphics ONYX is 90% as fast, the Gateway 2000 model 4DX2-66V personal computer is 27% as fast, and the Sun Sparc2 is 24% as fast. In addition to comparing the timing performance of the seven platforms, the authors observe that changes in compilers and software over the past 2 yr have resulted in only modest performance improvements, hardware improvements have enhanced performance by less than a factor of [approximately]3, timing studies are very problem dependent, MCNP4Q runs about as fast as MCNP4.

  9. TORT/MCNP coupling method for the calculation of neutron flux around a core of BWR.

    PubMed

    Kurosawa, Masahiko

    2005-01-01

    For the analysis of BWR neutronics performance, accurate data are required for neutron flux distribution over the In-Reactor Pressure Vessel equipments taking into account the detailed geometrical arrangement. The TORT code can calculate neutron flux around a core of BWR in a three-dimensional geometry model, but has difficulties in fine geometrical modelling and lacks huge computer resource. On the other hand, the MCNP code enables the calculation of the neutron flux with a detailed geometry model, but requires very long sampling time to give enough number of particles. Therefore, a TORT/MCNP coupling method has been developed to eliminate the two problems mentioned above in each code. In this method, the TORT code calculates angular flux distribution on the core surface and the MCNP code calculates neutron spectrum at the points of interest using the flux distribution. The coupling method will be used as the DOT-DOMINO-MORSE code system. This TORT/MCNP coupling method was applied to calculate the neutron flux at points where induced radioactivity data were measured for 54Mn and 60Co and the radioactivity calculations based on the neutron flux obtained from the above method were compared with the measured data. PMID:16604689

  10. Certification of MCNP Version 4A for WHC computer platforms. Revision 7

    SciTech Connect

    Carter, L.L.

    1995-05-03

    MCNP is a general-purpose Monte Carlo code that can be used for neutron, photon, or coupled neutron/photon transport, including the capability to calculate eigenvalues for critical systems. The code treats an arbitrary three-dimensional configuration of materials in geometric cells bounded by first- and second-degree surfaces, and some special fourth-degree surfaces (elliptical tori).

  11. Application of MCNP for neutronic calculations at VR-1 training reactor

    NASA Astrophysics Data System (ADS)

    Huml, Ondřej; Rataj, Jan; Bílý, Tomáš

    2014-06-01

    The paper presents utilization of Monte Carlo MCNP transport code for neutronic calculations of training reactor VR-1. Results of calculations are compared with results of measurements realized during last few critical experiments with various reactor core configurations. Very good agreement between calculations and measurements is observed.

  12. MCNP5 CRITICALITY VALIDATION AND BIAS FOR INTERMEDIATE ENRICHED URANIUM SYSTEMS

    SciTech Connect

    FINFROCK SH

    2009-12-10

    The purpose of this analysis is to validate the Monte Carlo N-Particle 5 (MCNP5) code Version 1.40 (LA-UR-03-1987, 2005) and its cross-section database for k-code calculations of intermediate enriched uranium systems on INTEL{reg_sign} processor based PC's running any version of the WINDOWS operating system. Configurations with intermediate enriched uranium were modeled with the moderator range of 39 {le} H/Fissile {le} 1438. See Table 2-1 for brief descriptions of selected cases and Table 3-1 for the range of applicability for this validation. A total of 167 input cases were evaluated including bare and reflected systems in a single body or arrays. The 167 cases were taken directly from the previous (Version 4C [Lan 2005]) validation database. Section 2.0 list data used to calculate k-effective (k{sub eff}) for the 167 experimental criticality benchmark cases using the MCNP5 code v1.40 and its cross section database. Appendix B lists the MCNP cross-section database entries validated for use in evaluating the intermediate enriched uranium systems for criticality safety. The dimensions and atom densities for the intermediate enriched uranium experiments were taken from NEA/NSC/DOC(95)03, September 2005, which will be referred to as the benchmark handbook throughout the report. For these input values, the experimental benchmark k{sub eff} is approximately 1.0. The MCNP validation computer runs ran to an accuracy of approximately {+-} 0.001. For the cases where the reported benchmark k{sub eff} was not equal to 1.0000 the MCNP calculational results were normalized. The difference between the MCNP validation computer runs and the experimentally measured k{sub eff} is the MCNP5 v1.40 bias. The USLSTATS code (ORNL 1998) was utilized to perform the statistical analysis and generate an acceptable maximum k{sub eff} limit for calculations of the intermediate enriched uranium type systems.

  13. EDITORIAL: Greetings from the new Editor-in-Chief

    NASA Astrophysics Data System (ADS)

    Bhattacharya, P.

    2004-04-01

    On 1 January, 2004, I assumed the position of Editor-in-Chief of Journal of Physics D: Applied Physics. I will start by saying that I will do my best to justify the confidence of the journal management and publishing staff in my abilities. I was fortunate to have been able to work, as an Editorial Board member, with my predecessor, the previous Editor-in-Chief, Professor Allister Ferguson. Allister has provided a high degree of intellectual stewardship for the journal in the last five years. He has made the job appear a worthy challenge for me. I therefore take this opportunity to thank Allister on behalf of the Editorial Board and publishing staff of the journal. Several other factors contributed to my decision to accept this position. The first is the group of people who actually go about the business of publishing. The Senior Publisher, Nicola Gulley (and her predecessor Sophy Le Masurier); the Managing Editor, Jill Membrey; the Publishing Administrators, Nina Blakesley and Sarah Towell; the Production Editor, Katie Gerrard and their office staff form an amazing group and have managed to make the operation of the journal incredibly efficient. An index of this is the speed with which incoming manuscripts are processed. The average time between the receipt of a manuscript and its web publication, if accepted, is 130 days. This is three to five times shorter than for most other journals. A factor that contributes to this success is a responsive pool of referees that the publishing staff have as a valuable resource. Ultimately, the standard bearers of any journal are the referees. Therefore, a grateful `thank you' is due from all of us at J. Phys. D to all our referees, who diligently perform this honourable task. The Associate Editors of the journal, Professors Lawler, Margaritondo and O'Grady, also provide immense scientific leadership. They help in defining new directions for the journal and in the publishing process. Last, but not least, a remarkable asset of

  14. EDITORIAL: Greetings from the new Editor-in-Chief Greetings from the new Editor-in-Chief

    NASA Astrophysics Data System (ADS)

    Nielsch, Kornelius

    2012-01-01

    On 1 January 2012 I will be assuming the position of Editor-in-Chief of the journal Semiconductor Science and Technology (SST). I am flattered by the confidence expressed in my ability to carry out this challenging job and I will try hard to justify this confidence. The previous Editor-in-Chief, Laurens Molenkamp, University of Würzburg, Germany, has worked tirelessly for the last ten years and has done an excellent job for the journal. Everyone at the journal is profoundly grateful for his leadership and for his achievements In 2012 several new members will join the Editorial Board: Professor Deli Wang (University of California, San Diego) with considerable expertise in semiconductor nanowires, Professor Saskia Fischer (Humboldt University, Berlin, Germany) with a background in semiconductor quantum devices, and Professor Erwin Kessels (Eindhoven University of Technology, Netherlands) with extensive experience in plasma processing of thin films and gate oxides. In particular, I want to express my gratitude to Professor Israel Bar-Joseph (Weizmann Institute of Science, Israel) and Professor Maria Tamargo (The City College of New York, USA), who will leave next year and who have vigorously served the Editorial Board for years. The journal has recently introduced a fast-track option for manuscripts. This option is a high-quality, high-profile outlet for new and important research across all areas of semiconductor research. Authors can expect to receive referee reports in less than 20 days from submission. Once accepted, you can expect the articles to be online within two or three weeks from acceptance and to be published in print in less than a month. Furthermore, all fast-track communications published in 2011 will be free to read for ten years. More detailed information on fast-track publication can be found on the following webpage: http://iopscience.iop.org/0268-1242/page/Fast track communications It is encouraging to see that since the journal introduced pre

  15. EDITORIAL: Greetings from the new Editor-in-Chief Greetings from the new Editor-in-Chief

    NASA Astrophysics Data System (ADS)

    Nielsch, Kornelius

    2012-01-01

    On 1 January 2012 I will be assuming the position of Editor-in-Chief of the journal Semiconductor Science and Technology (SST). I am flattered by the confidence expressed in my ability to carry out this challenging job and I will try hard to justify this confidence. The previous Editor-in-Chief, Laurens Molenkamp, University of Würzburg, Germany, has worked tirelessly for the last ten years and has done an excellent job for the journal. Everyone at the journal is profoundly grateful for his leadership and for his achievements In 2012 several new members will join the Editorial Board: Professor Deli Wang (University of California, San Diego) with considerable expertise in semiconductor nanowires, Professor Saskia Fischer (Humboldt University, Berlin, Germany) with a background in semiconductor quantum devices, and Professor Erwin Kessels (Eindhoven University of Technology, Netherlands) with extensive experience in plasma processing of thin films and gate oxides. In particular, I want to express my gratitude to Professor Israel Bar-Joseph (Weizmann Institute of Science, Israel) and Professor Maria Tamargo (The City College of New York, USA), who will leave next year and who have vigorously served the Editorial Board for years. The journal has recently introduced a fast-track option for manuscripts. This option is a high-quality, high-profile outlet for new and important research across all areas of semiconductor research. Authors can expect to receive referee reports in less than 20 days from submission. Once accepted, you can expect the articles to be online within two or three weeks from acceptance and to be published in print in less than a month. Furthermore, all fast-track communications published in 2011 will be free to read for ten years. More detailed information on fast-track publication can be found on the following webpage: http://iopscience.iop.org/0268-1242/page/Fast track communications It is encouraging to see that since the journal introduced pre

  16. EDITORIAL: Greetings from the new Editor-in-Chief

    NASA Astrophysics Data System (ADS)

    Garcia, Ephrahim

    2008-02-01

    I am Professor Ephrahim Garcia, an Associate Professor at Sibley School of Mechanical and Aerospace Engineering at Cornell University in Ithaca, New York. I have been at Cornell University since 2002, spent four years as a Program Manager at the Defense Advanced Research Project Agency from 1998-2002, and before that seven years at the Department of Mechanical Engineering at Vanderbilt University in Nashville, Tennessee. I have served on the Editorial Advisory Board of Smart Materials and Structures (SMS) for the last six years. It is a humbling thing to be asked to take up the post of Editor-in-Chief in a field with so many talented researchers. I would like to say a heartfelt thanks to the members of the Editorial Board and IOP Publishing for their confidence in me. Most importantly, I would like to thank Professor Vijay Varadan of the University of Arkansas and Professor Richard Claus of Virginia Polytechnic Institute and State University for their efforts in launching the journal 16 years ago. They have been stewards, promoters and, especially Vijay, key to the operation and function of SMS for all these years, and our research community is indebted to them. Professors Varadan and Claus have dedicated their careers to the area of smart materials and structures and we are very grateful for their leadership, mentoring and contribution. SMS is a thriving journal offering papers on all technical areas concerned with smart materials, systems and structures from the micro- and nanoscale to the macroscale. The journal is undergoing some major changes, including the recent transferal of papers to IOP Publishing's peer-review management system. With this new system authors can expect fast publication times of around 4 or 5 months from submission, and excellent author service. In this world of ever changing technology, the Editorial Board and I aim to reduce the time to publication for researchers in this exciting area of science and engineering. I am in the process of

  17. 29 CFR 793.8 - “News editor.”

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ... 29 Labor 3 2012-07-01 2012-07-01 false âNews editor.â 793.8 Section 793.8 Labor Regulations... Exemption § 793.8 “News editor.” A news editor is an employee who gathers, edits and rewrites the news. He may also select and prepare news items for broadcast and present the news on the air. An employee...

  18. 29 CFR 793.8 - “News editor.”

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... 29 Labor 3 2014-07-01 2014-07-01 false âNews editor.â 793.8 Section 793.8 Labor Regulations... Exemption § 793.8 “News editor.” A news editor is an employee who gathers, edits and rewrites the news. He may also select and prepare news items for broadcast and present the news on the air. An employee...

  19. 29 CFR 793.8 - “News editor.”

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... 29 Labor 3 2013-07-01 2013-07-01 false âNews editor.â 793.8 Section 793.8 Labor Regulations... Exemption § 793.8 “News editor.” A news editor is an employee who gathers, edits and rewrites the news. He may also select and prepare news items for broadcast and present the news on the air. An employee...

  20. Editorial independence at medical journals owned by professional associations: a survey of editors.

    PubMed

    Davis, Ronald M; Müllner, Marcus

    2002-10-01

    The purpose of this study was to assess the degree of editorial independence at a sample of medical journals and the relationship between the journals and their owners. We surveyed the editors of 33 medical journals owned by not-for-profit organizations ("associations"), including 10 journals represented on the International Committee of Medical Journal Editors (nine of which are general medical journals) and a random sample of 23 specialist journals with high impact factors that are indexed by the Institute for Scientific Information. The main outcome measures were the authority to hire, fire, and oversee the work of the editor; the editor's tenure and financial compensation; control of the journal's budget; publication of material about the association; and the editor's perceptions about editorial independence and pressure over editorial content. Of the 33 editors, 23 (70%) reported having complete editorial freedom, and the remainder reported a high level of freedom (a score of > or = 8, where 10 equals complete editorial freedom and 1 equals no editorial freedom). Nevertheless, a substantial minority of editors reported having received at least some pressure in recent years over editorial content from the association's leadership (42%), senior staff (30%), or rank-and-file members (39%). The association's board of directors has the authority to hire (48%) or fire (55%) the editor for about half of the journals, and the editor reports to the board for 10 journals (30%). Twenty-three editors (70%) are appointed for a specific term (median term = 5 years). Three-fifths of the journals have no control over their profit, and the majority of journals use the association's legal counsel and/or media relations staff. Stronger safeguards are needed to give editors protection against pressure over editorial content, including written guarantees of editorial freedom and governance structures that support those guarantees. Strong safeguards are also needed because editors

  1. 29 CFR 793.8 - “News editor.”

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... 29 Labor 3 2011-07-01 2011-07-01 false âNews editor.â 793.8 Section 793.8 Labor Regulations... Exemption § 793.8 “News editor.” A news editor is an employee who gathers, edits and rewrites the news. He may also select and prepare news items for broadcast and present the news on the air. An employee...

  2. 29 CFR 793.8 - “News editor.”

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... 29 Labor 3 2010-07-01 2010-07-01 false âNews editor.â 793.8 Section 793.8 Labor Regulations... Exemption § 793.8 “News editor.” A news editor is an employee who gathers, edits and rewrites the news. He may also select and prepare news items for broadcast and present the news on the air. An employee...

  3. Gene targeting, genome editing: from Dolly to editors.

    PubMed

    Tan, Wenfang; Proudfoot, Chris; Lillico, Simon G; Whitelaw, C Bruce A

    2016-06-01

    One of the most powerful strategies to investigate biology we have as scientists, is the ability to transfer genetic material in a controlled and deliberate manner between organisms. When applied to livestock, applications worthy of commercial venture can be devised. Although initial methods used to generate transgenic livestock resulted in random transgene insertion, the development of SCNT technology enabled homologous recombination gene targeting strategies to be used in livestock. Much has been accomplished using this approach. However, now we have the ability to change a specific base in the genome without leaving any other DNA mark, with no need for a transgene. With the advent of the genome editors this is now possible and like other significant technological leaps, the result is an even greater diversity of possible applications. Indeed, in merely 5 years, these 'molecular scissors' have enabled the production of more than 300 differently edited pigs, cattle, sheep and goats. The advent of genome editors has brought genetic engineering of livestock to a position where industry, the public and politicians are all eager to see real use of genetically engineered livestock to address societal needs. Since the first transgenic livestock reported just over three decades ago the field of livestock biotechnology has come a long way-but the most exciting period is just starting. PMID:26847670

  4. Comments on ``Anonymous Reviews'' An Editor's View of Anonymous Reviews

    NASA Astrophysics Data System (ADS)

    Goff, John A.

    I have read with great interest the recent Forum commentaries in Eos by Myrl Beck, Charles Robinove, Robert Criss, and Anne Hofmeister regarding anonymous reviews. I heartily support their position that anonymous reviews should be avoided. I have not written an anonymous review in ages (and regret the few that I did), and have always appreciated and respected greatly anyone who signs a critical review of one of my own papers. However, I would like to add some perspective from the editorial standpoint. I have served as JGR associate editor for 3 years (never anonymously!), and as Eos editor for seismology and tectonophysics for 4. Over the years, I have rejected a fair number of papers, most of those based on anonymous reviews (fortunately, none of the above commentators was one of them). The vast majority of anonymous reviews I received were well considered. While I would wish that all reviews were signed, I don't think we can summarily dismiss the fear that many would have of enmity and reprisal over a critical review. Some of these fears are likely justified. On more than one occasion, have I witnessed overly aggressive responses on the part of authors to anonymous reviews that I considered to be entirely fair and constructive in their criticisms. I do think we need to do all we can to discourage anonymous reviews, but it will be difficult to completely remove that choice from the process.

  5. A Generic Metadata Editor Supporting System Using Drupal CMS

    NASA Astrophysics Data System (ADS)

    Pan, J.; Banks, N. G.; Leggott, M.

    2011-12-01

    Metadata handling is a key factor in preserving and reusing scientific data. In recent years, standardized structural metadata has become widely used in Geoscience communities. However, there exist many different standards in Geosciences, such as the current version of the Federal Geographic Data Committee's Content Standard for Digital Geospatial Metadata (FGDC CSDGM), the Ecological Markup Language (EML), the Geography Markup Language (GML), and the emerging ISO 19115 and related standards. In addition, there are many different subsets within the Geoscience subdomain such as the Biological Profile of the FGDC (CSDGM), or for geopolitical regions, such as the European Profile or the North American Profile in the ISO standards. It is therefore desirable to have a software foundation to support metadata creation and editing for multiple standards and profiles, without re-inventing the wheels. We have developed a software module as a generic, flexible software system to do just that: to facilitate the support for multiple metadata standards and profiles. The software consists of a set of modules for the Drupal Content Management System (CMS), with minimal inter-dependencies to other Drupal modules. There are two steps in using the system's metadata functions. First, an administrator can use the system to design a user form, based on an XML schema and its instances. The form definition is named and stored in the Drupal database as a XML blob content. Second, users in an editor role can then use the persisted XML definition to render an actual metadata entry form, for creating or editing a metadata record. Behind the scenes, the form definition XML is transformed into a PHP array, which is then rendered via Drupal Form API. When the form is submitted the posted values are used to modify a metadata record. Drupal hooks can be used to perform custom processing on metadata record before and after submission. It is trivial to store the metadata record as an actual XML file

  6. Performance analysis of the Monte Carlo code MCNP4A for photon-based radiotherapy applications

    SciTech Connect

    DeMarco, J.J.; Solberg, T.D.; Wallace, R.E.; Smathers, J.B.

    1995-12-31

    The Los Alamos code MCNP4A (Monte Carlo M-Particle version 4A) is currently used to simulate a variety of problems ranging from nuclear reactor analysis to boron neutron capture therapy. This study is designed to evaluate MCNP4A as the dose calculation system for photon-based radiotherapy applications. A graphical user interface (MCNP Radiation Therapy) has been developed which automatically sets up the geometry and photon source requirements for three-dimensional simulations using Computed Tomography (CT) data. Preliminary results suggest the code is capable of calculating satisfactory dose distributions in a variety of simulated homogeneous and heterogeneous phantoms. The major drawback for this dosimetry system is the amount of time to obtain a statistically significant answer. MCNPRT allows the user to analyze the performance of MCNP4A as a function of material, geometry resolution and MCNP4A photon and electron physics parameters. A typical simulation geometry consists of a 10 MV photon point source incident on a 15 x 15 x 15 cm{sup 3} phantom composed of water voxels ranging in size from 10 x 10 x 10 mm{sup 3} to 2 x 2 x 2 mm{sup 3}. As the voxel size is decreased, a larger percentage of time is spent tracking photons through the voxelized geometry as opposed to the secondary electrons. A PRPR Patch file is under development that will optimize photon transport within the simulation phantom specifically for radiotherapy applications. MCNP4A also supports parallel processing capabilities via the Parallel Virtual Machine (PVM) message passing system. A dedicated network of five SUN SPARC2 processors produced a wall-clock speedup of 4.4 based on a simulation phantom containing 5 x 5 x 5 mm{sup 3} water voxels. The code was also tested on the 80 node IBM RS/6000 cluster at the Maui High Performance Computing Center (NHPCC). A non-dedicated system of 75 processors produces a wall clock speedup of 29 relative to one SUN SPARC2 computer.

  7. Comparative studies of actinide and sub-actinide fission cross section calculation from MCNP6 and TALYS

    SciTech Connect

    Perkasa, Y. S.; Waris, A. Kurniadi, R. Su'ud, Z.

    2014-09-30

    Comparative studies of actinide and sub-actinide fission cross section calculation from MCNP6 and TALYS have been conducted. In this work, fission cross section resulted from MCNP6 prediction will be compared with result from TALYS calculation. MCNP6 with its event generator CEM03.03 and LAQGSM03.03 have been validated and verified for several intermediate and heavy nuclides fission reaction data and also has a good agreement with experimental data for fission reaction that induced by photons, pions, and nucleons at energy from several ten of MeV to about 1 TeV. The calculation that induced within TALYS will be focused mainly to several hundred MeV for actinide and sub-actinide nuclides and will be compared with MCNP6 code and several experimental data from other evaluator.

  8. Coupling MCNP-DSP and LAHET Monte Carlo Codes for Designing Subcriticality Monitors for Accelerator-Driven Systems

    SciTech Connect

    Valentine, T.E.; Rugama, Y. Munoz-Cobos, J.; Perez, R.

    2000-10-23

    The design of reactivity monitoring systems for accelerator-driven systems must be investigated to ensure that such systems remain subcritical during operation. The Monte Carlo codes LAHET and MCNP-DSP were combined together to facilitate the design of reactivity monitoring systems. The coupling of LAHET and MCNP-DSP provides a tool that can be used to simulate a variety of subcritical measurements such as the pulsed neutron, Rossi-{alpha}, or noise analysis measurements.

  9. Validation of MCNP: SPERT-D and BORAX-V fuel

    SciTech Connect

    Crawford, C.; Palmer, B.

    1992-11-01

    This report discusses critical experiments involving SPERT-D[sup 1,2] fuel elements and BORAX-V[sup 3-8] fuel which have been modeled and calculations performed with MCNP. MCNP is a Monte Carlo based transport code. For this study continuous-energy nuclear data from the ENDF/B-V cross section library was used. The SPERT-D experiments consisted of various arrays of fuel elements moderated and reflected with either water or a uranyl nitrate solution. Some SPERT-D experiments used cadmium as a fixed neutron poison, while others were poisoned with various concentrations of boron in the moderating/reflecting solution. ne BORAX-V experiments were arrays of either boiling fuel rod assemblies or superheater assemblies, both types of arrays were moderated and reflected with water. In one boiling fuel experiment, two fuel rods were replaced with borated stainless steel poison rods.

  10. Validation of MCNP: SPERT-D and BORAX-V fuel

    SciTech Connect

    Crawford, C.; Palmer, B.

    1992-11-01

    This report discusses critical experiments involving SPERT-D{sup 1,2} fuel elements and BORAX-V{sup 3-8} fuel which have been modeled and calculations performed with MCNP. MCNP is a Monte Carlo based transport code. For this study continuous-energy nuclear data from the ENDF/B-V cross section library was used. The SPERT-D experiments consisted of various arrays of fuel elements moderated and reflected with either water or a uranyl nitrate solution. Some SPERT-D experiments used cadmium as a fixed neutron poison, while others were poisoned with various concentrations of boron in the moderating/reflecting solution. ne BORAX-V experiments were arrays of either boiling fuel rod assemblies or superheater assemblies, both types of arrays were moderated and reflected with water. In one boiling fuel experiment, two fuel rods were replaced with borated stainless steel poison rods.

  11. Total reaction cross sections in CEM and MCNP6 at intermediate energies

    SciTech Connect

    Kerby, Leslie M.; Mashnik, Stepan G.

    2015-05-14

    Accurate total reaction cross section models are important to achieving reliable predictions from spallation and transport codes. The latest version of the Cascade Exciton Model (CEM) as incorporated in the code CEM03.03, and the Monte Carlo N-Particle transport code (MCNP6), both developed at Los Alamos National Laboratory (LANL), each use such cross sections. Having accurate total reaction cross section models in the intermediate energy region (50 MeV to 5 GeV) is very important for different applications, including analysis of space environments, use in medical physics, and accelerator design, to name just a few. The current inverse cross sections used in the preequilibrium and evaporation stages of CEM are based on the Dostrovsky et al. model, published in 1959. Better cross section models are now available. Implementing better cross section models in CEM and MCNP6 should yield improved predictions for particle spectra and total production cross sections, among other results.

  12. MCNP6 Simulation of Light and Medium Nuclei Fragmentation at Intermediate Energies

    SciTech Connect

    Mashnik, Stepan Georgievich; Kerby, Leslie Marie

    2015-08-24

    Fragmentation reactions induced on light and medium nuclei by protons and light nuclei of energies around 1 GeV/nucleon and below are studied with the Los Alamos transport code MCNP6 and with its CEM03.03 and LAQGSM03.03 event generators. CEM and LAQGSM assume that intermediate-energy fragmentation reactions on light nuclei occur generally in two stages. The first stage is the intranuclear cascade (INC), followed by the second, Fermi breakup disintegration of light excited residual nuclei produced after the INC. CEM and LAQGSM account also for coalescence of light fragments (complex particles) up to sup>4He from energetic nucleons emitted during INC. We investigate the validity and performance of MCNP6, CEM, and LAQGSM in simulating fragmentation reactions at intermediate energies and discuss possible ways of further improving these codes.

  13. Gamma irradiator dose mapping simulation using the MCNP code and benchmarking with dosimetry.

    PubMed

    Sohrabpour, M; Hassanzadeh, M; Shahriari, M; Sharifzadeh, M

    2002-10-01

    The Monte Carlo transport code, MCNP, has been applied in simulating dose rate distribution in the IR-136 gamma irradiator system. Isodose curves, cumulative dose values, and system design data such as throughputs, over-dose-ratios, and efficiencies have been simulated as functions of product density. Simulated isodose curves, and cumulative dose values were compared with dosimetry values obtained using polymethyle-methacrylate, Fricke, ethanol-chlorobenzene, and potassium dichromate dosimeters. The produced system design data were also found to agree quite favorably with those of the system manufacturer's data. MCNP has thus been found to be an effective transport code for handling of various dose mapping excercises for gamma irradiators. PMID:12361333

  14. An MCNP model of glove boxes in a plutonium processing facility

    SciTech Connect

    Dooley, D.E.; Kornreich, D.E.

    1998-12-31

    Nuclear material processing usually occurs simultaneously in several glove boxes whose primary purpose is to contain radioactive materials and prevent inhalation or ingestion of radioactive materials by workers. A room in the plutonium facility at Los Alamos National Laboratory has been slated for installation of a glove box for storing plutonium metal in various shapes during processing. This storage glove box will be located in a room containing other glove boxes used daily by workers processing plutonium parts. An MCNP model of the room and glove boxes has been constructed to estimate the neutron flux at various locations in the room for two different locations of the storage glove box and to determine the effect of placing polyethylene shielding around the storage glove box. A neutron dose survey of the room with sources dispersed as during normal production operations was used as a benchmark to compare the neutron dose equivalent rates calculated by the MCNP model.

  15. MCNP6 simulation of light and medium nuclei fragmentation at intermediate energies

    NASA Astrophysics Data System (ADS)

    Mashnik, Stepan G.; Kerby, Leslie M.

    2016-05-01

    Fragmentation reactions induced on light and medium nuclei by protons and light nuclei of energies around 1 GeV/nucleon and below are studied with the Los Alamos transport code MCNP6 and with its CEM03.03 and LAQGSM03.03 event generators. CEM and LAQGSM assume that intermediate-energy fragmentation reactions on light nuclei occur generally in two stages. The first stage is the intranuclear cascade (INC), followed by the second, Fermi breakup disintegration of light excited residual nuclei produced after the INC. CEM and LAQGSM account also for coalescence of light fragments (complex particles) up to 4He from energetic nucleons emitted during INC. We investigate the validity and performance of MCNP6, CEM, and LAQGSM in simulating fragmentation reactions at intermediate energies and discuss possible ways of further improving these codes.

  16. MCNPX{trademark} -- The LAHET{trademark}/MCNP{trademark} code merger

    SciTech Connect

    Hughes, H.G.; Adams, K.J.; Chadwick, M.B.

    1997-08-01

    The MCNP code is written and maintained by Group X-TM at Los Alamos National Laboratory. In response to the demands of the accelerator community, the authors have undertaken a major effort to expand the capabilities of MCNP to increase the set of transportable particles; to make use of newly evaluated high-energy nuclear data tables for neutrons, protons, and potentially other particles; and to incorporate physics models for use where tabular data are unavailable. A preliminary version of the expanded code, called MCNPX, has now been issued for testing. The new code includes all existing LAHET physics modules, and has the ability to utilize the 150-MeV data libraries that have recently been released by LANL Group T-2.

  17. Conversion of Input Data between KENO and MCNP File Formats for Computer Criticality Assessments

    SciTech Connect

    Schwarz, Randolph A.; Carter, Leland L.; Schwarz Alysia L.

    2006-11-30

    KENO is a Monte Carlo criticality code that is maintained by Oak Ridge National Laboratory (ORNL). KENO is included in the SCALE (Standardized Computer Analysis for Licensing Evaluation) package. KENO is often used because it was specifically designed for criticality calculations. Because KENO has convenient geometry input, including the treatment of lattice arrays of materials, it is frequently used for production calculations. Monte Carlo N-Particle (MCNP) is a Monte Carlo transport code maintained by Los Alamos National Laboratory (LANL). MCNP has a powerful 3D geometry package and an extensive cross section database. It is a general-purpose code and may be used for calculations involving shielding or medical facilities, for example, but can also be used for criticality calculations. MCNP is becoming increasingly more popular for performing production criticality calculations. Both codes have their own specific advantages. After a criticality calculation has been performed with one of the codes, it is often desirable (or may be a safety requirement) to repeat the calculation with the other code to compare the important parameters using a different geometry treatment and cross section database. This manual conversion of input files between the two codes is labor intensive. The industry needs the capability of converting geometry models between MCNP and KENO without a large investment in manpower. The proposed conversion package will aid the user in converting between the codes. It is not intended to be used as a “black box”. The resulting input file will need to be carefully inspected by criticality safety personnel to verify the intent of the calculation is preserved in the conversion. The purpose of this package is to help the criticality specialist in the conversion process by converting the geometry, materials, and pertinent data cards.

  18. SABRINA: an interactive three-dimensional geometry-mnodeling program for MCNP

    SciTech Connect

    West, J.T. III

    1986-10-01

    SABRINA is a fully interactive three-dimensional geometry-modeling program for MCNP, a Los Alamos Monte Carlo code for neutron and photon transport. In SABRINA, a user constructs either body geometry or surface geometry models and debugs spatial descriptions for the resulting objects. This enhanced capability significantly reduces effort in constructing and debugging complicated three-dimensional geometry models for Monte Carlo analysis. 2 refs., 33 figs.

  19. MCNP Continuous-Energy Neutron Cross Section Libraries for Temperatures from 300 to 1365K.

    Energy Science and Technology Software Center (ESTSC)

    2001-04-19

    Version 00 UTXS is a project whereby continuous-energy cross section libraries in ACE format suitable for the MCNP code were generated using the NJOY94.105 processing code. Libraries for various materials were generated at typical operating temperatures of the US Pressurized Water Reactor (PWR), Boiling Water Reactor (BWR), and the Russian PWR (VVER) as well as libraries for other non-reactor applications such as nuclear medicine.

  20. UW MCNP source patch for the EPFL Haefely source. EPFL (Swiss) fusion-fission hybrid experiment

    SciTech Connect

    McKinney, G; Woodruff, G L

    1986-06-01

    The development of a source patch which describes the Haefely neutron source for use in the MCNP Monte Carlo code has been described in progress reports of the EPFL (Swiss) Fusion Blanket Project at the University of Washington. The most recent of these reports dealing with the source patch was Progress Report No. 14. This report reviews some of the physical description included in the report, and also includes additional details of the patch as well as a listing of the patch itself.

  1. Calculation of self-shielding factor for neutron activation experiments using GEANT4 and MCNP

    NASA Astrophysics Data System (ADS)

    Romero-Barrientos, Jaime; Molina, F.; Aguilera, Pablo; Arellano, H. F.

    2016-07-01

    The neutron self-shielding factor G as a function of the neutron energy was obtained for 14 pure metallic samples in 1000 isolethargic energy bins from 1.10-5eV to 2.107eV using Monte Carlo simulations in GEANT4 and MCNP6. The comparison of these two Monte Carlo codes shows small differences in the final self-shielding factor mostly due to the different cross section databases that each program uses.

  2. JEF 2.2 Cross Section Library for the MCNP Monte Carlo Code.

    Energy Science and Technology Software Center (ESTSC)

    2003-11-24

    Version 01 This continuous energy cross-section data library for MCNP is based on the JEF-2.2 evaluated nuclear data library (ACE format). The present library was satisfactorily tested in thermal and fast criticality benchmarks. For analyses below 20 MeV, MCJEF22NEA.BOLlB was applied also in cell and core calculations dedicated to the study of the subcritical accelerator driven systems (ADS).

  3. Validation and verification of MCNP6 against intermediate and high-energy experimental data and results by other codes

    SciTech Connect

    Mashnik, Stepan G

    2010-11-22

    MCNP6, the latest and most advanced LANL transport code representing a recent merger of MCNP5 and MCNPX, has been Validated and Verified (V and V) against a variety of intermediate and high-energy experimental data and against results by different versions of MCNPX and other codes. In the present work, we V andV MCNP6 using mainly the latest modifications of the Cascade-Exciton Model (CEM) and of the Los Alamos version of the Quark-Gluon String Model (LAQGSM) event generators CEM03.02 and LAQGSM03.03. We found that MCNP6 describes reasonably well various reactions induced by particles and nuclei at incident energies from 18 MeV to about 1 TeV per nucleon measured on thin and thick targets and agrees very well with similar results obtained with MCNPX and calculations by CEM03.02, LAQGSM03.01 (03.03), INCL4 + ABLA, and Bertini INC + Dresner evaporation, EPAX, ABRABLA, HIPSE, and AMD, used as stand alone codes. Most of several computational bugs and more serious physics problems observed in MCNP6/X during our V and V have been fixed; we continue our work to solve all the known problems before MCNP6 is distributed to the public.

  4. Monte Carlo calculations of thermal neutron capture in gadolinium: a comparison of GEANT4 and MCNP with measurements.

    PubMed

    Enger, Shirin A; Munck af Rosenschöld, Per; Rezaei, Arash; Lundqvist, Hans

    2006-02-01

    GEANT4 is a Monte Carlo code originally implemented for high-energy physics applications and is well known for particle transport at high energies. The capacity of GEANT4 to simulate neutron transport in the thermal energy region is not equally well known. The aim of this article is to compare MCNP, a code commonly used in low energy neutron transport calculations and GEANT4 with experimental results and select the suitable code for gadolinium neutron capture applications. To account for the thermal neutron scattering from chemically bound atoms [S(alpha,beta)] in biological materials a comparison of thermal neutron fluence in tissue-like poly(methylmethacrylate) phantom is made with MCNP4B, GEANT4 6.0 patch1, and measurements from the neutron capture therapy (NCT) facility at the Studsvik, Sweden. The fluence measurements agreed with MCNP calculated results considering S(alpha,beta). The location of the thermal neutron peak calculated with MCNP without S(alpha,beta) and GEANT4 is shifted by about 0.5 cm towards a shallower depth and is 25%-30% lower in amplitude. Dose distribution from the gadolinium neutron capture reaction is then simulated by MCNP and compared with measured data. The simulations made by MCNP agree well with experimental results. As long as thermal neutron scattering from chemically bound atoms are not included in GEANT4 it is not suitable for NCT applications. PMID:16532938

  5. Monte Carlo calculations of thermal neutron capture in gadolinium: A comparison of GEANT4 and MCNP with measurements

    SciTech Connect

    Enger, Shirin A.; Munck af Rosenschoeld, Per; Rezaei, Arash; Lundqvist, Hans

    2006-02-15

    GEANT4 is a Monte Carlo code originally implemented for high-energy physics applications and is well known for particle transport at high energies. The capacity of GEANT4 to simulate neutron transport in the thermal energy region is not equally well known. The aim of this article is to compare MCNP, a code commonly used in low energy neutron transport calculations and GEANT4 with experimental results and select the suitable code for gadolinium neutron capture applications. To account for the thermal neutron scattering from chemically bound atoms [S({alpha},{beta})] in biological materials a comparison of thermal neutron fluence in tissue-like poly(methylmethacrylate) phantom is made with MCNP4B, GEANT4 6.0 patch1, and measurements from the neutron capture therapy (NCT) facility at the Studsvik, Sweden. The fluence measurements agreed with MCNP calculated results considering S({alpha},{beta}). The location of the thermal neutron peak calculated with MCNP without S({alpha},{beta}) and GEANT4 is shifted by about 0.5 cm towards a shallower depth and is 25%-30% lower in amplitude. Dose distribution from the gadolinium neutron capture reaction is then simulated by MCNP and compared with measured data. The simulations made by MCNP agree well with experimental results. As long as thermal neutron scattering from chemically bound atoms are not included in GEANT4 it is not suitable for NCT applications.

  6. Educating science editors: is there a comprehensive strategy?

    PubMed Central

    Gasparyan, Armen Yuri; Yessirkepov, Marlen; Gorin, Sergey V.; Kitas, George D.

    2014-01-01

    The article considers available options to educate science editors in the fast-transforming digital environment. There is no single course or resource that can cover their constantly changing and diversifying educational needs. The involvement in research, writing, and reviewing is important for gaining editing skills, but that is not all. Membership in editorial associations and access to updated scholarly information in the field are mandatory for maintaining editorial credentials. Learned associations offer access to a few widely-recognized periodicals. There are also formal training courses covering issues in science writing and ethical editing, but no high-level evidence data exist to promote any of these. Networking with like-minded specialists within the global and regional editorial associations seems a useful strategy to upgrade editorial skills and resolve problems with the quality control and digitization of scholarly periodicals. PMID:25559840

  7. Automatic adverse drug events detection using letters to the editor.

    PubMed

    Yang, Chao; Srinivasan, Padmini; Polgreen, Philip M

    2012-01-01

    We present and test the intuition that letters to the editor in journals carry early signals of adverse drug events (ADEs). Surprisingly these letters have not yet been exploited for automatic ADE detection unlike for example, clinical records and PubMed. Part of the challenge is that it is not easy to access the full-text of letters (for the most part these do not appear in PubMed). Also letters are likely underrated in comparison with full articles. Besides demonstrating that this intuition holds we contribute techniques for post market drug surveillance. Specifically, we test an automatic approach for ADE detection from letters using off-the-shelf machine learning tools. We also involve natural language processing for feature definitions. Overall we achieve high accuracy in our experiments and our method also works well on a second new test set. Our results encourage us to further pursue this line of research. PMID:23304379

  8. Automatic Adverse Drug Events Detection Using Letters to the Editor

    PubMed Central

    Yang, Chao; Srinivasan, Padmini; Polgreen, Philip M.

    2012-01-01

    We present and test the intuition that letters to the editor in journals carry early signals of adverse drug events (ADEs). Surprisingly these letters have not yet been exploited for automatic ADE detection unlike for example, clinical records and PubMed. Part of the challenge is that it is not easy to access the full-text of letters (for the most part these do not appear in PubMed). Also letters are likely underrated in comparison with full articles. Besides demonstrating that this intuition holds we contribute techniques for post market drug surveillance. Specifically, we test an automatic approach for ADE detection from letters using off-the-shelf machine learning tools. We also involve natural language processing for feature definitions. Overall we achieve high accuracy in our experiments and our method also works well on a second new test set. Our results encourage us to further pursue this line of research. PMID:23304379

  9. Improving systems documentation using an online copy editor

    SciTech Connect

    Kahn, R.L.

    1985-01-01

    For the last three years the author has been using Writers Workbench, a UNIX text-editing tool, to edit computer documentation. In this article the author outlines his experiences using the system, noting both the advantages to explore and pitfalls to avoid in using this tool. Writers Workbench is especially useful for improving a writer's basic skills - punctuation, spelling, and grammar. When used effectively, Writers Workbench can cut down on wordiness and improve the consistency of a manual. It can help in the creation of a table of contents, index, glossary, and bibliography and in checking readability. Furthermore, by creating user-defined dictionaries, authors or editors can customize the tool to fit their purposes and styles. However, Writers Workbench is not good at catching problems relating to organization, focus, and clarity.

  10. Highlighting impact: Do editors' selections identify influential papers?

    NASA Astrophysics Data System (ADS)

    Antonoyiannakis, Manolis

    A recent trend in scientific publishing is that journal editors highlight each week a select set among the papers published (usually) in their respective journals. The highlighted papers are deemed of higher quality, importance, or interest than the 'average' paper and feature prominently in the publishers' websites. We perform a citation analysis of the highlighted papers for a number of journals from various publishers in physics. By comparing the performance of highlighted papers relative to (a) typical papers and (b) highly cited papers in their source journals and in other journals in the field, we explore whether, and to what extent, the selection process at the time of publication identifies papers that will turn out to be influential. We discuss the broader implications for research assessment.

  11. Advanced software development workstation project: Engineering scripting language. Graphical editor

    NASA Technical Reports Server (NTRS)

    1992-01-01

    Software development is widely considered to be a bottleneck in the development of complex systems, both in terms of development and in terms of maintenance of deployed systems. Cost of software development and maintenance can also be very high. One approach to reducing costs and relieving this bottleneck is increasing the reuse of software designs and software components. A method for achieving such reuse is a software parts composition system. Such a system consists of a language for modeling software parts and their interfaces, a catalog of existing parts, an editor for combining parts, and a code generator that takes a specification and generates code for that application in the target language. The Advanced Software Development Workstation is intended to be an expert system shell designed to provide the capabilities of a software part composition system.

  12. The X-windows interactive navigation data editor

    NASA Technical Reports Server (NTRS)

    Rinker, G. C.

    1992-01-01

    A new computer program called the X-Windows Interactive Data Editor (XIDE) was developed and demonstrated as a prototype application for editing radio metric data in the orbit-determination process. The program runs on a variety of workstations and employs pull-down menus and graphical displays, which allow users to easily inspect and edit radio metric data in the orbit data files received from the Deep Space Network (DSN). The XIDE program is based on the Open Software Foundation OSF/Motif Graphical User Interface (GUI) and has proven to be an efficient tool for editing radio metric data in the navigation operations environment. It was adopted by the Magellan Navigation Team as their primary data-editing tool. Because the software was designed from the beginning to be portable, the prototype was successfully moved to new workstation environments. It was also itegrated into the design of the next-generation software tool for DSN multimission navigation interactive launch support.

  13. An analysis of MCNP cross-sections and tally methods for low-energy photon emitters

    NASA Astrophysics Data System (ADS)

    DeMarco, John J.; Wallace, Robert E.; Boedeker, Kirsten

    2002-04-01

    Monte Carlo calculations are frequently used to analyse a variety of radiological science applications using low-energy (10-1000 keV) photon sources. This study seeks to create a low-energy benchmark for the MCNP Monte Carlo code by simulating the absolute dose rate in water and the air-kerma rate for monoenergetic point sources with energies between 10 keV and 1 MeV. The analysis compares four cross-section datasets as well as the tally method for collision kerma versus absorbed dose. The total photon attenuation coefficient cross-section for low atomic number elements has changed significantly as cross-section data have changed between 1967 and 1989. Differences of up to 10% are observed in the photoelectric cross-section for water at 30 keV between the standard MCNP cross-section dataset (DLC-200) and the most recent XCOM/NIST tabulation. At 30 keV, the absolute dose rate in water at 1.0 cm from the source increases by 7.8% after replacing the DLC-200 photoelectric cross-sections for water with those from the XCOM/NIST tabulation. The differences in the absolute dose rate are analysed when calculated with either the MCNP absorbed dose tally or the collision kerma tally. Significant differences between the collision kerma tally and the absorbed dose tally can occur when using the DLC-200 attenuation coefficients in conjunction with a modern tabulation of mass energy-absorption coefficients.

  14. MCNP6 Simulation of Reactions of Interest to FRIB, Medical, and Space Applications

    NASA Astrophysics Data System (ADS)

    Mashnik, Stepan G.

    The latest production-version of the Los Alamos Monte Carlo N-Particle transport code MCNP6 has been used to simulate a variety of particle-nucleus and nucleus-nucleus reactions of academic and applied interest to research subjects at the Facility for Rare Isotope Beams (FRIB), medical isotope production, space-radiation shielding, cosmic-ray propagation, and accelerator applications, including several reactions induced by radioactive isotopes, analyzing production of both stable and radioactive residual nuclei. Here, we discuss examples of validation and verification of MCNP6 by comparing with recent neutron spectra measured at the Heavy Ion Medical Accelerator in Chiba, Japan; spectra of light fragments from several reactions measured recently at GANIL, France; INFN Laboratori Nazionali del Sud, Catania, Italy; COSY of the Jülich Research Center, Germany; and cross sections of products from several reactions measured lately at GSI, Darmstadt, Germany; ITEP, Moscow, Russia; and, LANSCE, LANL, Los Alamos, U.S.A. As a rule, MCNP6 provides quite good predictions for most of the reactions we analyzed so far, allowing us to conclude that it can be used as a reliable and useful simulation tool for various applications for FRIB, medical, and space applications involving stable and radioactive isotopes.

  15. Voxel2MCNP: software for handling voxel models for Monte Carlo radiation transport calculations.

    PubMed

    Hegenbart, Lars; Pölz, Stefan; Benzler, Andreas; Urban, Manfred

    2012-02-01

    Voxel2MCNP is a program that sets up radiation protection scenarios with voxel models and generates corresponding input files for the Monte Carlo code MCNPX. Its technology is based on object-oriented programming, and the development is platform-independent. It has a user-friendly graphical interface including a two- and three-dimensional viewer. A row of equipment models is implemented in the program. Various voxel model file formats are supported. Applications include calculation of counting efficiency of in vivo measurement scenarios and calculation of dose coefficients for internal and external radiation scenarios. Moreover, anthropometric parameters of voxel models, for instance chest wall thickness, can be determined. Voxel2MCNP offers several methods for voxel model manipulations including image registration techniques. The authors demonstrate the validity of the program results and provide references for previous successful implementations. The authors illustrate the reliability of calculated dose conversion factors and specific absorbed fractions. Voxel2MCNP is used on a regular basis to generate virtual radiation protection scenarios at Karlsruhe Institute of Technology while further improvements and developments are ongoing. PMID:22217596

  16. MCNP-POLIMI Evaluation of Time Dependent Coincidence Between Detectors for Fissile Metal Vs. Oxide Determination

    SciTech Connect

    Pozzi, S. A.; Mihalczo, J. T.

    2002-06-03

    In the past, passive Nuclear Materials Identification System (NMIS) measurements on plutonium metal shells at VNIIEF have shown the sensitivity of the acquired covariance functions to shell mass and thickness for a variety of shell thicknesses from 6 to 30 mm and masses varying from 1829 to 4468g. The technique acquires the time-dependent coincidence distribution between plastic scintillators detecting radiation from the Pu. The measurements showed the sensitivity of the acquired signature to the different spontaneous emission, attenuation, and multiplication properties of the shells. In this work, the MCNP-POLIMI neutron and photon transport code was used to simulate passive measurements on plutonium metal and oxide. The code is a modified version of MCNP, which attempts to calculate more correctly quantities that depend on the second moment of the neutron and gamma distributions, and attempts to model detector pulses as closely as possible. MCNP-POLIMI, together with a post-processing code, can simulate all the time-dependent coincidence distributions measured by NMIS. In particular, the simulations evaluate the time-dependent coincidence distributions between detectors for plutonium samples having mass 2 and 4 kg, in metal and oxide form. This work shows that the time-dependent coincidence distributions between two scintillators measured by NMIS can be used to distinguish metal from oxide.

  17. Calculated organ doses for Mayak production association central hall using ICRP and MCNP.

    PubMed

    Choe, Dong-Ok; Shelkey, Brenda N; Wilde, Justin L; Walk, Heidi A; Slaughter, David M

    2003-03-01

    As part of an ongoing dose reconstruction project, equivalent organ dose rates from photons and neutrons were estimated using the energy spectra measured in the central hall above the graphite reactor core located in the Russian Mayak Production Association facility. Reconstruction of the work environment was necessary due to the lack of personal dosimeter data for neutrons in the time period prior to 1987. A typical worker scenario for the central hall was developed for the Monte Carlo Neutron Photon-4B (MCNP) code. The resultant equivalent dose rates for neutrons and photons were compared with the equivalent dose rates derived from calculations using the conversion coefficients in the International Commission on Radiological Protection Publications 51 and 74 in order to validate the model scenario for this Russian facility. The MCNP results were in good agreement with the results of the ICRP publications indicating the modeling scenario was consistent with actual work conditions given the spectra provided. The MCNP code will allow for additional orientations to accurately reflect source locations. PMID:12645766

  18. An investigation of voxel geometries for MCNP-based radiation dose calculations.

    PubMed

    Zhang, Juying; Bednarz, Bryan; Xu, X George

    2006-11-01

    Voxelized geometry such as those obtained from medical images is increasingly used in Monte Carlo calculations of absorbed doses. One useful application of calculated absorbed dose is the determination of fluence-to-dose conversion factors for different organs. However, confusion still exists about how such a geometry is defined and how the energy deposition is best computed, especially involving a popular code, MCNP5. This study investigated two different types of geometries in the MCNP5 code, cell and lattice definitions. A 10 cm x 10 cm x 10 cm test phantom, which contained an embedded 2 cm x 2 cm x 2 cm target at its center, was considered. A planar source emitting parallel photons was also considered in the study. The results revealed that MCNP5 does not calculate total target volume for multi-voxel geometries. Therefore, tallies which involve total target volume must be divided by the user by the total number of voxels to obtain a correct dose result. Also, using planar source areas greater than the phantom size results in the same fluence-to-dose conversion factor. PMID:17023800

  19. Letters to the Editor: Public Writing as a Response to Reading.

    ERIC Educational Resources Information Center

    Rinehammer, Nora

    A study conducted by the copy editor of a small daily newspaper in Porter County, Indiana examines readers' motivations for writing letters to the editor. Analysis was based on letters that appeared in "The Vidette Messenger" September 16-30, 1992. Of 75 letters, 32 were responses to information published in the paper during the last 2 weeks. All…

  20. Debunking the Mutilated Boy: A Study of Newspaper Editors and an Inflammatory Rumor.

    ERIC Educational Resources Information Center

    Brown, Lee

    A study examined how newspaper editors resolve issues relating to rumors--that is whether to cover stories which may turn out to be false. The "mutilated boy" rumor was chosen for its antiquity and endurance, its powerful theme, and its ability to create intense anxiety in a community. Thirty-three of the 86 editors who responded to the…

  1. The Student Press under Fire and College Newspaper Editors by Race: A Chronicle Survey.

    ERIC Educational Resources Information Center

    Lederman, Douglas; Shea, Christopher

    1993-01-01

    Colleges' student newspapers are criticized for poor coverage of minority groups. Survey reveals that few student editors are minority group members. Table detailing the survey results shows college newspaper editors by race for 111 colleges. Although diversity is cited as a goal, it is not easy to accomplish. Separate sections and minority-group…

  2. Self-Interest and Scholarly Publication: The Dilemma of Researchers, Reviewers, and Editors

    ERIC Educational Resources Information Center

    Calabrese, Raymond L.; Roberts, Brian

    2004-01-01

    Academic misconduct in research is of growing concern to funding agencies, scholars, and academic journal editors. Scholarly publication has ethical implications researchers, reviewers, and journal editors. The theoretical background of the ethics of scholarly publication is explored as well as the use of a case study of an untenured researcher…

  3. Adolescent Sexual Initiation through the Lens of Letters to the Editor Published in Polish Teenage Magazines

    ERIC Educational Resources Information Center

    Kopacz, Marek S.; Bajka-Kopacz, Aleksandra

    2012-01-01

    Almost all teenage magazines invite readers to submit questions concerning relationships, published as letters to the editor, popularly called "advice columns," often containing explicit questions about sexuality. This study aims to examine, firstly, how themes related to sexual initiation are presented in letters to the editor published in Polish…

  4. Error Pattern Analysis Applied to Technical Writing: An Editor's Guide for Writers.

    ERIC Educational Resources Information Center

    Monagle, E. Brette

    The use of error pattern analysis can reduce the time and money spent on editing and correcting manuscripts. What is required is noting, classifying, and keeping a frequency count of errors. First an editor should take a typical page of writing and circle each error. After the editor has done a sufficiently large number of pages to identify an…

  5. A "Situational" and "Coorientational" Measure of Specialized Magazine Editors' Perceptions of Readers.

    ERIC Educational Resources Information Center

    Jeffers, Dennis W.

    A study was undertaken of specialized magazine editors' perceptions of audience characteristics as well as the perceived role of their publications. Specifically, the study examines the relationship between the editors' perceptions of reader problem recognition, level of involvement, constraint recognition, and possession of reference criteria and…

  6. Appropriate roles for the subscriber, publisher, editor, author, and reviewer in the archives of plastic surgery.

    PubMed

    Hwang, Kun

    2013-11-01

    Authors, editors and reviewers, publishers, and subscribers all play their role in scientific journals. These 5 stakeholders are essential to journals. In this paper, firstly, I briefly summarize the role of each journal stakeholder and their respective goals. Secondly, the status of each participant in the Archives of Plastic Surgery is described. Finally, I propose an appropriate role and plan for each of them. Specific roles and responsibilities include the following: subscribers should welcome and submit the critiques of published papers in letters to the editor. Publishers should trust editors and provide them with adequate financial support for ongoing quality improvement of the journal. The editor-in-chief should be given a sufficient period of time-several years-to build up journal quality and train the incoming editor. The editors, including section editors, are also responsible for increasing the author pool. One editor might be designated a 'devil's referee', that is, a kind of devil's advocate with the responsibility of examining the originality of the manuscript, taking a skeptical view of the manuscript, and looking for holes in the methods and results of reported experiments. Authors' responsibilities include submitting manuscripts with scientific integrity and being ready to take responsibility for their articles even long after publication. Finally, reviewers' responsibilities include identifying similar articles not cited. Reviewers are also welcome to write a discussion on the article they review. PMID:24286037

  7. 29 CFR 793.11 - Combination announcer, news editor and chief engineer.

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... 29 Labor 3 2010-07-01 2010-07-01 false Combination announcer, news editor and chief engineer. 793...)(9) OF THE FAIR LABOR STANDARDS ACT Requirements for Exemption § 793.11 Combination announcer, news... as a news editor. In such cases, the primary employment test under the section 13(b)(9)...

  8. 29 CFR 793.11 - Combination announcer, news editor and chief engineer.

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... 29 Labor 3 2011-07-01 2011-07-01 false Combination announcer, news editor and chief engineer. 793...)(9) OF THE FAIR LABOR STANDARDS ACT Requirements for Exemption § 793.11 Combination announcer, news... as a news editor. In such cases, the primary employment test under the section 13(b)(9)...

  9. A survey of orthopaedic journal editors determining the criteria of manuscript selection for publication

    PubMed Central

    2011-01-01

    Background To investigate the characteristics of editors and criteria used by orthopaedic journal editors in assessing submitted manuscripts. Methods Between 2008 to 2009 all 70 editors of Medline listed orthopaedic journals were approached prospectively with a questionnaire to determine the criteria used in assessing manuscripts for publication. Results There was a 42% response rate. There was 1 female editor and the rest were male with 57% greater than 60 years of age. 67% of the editors worked in university teaching hospitals and 90% of publications were in English. The review process differed between journals with 59% using a review proforma, 52% reviewing an anonymised manuscript, 76% using a routine statistical review and 59% of journals used 2 reviewers routinely. In 89% of the editors surveyed, the editor was able to overrule the final decision of the reviewers. Important design factors considered for manuscript acceptance were that the study conclusions were justified (80%), that the statistical analysis was appropriate (76%), that the findings could change practice (72%). The level of evidence (70%) and type of study (62%) were deemed less important. When asked what factors were important in the manuscript influencing acceptance, 73% cited an understandable manuscript, 53% cited a well written manuscript and 50% a thorough literature review as very important factors. Conclusions The editorial and review process in orthopaedic journals uses different approaches. There may be a risk of language bias among editors of orthopaedic journals with under-representation of non-English publications in the orthopaedic literature. PMID:21527007

  10. Magazine Article Placement: How Editors, Regular Contributors, and Novice Writers Rate Query Letters.

    ERIC Educational Resources Information Center

    Jolliffe, Lee

    About 350,000 freelance magazine articles were purchased by magazine editors last year from the 22,000 freelancers and 225,000 would-be freelancers in the United States. A study examined the factors editors judge most important in selecting freelance magazine article proposals, using factor analysis and qualitative examination of persuasive…

  11. 29 CFR 793.11 - Combination announcer, news editor and chief engineer.

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ... 29 Labor 3 2012-07-01 2012-07-01 false Combination announcer, news editor and chief engineer. 793.11 Section 793.11 Labor Regulations Relating to Labor (Continued) WAGE AND HOUR DIVISION, DEPARTMENT... editor and chief engineer. The 13(b)(9) exemption, as was made clear during the debate on the...

  12. 29 CFR 793.11 - Combination announcer, news editor and chief engineer.

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... 29 Labor 3 2014-07-01 2014-07-01 false Combination announcer, news editor and chief engineer. 793.11 Section 793.11 Labor Regulations Relating to Labor (Continued) WAGE AND HOUR DIVISION, DEPARTMENT... editor and chief engineer. The 13(b)(9) exemption, as was made clear during the debate on the...

  13. 29 CFR 793.11 - Combination announcer, news editor and chief engineer.

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... 29 Labor 3 2013-07-01 2013-07-01 false Combination announcer, news editor and chief engineer. 793.11 Section 793.11 Labor Regulations Relating to Labor (Continued) WAGE AND HOUR DIVISION, DEPARTMENT... editor and chief engineer. The 13(b)(9) exemption, as was made clear during the debate on the...

  14. Letter to the editor of TAAP, in response to letter from Anders et al.

    EPA Science Inventory

    To the Editor, Toxicology and Applied Pharmacology: We would like to address the letter to the editor submitted by Anders et al. regarding the substantive issues raised regarding our paper "Evaluation of two different metabolic hypotheses for dichloromethane toxicity using physi...

  15. "Clones," Codes, and Conflicts of Interest in Cartooning: Cartoonists and Editors Look at Ethics.

    ERIC Educational Resources Information Center

    Riffe, Daniel; And Others

    A study examined differences between political cartoonists and op-ed page editors on both traditional ethical issues (such as conflicts of interest) and the special, style-related concerns of editorial cartoonists. Hypotheses proposed were that editors and cartoonists (1) would condemn "cloning" or copying, reflecting an ethical principle…

  16. EDITORIAL: A word from the new Editor-in-Chief A word from the new Editor-in-Chief

    NASA Astrophysics Data System (ADS)

    Mostowski, Jan

    2011-01-01

    TIn the autumn of 2010 I became the Editor-in Chief of European Journal of Physics (EJP). EJP is a place for teachers, instructors and professors to exchange their views on teaching physics at university level and share their experience. It is general opinion that no good research is possible without connection with good, high-quality teaching, at the university level in particular. Therefore excellence in physics teaching is important to the physics community. European Journal of Physics is proud of its contribution to achieving this goal. As Editor-in-Chief, I will continue to work to this general objective of the journal. We will publish articles on specific topics in physics, stressing originality of presentation and suitability for use in students'laboratories, lectures and physics teaching in general. We will also publish more pedagogical papers presenting the achievements of particular teaching methods. In addition, we will continue to publish special sections on particular areas of physics, as well as the annual special section on physics competitions. European Journal of Physics is in good shape. Due to the work of the previous editors and the publisher, the readership is high and growing steadily, and many excellent papers are being submitted and published. I hope that this positive trend for the journal will continue, and I will do my best to keep to this high standard. A few words about myself. I work in the Institute of Physics in Warsaw, Poland. My main research interests are in theoretical quantum optics and I have published about 80 research papers on this topic. For many years I was involved in teaching physics at university and in high school. I am a co-author of a textbook on physics for high-school students and of a problem book in quantum mechanics. For the last ten years, I have been involved in the International Physics Olympiad and over the last few years I have been a member of the Editorial Board of European Journal of Physics.

  17. Evaluation of computational models and cross sections used by MCNP6 for simulation of electron backscattering

    NASA Astrophysics Data System (ADS)

    Poškus, Andrius

    2016-02-01

    This work evaluates the accuracy of the single-event (SE) and condensed-history (CH) models of electron transport in Monte Carlo simulations of electron backscattering from thick layers of Be, C, Al, Cu, Ag, Au and U at incident electron energies from 200 eV to 15 MeV. The CH method is used in simulations performed with MCNP6.1, and the SE method is used in simulations performed with an open-source single-event code MCNelectron written by the author of this paper. Both MCNP6.1 and MCNelectron use mainly ENDF/B-VI.8 library data, but MCNelectron allows replacing cross sections of certain types of interactions by alternative datasets from other sources. The SE method is evaluated both using only ENDF/B-VI.8 cross sections (the "SE-ENDF/B method", which is equivalent to using MCNP6.1 in SE mode) and with an alternative set of elastic scattering cross sections obtained from relativistic (Dirac) partial-wave (DPW) calculations (the "SE-DPW method"). It is shown that at energies from 200 eV to 300 keV the estimates of the backscattering coefficients obtained using the SE-DPW method are typically within 10% of the experimental data, which is approximately the same accuracy that is achieved using MCNP6.1 in CH mode. At energies below 1 keV and above 300 keV, the SE-DPW method is much more accurate than the SE-ENDF/B method due to lack of angular distribution data in the ENDF/B library in those energy ranges. At energies from 500 keV to 15 MeV, the CH approximation is roughly twice more accurate than the SE-DPW method, with the average relative errors equal 7% and 14%, respectively. The energy probability density functions (PDFs) of backscattered electrons for Al and Cu, calculated using the SE method with DPW cross sections when energy of incident electrons is 20 keV, have an average absolute error as low as 4% of the average PDF. This error is approximately twice less than the error of the corresponding PDF calculated using the CH approximation. It is concluded that the

  18. V&V of MCNP 6.1.1 Beta Against Intermediate and High-Energy Experimental Data

    SciTech Connect

    Mashnik, Stepan G

    2014-09-08

    This report presents a set of validation and verification (V&V) MCNP 6.1.1 beta results calculated in parallel, with MPI, obtained using its event generators at intermediate and high-energies compared against various experimental data. It also contains several examples of results using the models at energies below 150 MeV, down to 10 MeV, where data libraries are normally used. This report can be considered as the forth part of a set of MCNP6 Testing Primers, after its first, LA-UR-11-05129, and second, LA-UR-11-05627, and third, LA-UR-26944, publications, but is devoted to V&V with the latest, 1.1 beta version of MCNP6. The MCNP6 test-problems discussed here are presented in the /VALIDATION_CEM/and/VALIDATION_LAQGSM/subdirectories in the MCNP6/Testing/directory. README files that contain short descriptions of every input file, the experiment, the quantity of interest that the experiment measures and its description in the MCNP6 output files, and the publication reference of that experiment are presented for every test problem. Templates for plotting the corresponding results with xmgrace as well as pdf files with figures representing the final results of our V&V efforts are presented. Several technical “bugs” in MCNP 6.1.1 beta were discovered during our current V&V of MCNP6 while running it in parallel with MPI using its event generators. These “bugs” are to be fixed in the following version of MCNP6. Our results show that MCNP 6.1.1 beta using its CEM03.03, LAQGSM03.03, Bertini, and INCL+ABLA, event generators describes, as a rule, reasonably well different intermediate- and high-energy measured data. This primer isn’t meant to be read from cover to cover. Readers may skip some sections and go directly to any test problem in which they are interested.

  19. MCNP5 and GEANT4 comparisons for preliminary Fast Neutron Pencil Beam design at the University of Utah TRIGA system

    NASA Astrophysics Data System (ADS)

    Adjei, Christian Amevi

    The main objective of this thesis is twofold. The starting objective was to develop a model for meaningful benchmarking of different versions of GEANT4 against an experimental set-up and MCNP5 pertaining to photon transport and interactions. The following objective was to develop a preliminary design of a Fast Neutron Pencil Beam (FNPB) Facility to be applicable for the University of Utah research reactor (UUTR) using MCNP5 and GEANT4. The three various GEANT4 code versions, GEANT4.9.4, GEANT4.9.3, and GEANT4.9.2, were compared to MCNP5 and the experimental measurements of gamma attenuation in air. The average gamma dose rate was measured in the laboratory experiment at various distances from a shielded cesium source using a Ludlum model 19 portable NaI detector. As it was expected, the gamma dose rate decreased with distance. All three GEANT4 code versions agreed well with both the experimental data and the MCNP5 simulation. Additionally, a simple GEANT4 and MCNP5 model was developed to compare the code agreements for neutron interactions in various materials. Preliminary FNPB design was developed using MCNP5; a semi-accurate model was developed using GEANT4 (because GEANT4 does not support the reactor physics modeling, the reactor was represented as a surface neutron source, thus a semi-accurate model). Based on the MCNP5 model, the fast neutron flux in a sample holder of the FNPB is obtained to be 6.52×107 n/cm2s, which is one order of magnitude lower than gigantic fast neutron pencil beam facilities existing elsewhere. The MCNP5 model-based neutron spectrum indicates that the maximum expected fast neutron flux is at a neutron energy of ~1 MeV. In addition, the MCNP5 model provided information on gamma flux to be expected in this preliminary FNPB design; specifically, in the sample holder, the gamma flux is to be expected to be around 108 γ/cm 2s, delivering a gamma dose of 4.54×103 rem/hr. This value is one to two orders of magnitudes below the gamma

  20. Visual agnosia.

    PubMed

    Álvarez, R; Masjuan, J

    2016-03-01

    Visual agnosia is defined as an impairment of object recognition, in the absence of visual acuity or cognitive dysfunction that would explain this impairment. This condition is caused by lesions in the visual association cortex, sparing primary visual cortex. There are 2 main pathways that process visual information: the ventral stream, tasked with object recognition, and the dorsal stream, in charge of locating objects in space. Visual agnosia can therefore be divided into 2 major groups depending on which of the two streams is damaged. The aim of this article is to conduct a narrative review of the various visual agnosia syndromes, including recent developments in a number of these syndromes. PMID:26358494

  1. THE NEW ONLINE METADATA EDITOR FOR GENERATING STRUCTURED METADATA

    SciTech Connect

    Devarakonda, Ranjeet; Shrestha, Biva; Palanisamy, Giri; Hook, Leslie A; Killeffer, Terri S; Boden, Thomas A; Cook, Robert B; Zolly, Lisa; Hutchison, Viv; Frame, Mike; Cialella, Alice; Lazer, Kathy

    2014-01-01

    Nobody is better suited to describe data than the scientist who created it. This description about a data is called Metadata. In general terms, Metadata represents the who, what, when, where, why and how of the dataset [1]. eXtensible Markup Language (XML) is the preferred output format for metadata, as it makes it portable and, more importantly, suitable for system discoverability. The newly developed ORNL Metadata Editor (OME) is a Web-based tool that allows users to create and maintain XML files containing key information, or metadata, about the research. Metadata include information about the specific projects, parameters, time periods, and locations associated with the data. Such information helps put the research findings in context. In addition, the metadata produced using OME will allow other researchers to find these data via Metadata clearinghouses like Mercury [2][4]. OME is part of ORNL s Mercury software fleet [2][3]. It was jointly developed to support projects funded by the United States Geological Survey (USGS), U.S. Department of Energy (DOE), National Aeronautics and Space Administration (NASA) and National Oceanic and Atmospheric Administration (NOAA). OME s architecture provides a customizable interface to support project-specific requirements. Using this new architecture, the ORNL team developed OME instances for USGS s Core Science Analytics, Synthesis, and Libraries (CSAS&L), DOE s Next Generation Ecosystem Experiments (NGEE) and Atmospheric Radiation Measurement (ARM) Program, and the international Surface Ocean Carbon Dioxide ATlas (SOCAT). Researchers simply use the ORNL Metadata Editor to enter relevant metadata into a Web-based form. From the information on the form, the Metadata Editor can create an XML file on the server that the editor is installed or to the user s personal computer. Researchers can also use the ORNL Metadata Editor to modify existing XML metadata files. As an example, an NGEE Arctic scientist use OME to register

  2. The New Online Metadata Editor for Generating Structured Metadata

    NASA Astrophysics Data System (ADS)

    Devarakonda, R.; Shrestha, B.; Palanisamy, G.; Hook, L.; Killeffer, T.; Boden, T.; Cook, R. B.; Zolly, L.; Hutchison, V.; Frame, M. T.; Cialella, A. T.; Lazer, K.

    2014-12-01

    Nobody is better suited to "describe" data than the scientist who created it. This "description" about a data is called Metadata. In general terms, Metadata represents the who, what, when, where, why and how of the dataset. eXtensible Markup Language (XML) is the preferred output format for metadata, as it makes it portable and, more importantly, suitable for system discoverability. The newly developed ORNL Metadata Editor (OME) is a Web-based tool that allows users to create and maintain XML files containing key information, or metadata, about the research. Metadata include information about the specific projects, parameters, time periods, and locations associated with the data. Such information helps put the research findings in context. In addition, the metadata produced using OME will allow other researchers to find these data via Metadata clearinghouses like Mercury [1] [2]. Researchers simply use the ORNL Metadata Editor to enter relevant metadata into a Web-based form. How is OME helping Big Data Centers like ORNL DAAC? The ORNL DAAC is one of NASA's Earth Observing System Data and Information System (EOSDIS) data centers managed by the ESDIS Project. The ORNL DAAC archives data produced by NASA's Terrestrial Ecology Program. The DAAC provides data and information relevant to biogeochemical dynamics, ecological data, and environmental processes, critical for understanding the dynamics relating to the biological components of the Earth's environment. Typically data produced, archived and analyzed is at a scale of multiple petabytes, which makes the discoverability of the data very challenging. Without proper metadata associated with the data, it is difficult to find the data you are looking for and equally difficult to use and understand the data. OME will allow data centers like the ORNL DAAC to produce meaningful, high quality, standards-based, descriptive information about their data products in-turn helping with the data discoverability and

  3. Accuracy of the electron transport in mcnp5 and its suitability for ionization chamber response simulations: A comparison with the egsnrc and penelope codes

    SciTech Connect

    Koivunoro, Hanna; Siiskonen, Teemu; Kotiluoto, Petri; Auterinen, Iiro; Hippelaeinen, Eero; Savolainen, Sauli

    2012-03-15

    Purpose: In this work, accuracy of the mcnp5 code in the electron transport calculations and its suitability for ionization chamber (IC) response simulations in photon beams are studied in comparison to egsnrc and penelope codes. Methods: The electron transport is studied by comparing the depth dose distributions in a water phantom subdivided into thin layers using incident energies (0.05, 0.1, 1, and 10 MeV) for the broad parallel electron beams. The IC response simulations are studied in water phantom in three dosimetric gas materials (air, argon, and methane based tissue equivalent gas) for photon beams ({sup 60}Co source, 6 MV linear medical accelerator, and mono-energetic 2 MeV photon source). Two optional electron transport models of mcnp5 are evaluated: the ITS-based electron energy indexing (mcnp5{sub ITS}) and the new detailed electron energy-loss straggling logic (mcnp5{sub new}). The electron substep length (ESTEP parameter) dependency in mcnp5 is investigated as well. Results: For the electron beam studies, large discrepancies (>3%) are observed between the mcnp5 dose distributions and the reference codes at 1 MeV and lower energies. The discrepancy is especially notable for 0.1 and 0.05 MeV electron beams. The boundary crossing artifacts, which are well known for the mcnp5{sub ITS}, are observed for the mcnp5{sub new} only at 0.1 and 0.05 MeV beam energies. If the excessive boundary crossing is eliminated by using single scoring cells, the mcnp5{sub ITS} provides dose distributions that agree better with the reference codes than mcnp5{sub new}. The mcnp5 dose estimates for the gas cavity agree within 1% with the reference codes, if the mcnp5{sub ITS} is applied or electron substep length is set adequately for the gas in the cavity using the mcnp5{sub new}. The mcnp5{sub new} results are found highly dependent on the chosen electron substep length and might lead up to 15% underestimation of the absorbed dose. Conclusions: Since the mcnp5 electron

  4. Role of Visual Familiarity in the Word-Superiority Effects Obtained with the Simultaneous-Matching Task

    ERIC Educational Resources Information Center

    Bruder, Gail A.

    1978-01-01

    Three experiments assessed the effect of visual familiarity of words on "same-different" reaction times (RTs) in a simultaneous-matching task. All three studies showed visual familiarity to be responsible for differences in slope over sequence length between words and nonwords. (Editor/RK)

  5. Fault Tree, Event Tree, and Piping and Instrumentation Diagram (FEP) editors, Version 4. 0

    SciTech Connect

    McKay, M.K.; Skinner, N.L.; Wood, S.T. )

    1992-05-01

    The Fault Tree, Event Tree, and Piping Instrumentation Diagram (FEP) editors allow the user to graphically build and edit fault trees, event trees, and piping instrumentation diagrams (P IDs). The software is designed to enable the use of graphical-based editors found in the Integrated Reliability and Risk Assessment System (IRRAS). FEP is made up of three separate editors (Fault Tree, Event Tree, and Piping Instrumentation Diagram) and a utility module. This reference manual provides a screen-by-screen walkthrough of the entire FEP System.

  6. Simulations of neutron multiplicity measurements of a weapons-grade plutonium sphere with MCNP-PoliMi.

    SciTech Connect

    Mattingly, John K.; Pozzi, Sara A.; Clarke, Shaun D.; Dennis, Ben D.; Miller, Eric C.; Padovani, E.

    2010-06-01

    With increasing concern over the ability to detect and characterize special nuclear materials, the need for computer codes that can successfully predict the response of detector systems to various measurement scenarios is extremely important. These computer algorithms need to be benchmarked against a variety of experimental configurations to ensure their accuracy and understand their limitations. The Monte Carlo code MCNP-PoliMi is a modified version of the MCNP-4c code. Recently these modifications have been ported into the new MCNPX 2.6.0 code, which gives the new MCNPX-PoliMi a wider variety of options and abilities, taking advantage of the improvements made to MCNPX. To verify the ability of the MCNPX-PoliMi code to simulate the response of a neutron multiplicity detector simulated results were compared to experimental data. The experiment consisted of a 4.5-kg sphere of alpha-phase plutonium that was moderated with various thicknesses of polyethylene. The results showed that our code system can simulate the multiplicity distributions with relatively good agreement with measured data. The enhancements made to MCNP since the release of MCNP-4c have had little to no effect on the ability of the MCNP-PoliMi to resolve the discrepancies observed in the simulated neutron multiplicity distributions when compared experimental data.

  7. Efficiency of whole-body counter for various body size calculated by MCNP5 software.

    PubMed

    Krstic, D; Nikezic, D

    2012-11-01

    The efficiency of a whole-body counter for (137)Cs and (40)K was calculated using the MCNP5 code. The ORNL phantoms of a human body of different body sizes were applied in a sitting position in front of a detector. The aim was to investigate the dependence of efficiency on the body size (age) and the detector position with respect to the body and to estimate the accuracy of real measurements. The calculation work presented here is related to the NaI detector, which is available in the Serbian Whole-body Counter facility in Vinca Institute. PMID:22923253

  8. Input files with ORNL—mathematical phantoms of the human body for MCNP-4B

    NASA Astrophysics Data System (ADS)

    Krstić, D.; Nikezić, D.

    2007-01-01

    Protection against ionizing radiation requires information on the absorbed doses in organs of the human body. Implantation of many dosimeters in the human body is undesirable (or impossible), so the doses in organs are not measurable and some kind of dose calculation has to be applied. Calculation of doses in organs requests: (a) an exact description of the geometry of organs, (b) the chemical constitution of tissues, and (c) appropriate computer programs. The first two items, (a) and (b), make a so-called "phantom". In another words, the "phantom of a human body" is a mathematical representation of the human body including all other relevant information. All organs are represented with geometrical bodies (like cylinders, ellipsoids, tori, cones etc.), which are described with suitable mathematical equations. A corresponding chemical constitution for various types of organ tissues is also defined. MCNP-4B ( Monte Carlo N- Particle) is often used as transport code. Users of this software prepare an "input file" providing all necessary information for program execution. This information includes: (a) source definition—type of ionizing radiation, energy spectrum, and geometry of the source; (b) target definition—material constitution, geometry, location in respect to the source etc.; (c) characterization of absorbing media between the source and target; (d) output tally, etc. This paper presents input files with "human phantoms" for the MCNP-4B code. The input files with "phantoms" were prepared based on publications issued by the Oak Ridge National Laboratory (ORNL). Seven input files relating to different age groups (newborn, 1, 5, 10, 15 years, as well as, male and female adults) are presented here. A test example and comparison with other data found in literature are also given. Program summaryTitle of program: INPUT FILES, AMALE, AFEMALE, AGE15, AGE10, AGE5, AGE01, NEWB Catalogue identifier:ADYF_v1_0 Program summary URL

  9. Calculation of the effective dose from natural radioactivity in soil using MCNP code.

    PubMed

    Krstic, D; Nikezic, D

    2010-01-01

    Effective dose delivered by photon emitted from natural radioactivity in soil was calculated in this work. Calculations have been done for the most common natural radionuclides in soil (238)U, (232)Th series and (40)K. A ORNL human phantoms and the Monte Carlo transport code MCNP-4B were employed to calculate the energy deposited in all organs. The effective dose was calculated according to ICRP 74 recommendations. Conversion factors of effective dose per air kerma were determined. Results obtained here were compared with other authors. PMID:20045343

  10. Application of Numerical Phantoms and MCNP Calculation for In Vivo Calibration

    NASA Astrophysics Data System (ADS)

    Franck, D.; Borisov, N. M.; Laval, L.

    The paper reports on development of numeric phantoms for Monte Carlo calculations for in vivo measurements of radionuclides deposited in tissues. The individual properties of each person require rather precise geometric representations. It is particularly important for low energy gamma ray emitting sources as thorium, uranium, plutonium and other actinides. The new utility which allows automatic creation of MCNP initial file from individual scanning information, was developed. It includes segmentation of voxel matrix, obtained with computer tomography, for distinguishing tissues by level of brightness, association colors with certain tissues, source and detector specification and, finally, voxel coupling to reduce the consumed memory and increase speed of calculations.

  11. Visual Scripting.

    ERIC Educational Resources Information Center

    Halas, John

    Visual scripting is the coordination of words with pictures in sequence. This book presents the methods and viewpoints on visual scripting of fourteen film makers, from nine countries, who are involved in animated cinema; it contains concise examples of how a storybook and preproduction script can be prepared in visual terms; and it includes a…

  12. EDITORIAL: Farewell from the outgoing Editor-in-Chief Farewell from the outgoing Editor-in-Chief

    NASA Astrophysics Data System (ADS)

    Molenkamp, Laurens W.

    2011-12-01

    At the end of 2011 I will retire as Editor-in-Chief of Semiconductor Science and Technology, and I am very pleased to announce that the job will be taken over by Professor Kornelius Nielsch. In the ten years I have held this position, I have seen many new topics entering the journal: spintronics, organic semiconductors, and Dirac fermion physics, to name just a few. The journal has also witnessed a strong internationalization of the authorship, with an especially strong increase in contributions from the Far East—a growth that is likely to continue in the coming years. I am certain that Kornelius will do an excellent job in guiding the journal through the developments of the coming decade. I would like to thank the publishing team of SST, or rather the three consecutive teams I witnessed during my tenure at the journal, for the help and support they have given me. The people at IOP Publishing are doing a great job in running the journal, and have made it possible to considerably reduce the time to publication for our submissions. I much enjoyed the collaboration with the other members of the Editorial Board; our annual meetings have always been a source of inspiration. Last, but certainly not least, I would like to thank you, the scientific community, authors, referees and readers, for your continuing support of the journal.

  13. The Technical Editor and the Non-Native Speaker of English.

    ERIC Educational Resources Information Center

    Leki, Ilona

    1990-01-01

    Summarizes current views of second-language acquisition, focusing on the types and origins of the problems of nonnative technical writers. Offers suggestions to help editors avoid or alleviate the problems. (PRA)

  14. Comparative studies on shielding properties of some steel alloys using Geant4, MCNP, WinXCOM and experimental results

    NASA Astrophysics Data System (ADS)

    Singh, Vishwanath P.; Medhat, M. E.; Shirmardi, S. P.

    2015-01-01

    The mass attenuation coefficients, μ/ρ and effective atomic numbers, Zeff of some carbon steel and stainless steel alloys have been calculated by using Geant4, MCNP simulation codes for different gamma ray energies, 279.1 keV, 661.6 keV, 662 keV, 1115.5 keV, 1173 keV and 1332 keV. The simulation results of Zeff using Geant4 and MCNP codes have been compared with possible available experimental results and theoretical WinXcom, and good agreement has been observed. The simulated μ/ρ and Zeff values using Geant4 and MCNP code signifies that both the simulation process can be followed to determine the gamma ray interaction properties of the alloys for energies wherever analogous experimental results may not be available. This kind of studies can be used for various applications such as for radiation dosimetry, medical and radiation shielding.

  15. Uniform requirements for manuscripts submitted to biomedical journals. International Committee of Medical Journal Editors.

    PubMed Central

    1994-01-01

    In the 13 years since it was first published the "Uniform requirements for manuscripts submitted to biomedical journals" (the Vancouver style), developed by the International Committee of Medical Journal Editors, has been widely accepted by both authors and editors; over 400 journals have stated that they will consider manuscripts that conform to its requirements. This is the fourth edition of the "Uniform requirements." PMID:8287338

  16. EDITORIAL: Message from the new Editor-in-Chief

    NASA Astrophysics Data System (ADS)

    Dendy, R.

    2005-01-01

    On 1 January 2005 I become Editor-in-Chief of Plasma Physics and Controlled Fusion. I look forward to assisting contributors, referees and the Board in maintaining the high standards of this international journal, whose bibliometric impact factor has consistently matched or exceeded that of other journals in the field. The robust, good health of Plasma Physics and Controlled Fusion reflects that of its user communities. With a decision to proceed to the construction of ITER apparently imminent, magnetic confinement fusion research is preparing to take a major step forwards. A new generation of laser-plasma interaction facilities for inertial fusion research is also rising at key sites around the world. Technical progress in our field is underpinned by scientific excellence, and the publication of results in Plasma Physics and Controlled Fusion will, I hope, continue to play its part. The journal will continue to offer the benefits of refereeing by two experts, combined with the rapid turnaround achieved by the highly efficient editorial office at the Institute of Physics Publishing in Bristol. Looking elsewhere, there may be opportunities for gentle incremental broadening of the scientific scope of the journal, in the medium term. One looks in particular to those branches of plasma physics that, in recent years, have become more strongly represented in the series of conferences organized by the Plasma Physics Division of the European Physical Society. The recent special issue of Plasma Physics and Controlled Fusion (Plasma Phys. Control. Fusion 46 (2004) B1--592) provides an indication. Finally, it is a pleasure to thank my predecessor, Professor Ian Hutchinson of the Massachusetts Institute of Technology, for handing on his role with the journal in such promising condition.

  17. Comparison of TG-43 dosimetric parameters of brachytherapy sources obtained by three different versions of MCNP codes.

    PubMed

    Zaker, Neda; Zehtabian, Mehdi; Sina, Sedigheh; Koontz, Craig; Meigooni, Ali S

    2016-01-01

    Monte Carlo simulations are widely used for calculation of the dosimetric parameters of brachytherapy sources. MCNP4C2, MCNP5, MCNPX, EGS4, EGSnrc, PTRAN, and GEANT4 are among the most commonly used codes in this field. Each of these codes utilizes a cross-sectional library for the purpose of simulating different elements and materials with complex chemical compositions. The accuracies of the final outcomes of these simulations are very sensitive to the accuracies of the cross-sectional libraries. Several investigators have shown that inaccuracies of some of the cross section files have led to errors in 125I and 103Pd parameters. The purpose of this study is to compare the dosimetric parameters of sample brachytherapy sources, calculated with three different versions of the MCNP code - MCNP4C, MCNP5, and MCNPX. In these simulations for each source type, the source and phantom geometries, as well as the number of the photons, were kept identical, thus eliminating the possible uncertainties. The results of these investigations indicate that for low-energy sources such as 125I and 103Pd there are discrepancies in gL(r) values. Discrepancies up to 21.7% and 28% are observed between MCNP4C and other codes at a distance of 6 cm for 103Pd and 10 cm for 125I from the source, respectively. However, for higher energy sources, the discrepancies in gL(r) values are less than 1.1% for 192Ir and less than 1.2% for 137Cs between the three codes. PMID:27074460

  18. Development of Monteburns: A Code That Links MCNP and ORIGEN2 in an Automated Fashion for Burnup Calculations

    SciTech Connect

    Holly R. Trellue

    1998-12-01

    Monteburns is a fully automated tool that links the Monte Carlo transport code MCNP with the radioactive decay and burnup code 0RIGEN2. Monteburns produces many criticality and burnup computational parameters based on material feed/removal specifications, power(s), and time intervals. This code processes input from the user indicating the system geometry, initial material compositions, feed/removal, and other code-specific parameters. Results from MCNP, 0RIGEN2, and other calculations are then output successively as the code runs. The principle function of monteburns is to first transfer one-group cross sections and fluxes from MCNP to 0RIGEN2, and then transfer the resulting material compositions (after irradiation and/or decay) from 0RIGEN2 back to MCNP in a repeated, cyclic fashion. The main requirement of the code is that the user have a working MCNP input file and other input parameters; all interaction with 0RIGEN2 and other calculations are performed by monteburns. This report presents the results obtained from the benchmarking of monteburns to measured and previously obtained data from traditional Light Water Reactor systems. The majority of the differences seen between the two were less than five percent. These were primarily a result of variances in cross sections between MCNP, cross section libraries used by other codes, and observed values. With this understanding, this code can now be used with confidence for burnup calculations in three-dimensional systems. It was designed for use in the Accelerator Transmutation of Waste project at Los Alamos National Laboratory but is also being applied to the analysis of isotopic production/destruction of transuranic actinides in a reactor system. The code has now been shown to sufficiently support these calculations.

  19. Visual Imagery without Visual Perception?

    ERIC Educational Resources Information Center

    Bertolo, Helder

    2005-01-01

    The question regarding visual imagery and visual perception remain an open issue. Many studies have tried to understand if the two processes share the same mechanisms or if they are independent, using different neural substrates. Most research has been directed towards the need of activation of primary visual areas during imagery. Here we review…

  20. Comparison of a NuScale SMR conceptual core design using CASMO5/simulate5 and MCNP5

    SciTech Connect

    Haugh, B.; Mohamed, A.

    2012-07-01

    A key issue during the initial start-ups of new Small Modular Reactors (SMRs) is the lack of operational data for reactor model validation. To help better understand the accuracy of the reactor analysis codes CASMO5 and SIMULATE5, higher order comparisons to MCNP5 have been performed. These comparisons are for an initial core conceptual design of the NuScale reactor. The data have been evaluated at Hot Zero Power (HZP) conditions. Comparisons of core reactivity, fuel temperature coefficient (FTC), and moderator temperature coefficients (MTC) have been performed. Comparison results show good agreement between CASMO5/SIMULATE5 and MCNP5 for the conceptual initial core design. (authors)

  1. Use of MCNP + GADRAS in Generating More Realistic Gamma-Ray Spectra for Plutonium and HEU Objects

    SciTech Connect

    Rawool-Sullivan, Mohini; Mattingly, John; Mitchell, Dean

    2012-08-07

    The ability to accurately simulate high-resolution gamma spectra from materials that emit both neutrons and gammas is very important to the analysis of special nuclear materials (SNM), e.g., uranium and plutonium. One approach under consideration has been to combine MCNP and GADRAS. This approach is expected to generate more accurate gamma ray spectra for complex three-dimensional geometries than can be obtained from one-dimensional deterministic transport simulations (e.g., ONEDANT). This presentation describes application of combining MCNP and GADRAS in simulating plutonium and uranium spectra.

  2. Radiation shielding evaluation of the BNCT treatment room at THOR: a TORT-coupled MCNP Monte Carlo simulation study.

    PubMed

    Chen, A Y; Liu, Y-W H; Sheu, R J

    2008-01-01

    This study investigates the radiation shielding design of the treatment room for boron neutron capture therapy at Tsing Hua Open-pool Reactor using "TORT-coupled MCNP" method. With this method, the computational efficiency is improved significantly by two to three orders of magnitude compared to the analog Monte Carlo MCNP calculation. This makes the calculation feasible using a single CPU in less than 1 day. Further optimization of the photon weight windows leads to additional 50-75% improvement in the overall computational efficiency. PMID:17825572

  3. Total reaction cross sections in CEM and MCNP6 at intermediate energies

    NASA Astrophysics Data System (ADS)

    Kerby, Leslie M.; Mashnik, Stepan G.

    2015-08-01

    Accurate total reaction cross section models are important to achieving reliable predictions from spallation and transport codes. The latest version of the Cascade Exciton Model (CEM) as incorporated in the code CEM03.03, and the Monte Carlo N-Particle transport code (MCNP6), both developed at Los Alamos National Laboratory (LANL), each use such cross sections. Having accurate total reaction cross section models in the intermediate energy region (∼ 50 MeV to ∼ 5 GeV) is very important for different applications, including analysis of space environments, use in medical physics, and accelerator design, to name just a few. The current inverse cross sections used in the preequilibrium and evaporation stages of CEM are based on the Dostrovsky et al. model, published in 1959. Better cross section models are available now. Implementing better cross section models in CEM and MCNP6 should yield improved predictions for particle spectra and total production cross sections, among other results. Our current results indicate this is, in fact, the case.

  4. TRIPOLI-4® - MCNP5 ITER A-lite neutronic model benchmarking

    NASA Astrophysics Data System (ADS)

    Jaboulay, J.-C.; Cayla, P.-Y.; Fausser, C.; Lee, Y.-K.; Trama, J.-C.; Li-Puma, A.

    2014-06-01

    The aim of this paper is to present the capability of TRIPOLI-4®, the CEA Monte Carlo code, to model a large-scale fusion reactor with complex neutron source and geometry. In the past, numerous benchmarks were conducted for TRIPOLI-4® assessment on fusion applications. Experiments (KANT, OKTAVIAN, FNG) analysis and numerical benchmarks (between TRIPOLI-4® and MCNP5) on the HCLL DEMO2007 and ITER models were carried out successively. In this previous ITER benchmark, nevertheless, only the neutron wall loading was analyzed, its main purpose was to present MCAM (the FDS Team CAD import tool) extension for TRIPOLI-4®. Starting from this work a more extended benchmark has been performed about the estimation of neutron flux, nuclear heating in the shielding blankets and tritium production rate in the European TBMs (HCLL and HCPB) and it is presented in this paper. The methodology to build the TRIPOLI-4® A-lite model is based on MCAM and the MCNP A-lite model (version 4.1). Simplified TBMs (from KIT) have been integrated in the equatorial-port. Comparisons of neutron wall loading, flux, nuclear heating and tritium production rate show a good agreement between the two codes. Discrepancies are mainly included in the Monte Carlo codes statistical error.

  5. Total reaction cross sections in CEM and MCNP6 at intermediate energies

    DOE PAGESBeta

    Kerby, Leslie M.; Mashnik, Stepan G.

    2015-05-14

    Accurate total reaction cross section models are important to achieving reliable predictions from spallation and transport codes. The latest version of the Cascade Exciton Model (CEM) as incorporated in the code CEM03.03, and the Monte Carlo N-Particle transport code (MCNP6), both developed at Los Alamos National Laboratory (LANL), each use such cross sections. Having accurate total reaction cross section models in the intermediate energy region (50 MeV to 5 GeV) is very important for different applications, including analysis of space environments, use in medical physics, and accelerator design, to name just a few. The current inverse cross sections used inmore » the preequilibrium and evaporation stages of CEM are based on the Dostrovsky et al. model, published in 1959. Better cross section models are now available. Implementing better cross section models in CEM and MCNP6 should yield improved predictions for particle spectra and total production cross sections, among other results.« less

  6. The X6XS. 0 cross section library for MCNP-4

    SciTech Connect

    Pruvost, N.L.; Seamon, R.E. ); Rombaugh, C.T. CTR Technical Services, Inc., Arlington, TX )

    1991-06-01

    This report documents the work done by X-6, HSE-6, and CTR Technical Services to produce a comprehensive working cross-section library for MCNP-4 suitable for SUN workstations and similar environments. The resulting library consists of a total of 436 files (one file for each ZAID). The library is 152 Megabytes in Type 1 format and 32 Megabytes in Type 2 format. Type 2 can be used when porting the library from one computer to another of the same make. Otherwise, Type 1 must be used to ensure portability between different computer systems. Instructions for installing the library and adding ZAIDs to it are included here. Also included is a description of the steps necessary to install and test version 4 of MCNP. To improve readability of this report, certain commands and filenames are given in uppercase letters. The actual command or filename on the SUN workstation, however, must be specified in lowercase letters. Any questions regarding the data contained in the library should be directed to X-6 and any questions regarding the installation of the library and the testing that was performed should be directed to HSE-6. 9 refs., 7 tabs.

  7. Physics and Algorithm Enhancements for a Validated MCNP/X Monte Carlo Simulation Tool, Phase VII

    SciTech Connect

    McKinney, Gregg W

    2012-07-17

    Currently the US lacks an end-to-end (i.e., source-to-detector) radiation transport simulation code with predictive capability for the broad range of DHS nuclear material detection applications. For example, gaps in the physics, along with inadequate analysis algorithms, make it difficult for Monte Carlo simulations to provide a comprehensive evaluation, design, and optimization of proposed interrogation systems. With the development and implementation of several key physics and algorithm enhancements, along with needed improvements in evaluated data and benchmark measurements, the MCNP/X Monte Carlo codes will provide designers, operators, and systems analysts with a validated tool for developing state-of-the-art active and passive detection systems. This project is currently in its seventh year (Phase VII). This presentation will review thirty enhancements that have been implemented in MCNPX over the last 3 years and were included in the 2011 release of version 2.7.0. These improvements include 12 physics enhancements, 4 source enhancements, 8 tally enhancements, and 6 other enhancements. Examples and results will be provided for each of these features. The presentation will also discuss the eight enhancements that will be migrated into MCNP6 over the upcoming year.

  8. Evaluation of 2-PI liquid scintillation whole body counter using MCNP

    NASA Astrophysics Data System (ADS)

    Mireles-Garcia, Fernando

    The 2-pi liquid scintillation whole body counter (WBC) at the University of Missouri-Columbia has been evaluated using MCNP-4A (a general Monte Carlo Neutron-Photon transport code, Version 4A). This facility is of importance to a wide variety of applications, such as determination of body fat content in human and animal subjects and measurement of radioactive tracers in animals. Phantoms and mathematical models were used in this research to upgrade the calibration procedures of the WBC. Since the existing protocol assumes a simple efficiency calibration based only upon body mass, it does not account for body shape and gives no methodology for placement of the subject below the detectors. Mathematical models were developed to calculate geometry efficiency for a variety of subjects and geometries utilizing the MCNP-4A transport code. Comparison of the results from simulation with experimental data shows excellent agreement not only in the shape of the curves as a function of subject position but also in absolute magnitude. In the case of the WBC and a phantom consisting of 40 liters of water containing 800 grams of sp+K the error in the magnitude is within 6%, which is easily attributable to the experimental calibration of the detectors. The efficiency of the WBC has been calculated for different weights for modified Adam-E through Adam-L model geometries; hence weight and shape can be modeled carefully and correction can be applied to actual human measurements based upon this work.

  9. Verification of analytic energy moments for the one-dimensional energy dependent neutron diffusion equation with MCNP5 and Attila-7.1.0

    SciTech Connect

    Douglas S. Crawford; Terry A. Ring

    2012-12-01

    The energy dependent neutron diffusion equation (EDNDE) is converted into a moment equation which is solved analytically for the 1-D problem of a bare sphere of pure 235U. The normalized moments 0–5 generated analytically are compared to normalized energy moments, from Monte Carlo N Particle 5 version 1.40 (MCNP5) and Attila-7.1.0-beta version (Attila). The analytic normalized neutron energy moments, fall between the results from MCNP5 (lower bound) and Attila (upper bound) and are accurate compared to MCNP5 neutron energy moments when error in this Monte Carlo simulation are considered. The error range is from 0% to 14%. The Attila moments are less accurate when compared to MCNP5 than the analytical moments derived in this work. The method of moments is shown to be a fast reliable method, compared to either Monte Carlo methods (MCNP5) or 30 multi-energy group methods (Attila).

  10. EDITORIAL: Greetings from the new Editor-in-Chief Greetings from the new Editor-in-Chief

    NASA Astrophysics Data System (ADS)

    Gardner, Jason S.

    2012-01-01

    As I begin my tenure as Editor-in-Chief of Journal of Physics: Condensed Matter (JPCM), I look upon this opportunity as both an honour and a real challenge. The journal is in great shape thanks to the work of my predecessors, Marshall Stoneham and David Ferry. The journal's solid reputation is based largely on the work these gentlemen have done over the past decade. The other main reason for the success of JPCM is the amazing staff in Bristol; keep up the good work, please. When discussing the journal with scientists from all corners of the globe, one thing is always mentioned—JPCM is a very reliable journal with well-written, high-quality papers, and a fast but rigorous peer-review process that provides fair, detailed and constructive referee reports for the benefit of authors. This is due almost entirely to our great authors and referees; we rely on them every day—thank you. As the new Editor-in-Chief I hope to continue to improve still further the journal's status in condensed matter science. As mentioned above, our reputation is excellent, but the reality is that we live in a world of bibliometrics and rankings. Over the past few years JPCM has been repositioned as a journal at the forefront of condensed matter physics, and the impact of the journal should increase further as a result of continued emphasis on commissioning in cutting-edge areas identified by the Editorial Board and the journal team. In addition to regular papers, JPCM has a number of other content streams that authors and readers can benefit from. Fast track communications (FTCs) offer exceptionally fast publication for work of the highest impact and urgency. By their select nature, FTCs benefit from personal treatment by the Editorial Board and the average receipt-to-first-decision time is just 11 days (the average receipt-to-publication time is just 45 days). Topical reviews in JPCM make the journal one of the most authoritative sources of review content for condensed matter physics

  11. EDITORIAL: Greetings from the new Editor-in-Chief Greetings from the new Editor-in-Chief

    NASA Astrophysics Data System (ADS)

    Corkum, Paul

    2011-01-01

    As a journal that reports advances in atomic, molecular and optical science (AMO), Journal of Physics B: Atomic, Molecular and Optical Physics (J. Phys. B) provides the AMO research community with three unique fora: topical reviews, tutorials and special issues. Developed under the leadership of editor Jan Michael Rost and his Editorial Board, these sections have cemented J. Phys. B's reputation as a major journal showcasing the AMO community's advances. For me, an AMO scientist, it is therefore a special pleasure to be entrusted with continuing the tradition of excellence established by Jan Michael and the Editorial Board. I intend to build on this foundation by ensuring that the journal makes full use of these tools. Topical reviews: a unique focus When J. Phys. B becomes the first journal you turn to for initial reviews about important emerging areas in your field, we as an Editorial Board will have succeeded. To us, a topical review is different from a traditional review—a topical review focuses on emerging sub-fields of AMO physics. Its function is to alert and educate our readers about emerging opportunities. Topical reviews can also serve a closely related function for readers: keeping us up-to-date with critical technologies that lie slightly outside our own fields, such as advances in free-electron lasers science, (which will surely affect our field). Our overall goal is to make your research more productive because of the topical reviews you read within the journal. Tutorials J. Phys. B tutorials are aimed at graduate students or researchers venturing into a new field. Just as in my own research group I encourage all graduate students to write their theses in a way that will be useful to both future graduate students and the larger community beyond my group, J. Phys. B has designed tutorials to fill this function on the journal scale. Thus, tutorial authors are able to write in greater depth than can be included in a paper in nature, science or in the

  12. EDITORIAL: Thank you and farewell from the Founding Editor

    NASA Astrophysics Data System (ADS)

    Baskes, Mike

    2005-07-01

    I have been involved with Modelling and Simulation in Materials Science and Engineering (MSMSE) from the very beginning when it was merely an idea, over 14 years ago, to the current journal that is well supported by the community. During my time as Editor there have been many changes in the journal, including the introduction of electronic submissions, web-based services and free printed colour where it is essential to the article, as well as completely free colour online. The journal has seen excellent growth in the number and quality of submissions and the number of articles published continues to rise, enabling us to expand the journal to eight issues in 2005. Web accesses and downloads have greatly surpassed even my wildest dreams. In my opinion, the emergence of MSMSE as a top materials modelling journal has confirmed the vision of Institute of Physics Publishing (IOPP) and the Executive Board that this area of science and engineering was ripe for a specialized journal. I feel that, having seen the journal through the early years and watched it grow into a successful arena for multidisciplinary materials research, it is now an appropriate time for me to hand over the reins. The journal has a great foundation for future growth and development and is supported by an excellent Editorial Board, who have given me a great deal of help and advice over the years. I feel sure that they will continue to support the journal when Bill Curtin, Brown University, takes over on 1 July 2005. Bill has the diverse experience in modelling at the atomic, dislocation, and continuum levels to lead the journal to new heights. Finally I would like to thank all of the readers, authors and referees who have greatly contributed to MSMSE over the years. Thank you for your support and help, and I hope you will continue to support the journal. Last, but not least, I would like to thank the staff at IOPP. Without their expert assistance, the journal could not have been as successful as it is

  13. Advances in reactor physics education: Visualization of reactor parameters

    SciTech Connect

    Snoj, L.; Kromar, M.; Zerovnik, G.

    2012-07-01

    Modern computer codes allow detailed neutron transport calculations. In combination with advanced 3D visualization software capable of treating large amounts of data in real time they form a powerful tool that can be used as a convenient modern educational tool for reactor operators, nuclear engineers, students and specialists involved in reactor operation and design. Visualization is applicable not only in education and training, but also as a tool for fuel management, core analysis and irradiation planning. The paper treats the visualization of neutron transport in different moderators, neutron flux and power distributions in two nuclear reactors (TRIGA type research reactor and a typical PWR). The distributions are calculated with MCNP and CORD-2 computer codes and presented using Amira software. (authors)

  14. CHAIRMEN'S PREFACE AND EDITORS' NOTE: Unification of Fundamental Interactions

    NASA Astrophysics Data System (ADS)

    Brink, Lars; Nilsson, Jan S.; Salomonson, Per; Skagerstam, Bo-Sture

    1987-01-01

    Vainshtein. We had hoped that the Nobel Symposium should be a signal for improved relations between East and West, but in this respect we failed. The Symposium was held in the small town of Marstrand, a summer resort on an island outside Göteborg. The idea was to have it relatively close to home and to show the participants perhaps the best part of the local nature. Another motive was to keep the participants semi-isolated to provide ample time for discussions. With the somewhat heavy programme we found that even so, the days were not long enough. This Symposium was the second Nobel Symposium on elementary particle physics. The first one, also organized by our group, was held in 1968. We hope and believe that the next one need not be awaited another 18 years! The Symposium was made possible by a generous grant from the Nobel Foundation. An additional grant from the Royal Swedish Academy of Sciences was also essential. A grant from Nordita made it possible to invite some ten Nordic observers. We also gratefully acknowledge help with the organization of the Symposium from the city of Goteborg, the city of Kungälv, Volvo, Skandinaviska Enskilda banken, Ericsson AB and IBM Sweden. We thank all the participants for all their efforts, to come to our remote part of the world, to give excellent talks, to write up their talks astonishingly quickly and to share with us so much of their knowledge and expertise. Last but not least we are indebted to the members of the organizing committee, members of the group and the secretarial staff. Goteborg, August 1986 Editors' NoteIn these Proceedings the lectures are given in the order of their oral presentation at the Symposium. Regrettably, a few contributors could not participate (V. Gribov, A. Linde, V. Ogievetsky, M. Shifman and A. M. Polyakov). Their contributions have been placed close to the end of the Proceedings. As these authors did not have the opportunity of correcting the proofs, responsibility for printing errors must rest with

  15. The comparison of two MCNP models used for prompt gamma in vivo detection of cadmium and mercury

    NASA Astrophysics Data System (ADS)

    Atanackovic, J.; Grinyer, J.; Chettle, D. R.; Byun, S. H.

    2007-10-01

    In vivo detection of trace elements is one of the most important research areas at the Medical Physics and Applied Radiation Sciences Department at McMaster University. Prompt gamma neutron activation analysis (PGNAA) used for detection of cadmium and mercury takes place simultaneously at two different experimental sites; the McMaster Nuclear Reactor (MNR) and the 238Pu/Be neutron source site. This particular study consists of two parts. In the first part the water phantoms (125 mL) were used in MCNP simulations. The water phantoms were doped with different concentrations of Cd, Hg and HCl. This is done in order to compare the (n, γ) prompt gamma reaction rate; in fact, the rate of neutron capture by the nuclides of interest; 113Cd, 199Hg and 35Cl. The second part involves, the neutron and photon dosimetry calculations that were performed for both sites using MCNP compatible body builder software developed in Los Alamos. The output of this program is the actual MCNP geometry description for various human anthropomorphic phantoms (different sex and ages). This phantom geometry output is incorporated into the original MCNP geometry and the dosimetry calculations were performed for various organs at risk.

  16. Mathematical Visualization

    ERIC Educational Resources Information Center

    Rogness, Jonathan

    2011-01-01

    Advances in computer graphics have provided mathematicians with the ability to create stunning visualizations, both to gain insight and to help demonstrate the beauty of mathematics to others. As educators these tools can be particularly important as we search for ways to work with students raised with constant visual stimulation, from video games…

  17. Visual Literacy

    ERIC Educational Resources Information Center

    Felten, Peter

    2008-01-01

    Living in an image-rich world does not mean students (or faculty and administrators) naturally possess sophisticated visual literacy skills, just as continually listening to an iPod does not teach a person to critically analyze or create music. Instead, "visual literacy involves the ability to understand, produce, and use culturally significant…

  18. Visual Literacy.

    ERIC Educational Resources Information Center

    Lamberski, Richard J.

    A series of articles examines visual literacy from the perspectives of definition, research, curriculum, and resources. Articles examining the definition of visual literacy approach it in terms of semantics, techniques, and exploratory definition areas. There are surveys of present and potential research, and a discussion of the problem of…

  19. Visual Closure.

    ERIC Educational Resources Information Center

    Groffman, Sidney

    An experimental test of visual closure based on an information-theory concept of perception was devised to test the ability to discriminate visual stimuli with reduced cues. The test is to be administered in a timed individual situation in which the subject is presented with sets of incomplete drawings of simple objects that he is required to name…

  20. Visual Thinking.

    ERIC Educational Resources Information Center

    Arnheim, Rudolf

    Based on the more general principle that all thinking (including reasoning) is basically perceptual in nature, the author proposes that visual perception is not a passive recording of stimulus material but an active concern of the mind. He delineates the task of visually distinguishing changes in size, shape, and position and points out the…

  1. US health journal editors' opinions and policies on research in race, ethnicity, and health.

    PubMed Central

    Bennett, T.; Bhopal, R.

    1998-01-01

    Health research on race and ethnicity has been criticized for lacking rigor in conceptualization, terminology, and analysis. Scientific journals' editorial processes help determine research quality. This survey assessed editors' awareness of current debates, attitudes toward recent recommendations, and involvement in developing editorial policies. Twenty-nine editors of health journals with impact factors of > or = 1 (based on citation ratings) were sent a questionnaire including four key problems identified in research literature and recommendations from federal agencies; 23 (79%) responded. Seven editors relevant policies. Two had read the federal directive on racial and ethnic classification; one was aware of its current review. Most perceived the four key problems as uncommon. The majority agreed with Public Health Service recommendations on race and ethnicity research, except for analyzing effects of racism. Approximately 20% had discussed issues with co-editors, editorial boards, or reviewers. About 40% saw further discussion as beneficial; four planned to draft guidelines. Editors' potential for helping resolve problems in race/ethnicity research is not being realized. Greater participation would be beneficial to public health research and practice. PMID:9685775

  2. Nuclear heat load calculations for the NBSR cold neutron source using MCNP

    SciTech Connect

    Blau, M. ); Rowe, J.M.; Williams, R.E. )

    1993-01-01

    A liquid-hydrogen (LH2) cold neutron source is being designed for installation in the 20-MW National Bureau of Standards reactor (NBSR) at National Institute of Standards and Technology to replace the D[sub 2]O-ice cold source currently in use. An accurate estimate of the heat deposited in the cold source is needed to ensure that it can be adequately cooled for successful operation. The heat load is caused by the interaction of neutrons and gamma rays with the cold moderator and the walls of the moderator chamber. The Monte Carlo code, MCNP (Version 4.2), was used to model the entire NBSR core and both the existing and the proposed cold sources. The model was used to calculate not only the heat load but also the reactivity and neutron gain of each source.

  3. Image enhancement using MCNP5 code and MATLAB in neutron radiography.

    PubMed

    Tharwat, Montaser; Mohamed, Nader; Mongy, T

    2014-07-01

    This work presents a method that can be used to enhance the neutron radiography (NR) image for objects with high scattering materials like hydrogen, carbon and other light materials. This method used Monte Carlo code, MCNP5, to simulate the NR process and get the flux distribution for each pixel of the image and determines the scattered neutron distribution that caused image blur, and then uses MATLAB to subtract this scattered neutron distribution from the initial image to improve its quality. This work was performed before the commissioning of digital NR system in Jan. 2013. The MATLAB enhancement method is quite a good technique in the case of static based film neutron radiography, while in neutron imaging (NI) technique, image enhancement and quantitative measurement were efficient by using ImageJ software. The enhanced image quality and quantitative measurements were presented in this work. PMID:24583508

  4. MCNP study for epithermal neutron irradiation of an isolated liver at the Finnish BNCT facility.

    PubMed

    Kotiluoto, P; Auterinen, I

    2004-11-01

    A successful boron neutron capture treatment (BNCT) of a patient with multiple liver metastases has been first given in Italy, by placing the removed organ into the thermal neutron column of the Triga research reactor of the University of Pavia. In Finland, FiR 1 Triga reactor with an epithermal neutron beam well suited for BNCT has been extensively used to irradiate patients with brain tumors such as glioblastoma and recently also head and neck tumors. In this work we have studied by MCNP Monte Carlo simulations, whether it would be beneficial to treat an isolated liver with epithermal neutrons instead of thermal ones. The results show, that the epithermal field penetrates deeper into the liver and creates a build-up distribution of the boron dose. Our results strongly encourage further studying of irradiation arrangement of an isolated liver with epithermal neutron fields. PMID:15308144

  5. MCNP simulation of the dose distribution in liver cancer treatment for BNC therapy

    NASA Astrophysics Data System (ADS)

    Krstic, Dragana; Jovanovic, Zoran; Markovic, Vladimir; Nikezic, Dragoslav; Urosevic, Vlade

    2014-10-01

    The Boron Neutron Capture Therapy ( BNCT) is based on selective uptake of boron in tumour tissue compared to the surrounding normal tissue. Infusion of compounds with boron is followed by irradiation with neutrons. Neutron capture on 10B, which gives rise to an alpha particle and recoiled 7Li ion, enables the therapeutic dose to be delivered to tumour tissue while healthy tissue can be spared. Here, therapeutic abilities of BNCT were studied for possible treatment of liver cancer using thermal and epithermal neutron beam. For neutron transport MCNP software was used and doses in organs of interest in ORNL phantom were evaluated. Phantom organs were filled with voxels in order to obtain depth-dose distributions in them. The result suggests that BNCT using an epithermal neutron beam could be applied for liver cancer treatment.

  6. MCNP simulation of the dose distribution in liver cancer treatment for BNC therapy

    NASA Astrophysics Data System (ADS)

    Krstic, Dragana; Jovanovic, Zoran; Markovic, Vladimir; Nikezic, Dragoslav; Urosevic, Vlade

    2014-10-01

    The Boron Neutron Capture Therapy (BNCT) is based on selective uptake of boron in tumour tissue compared to the surrounding normal tissue. Infusion of compounds with boron is followed by irradiation with neutrons. Neutron capture on 10B, which gives rise to an alpha particle and recoiled 7Li ion, enables the therapeutic dose to be delivered to tumour tissue while healthy tissue can be spared. Here, therapeutic abilities of BNCT were studied for possible treatment of liver cancer using thermal and epithermal neutron beam. For neutron transport MCNP software was used and doses in organs of interest in ORNL phantom were evaluated. Phantom organs were filled with voxels in order to obtain depth-dose distributions in them. The result suggests that BNCT using an epithermal neutron beam could be applied for liver cancer treatment.

  7. Borehole parametric study for neutron induced capture gamma-ray spectrometry using the MCNP code.

    PubMed

    Shahriari, M; Sohrabpour, M

    2000-01-01

    The MCNP Monte Carlo code has been used to simulate neutron transport from an Am-Be source into a granite formation surrounding a borehole. The effects of the moisture and the neutron poison on the thermal neutron flux distribution and the capture by the absorbing elements has been calculated. Thermal and nonthermal captures for certain absorbers having resonance structures in the epithermal and fast energy regions such as W and Si were performed. It is shown that for those absorbers having large resonances in the epithermal regions when they are present in dry formation or when accompanied by neutron poisons the resonance captures may be significant compared to the thermal captures. PMID:10670932

  8. MCNP-DSP calculations of measurements with uranyl nitrate solution system

    SciTech Connect

    Valentine, T.E.

    1998-09-01

    The {sup 252}Cf-source-driven noise analysis method has been used to determine the subcriticality of various configurations of fissile materials. In the past, the application of this method was limited because point-kinetics models had to be used to interpret the data; however, with the development of the Monte Carlo code MCNP-DSP, the measurements can be analyzed using the more general Monte Carlo models. The results of the Monte carlo calculations will be dependent on the ability to model the experiment accurately and on the nuclear data used to perform the calculations. This paper presents a comparison of the measured and calculated ratio of spectral densities for a subset of measurements performed with a uranyl nitrate solution tank filled to various heights. The results presented are for calculations that were performed with both ENDF/B-IV and ENDF/B-V cross-section data sets.

  9. Comparison of discrete and continuous thermal neutron scattering treatments in MCNP5

    SciTech Connect

    Pavlou, A. T.; Brown, F. B.; Martin, W. R.; Kiedrowski, B. C.

    2012-07-01

    The standard discrete thermal neutron S({alpha},{beta}) scattering treatment in MCNP5 is compared with a continuous S({alpha},{beta}) scattering treatment using a criticality suite of 119 benchmark cases and ENDF/B-VII.0 nuclear data. In the analysis, six bound isotopes are considered: beryllium metal, graphite, hydrogen in water, hydrogen in polyethylene, beryllium in beryllium oxide and oxygen in beryllium oxide. Overall, there are only small changes in the eigenvalue (k{sub eff}) between discrete and continuous treatments. In the comparison of 64 cases that utilize S({alpha},{beta}) scattering, 62 agreed at the 95% confidence level, and the 2 cases with differences larger than 3 {sigma} agreed within 1 {sigma} when more neutrons were run in the calculations. The results indicate that the changes in eigenvalue between continuous and discrete treatments are random, small, and well within the uncertainty of measured data for reactor criticality experiments. (authors)

  10. Neutron and photon shielding benchmark calculations by MCNP on the LR-0 experimental facility.

    PubMed

    Hordósy, G

    2005-01-01

    In the framework of the REDOS project, the space-energy distribution of the neutron and photon flux has been calculated over the pressure vessel simulator thickness of the LR-0 experimental reactor, Rez, Czech Republic. The results calculated by the Monte Carlo code MCNP4C are compared with the measurements performed in the Nuclear Research Institute, Rez. The spectra have been measured at the barrel, in front of, inside and behind the pressure vessel in different configurations. The neutron measurements were performed in the energy range 0.1-10 MeV. This work has been done in the frame of the 5th Frame Work Programme of the European Community 1998-2002. PMID:16604591

  11. Multi-canister overpack project -- verification and validation, MCNP 4A

    SciTech Connect

    Goldmann, L.H.

    1997-11-10

    This supporting document contains the software verification and validation (V and V) package used for Phase 2 design of the Spent Nuclear Fuel Multi-Canister Overpack. V and V packages for both ANSYS and MCNP are included. Description of Verification Run(s): This software requires that it be compiled specifically for the machine it is to be used on. Therefore to facilitate ease in the verification process the software automatically runs 25 sample problems to ensure proper installation and compilation. Once the runs are completed the software checks for verification by performing a file comparison on the new output file and the old output file. Any differences between any of the files will cause a verification error. Due to the manner in which the verification is completed a verification error does not necessarily indicate a problem. This indicates that a closer look at the output files is needed to determine the cause of the error.

  12. Accelerated equilibrium core composition search using a new MCNP-based simulator

    NASA Astrophysics Data System (ADS)

    Seifried, Jeffrey E.; Gorman, Phillip M.; Vujic, Jasmina L.; Greenspan, Ehud

    2014-06-01

    MocDown is a new Monte Carlo depletion and recycling simulator which couples neutron transport with MCNP and transmutation with ORIGEN. This modular approach to depletion allows for flexible operation by incorporating the accelerated progression of a complex fuel processing scheme towards equilibrium and by allowing for the online coupling of thermo-fluids feedback. MocDown also accounts for the variation of decay heat with fuel isotopics evolution. In typical cases, MocDown requires just over a day to find the equilibrium core composition for a multi-recycling fuel cycle, with a self-consistent thermo-fluids solution-a task that required between one and two weeks using previous Monte Carlo-based approaches.

  13. Gas Core Reactor Numerical Simulation Using a Coupled MHD-MCNP Model

    NASA Technical Reports Server (NTRS)

    Kazeminezhad, F.; Anghaie, S.

    2008-01-01

    Analysis is provided in this report of using two head-on magnetohydrodynamic (MHD) shocks to achieve supercritical nuclear fission in an axially elongated cylinder filled with UF4 gas as an energy source for deep space missions. The motivation for each aspect of the design is explained and supported by theory and numerical simulations. A subsequent report will provide detail on relevant experimental work to validate the concept. Here the focus is on the theory of and simulations for the proposed gas core reactor conceptual design from the onset of shock generations to the supercritical state achieved when the shocks collide. The MHD model is coupled to a standard nuclear code (MCNP) to observe the neutron flux and fission power attributed to the supercritical state brought about by the shock collisions. Throughout the modeling, realistic parameters are used for the initial ambient gaseous state and currents to ensure a resulting supercritical state upon shock collisions.

  14. Calculation of conversion coefficients for clinical photon spectra using the MCNP code.

    PubMed

    Lima, M A F; Silva, A X; Crispim, V R

    2004-01-01

    In this work, the MCNP4B code has been employed to calculate conversion coefficients from air kerma to the ambient dose equivalent, H*(10)/Ka, for monoenergetic photon energies from 10 keV to 50 MeV, assuming the kerma approximation. Also estimated are the H*(10)/Ka for photon beams produced by linear accelerators, such as Clinac-4 and Clinac-2500, after transmission through primary barriers of radiotherapy treatment rooms. The results for the conversion coefficients for monoenergetic photon energies, with statistical uncertainty <2%, are compared with those in ICRP publication 74 and good agreements were obtained. The conversion coefficients calculated for real clinic spectra transmitted through walls of concrete of 1, 1.5 and 2 m thick, are in the range of 1.06-1.12 Sv Gy(-1). PMID:15367760

  15. Mathematical Phantom Modelled with MCNP-4B code for Individual Patient Dosimetry

    NASA Astrophysics Data System (ADS)

    Gual, Maritza Rodríguez; Valle, Saúl Hernández

    2002-08-01

    In this work was modeled the ORNL mathematical phantom designed by Cristy and Eckerman in 1987 using the MCNP-4B code with the objective of validating the systems of patient specific dosimetry used in the hospitals. The mathematical phantoms modeling with Monte Carlo guarantee estimates doses more exact in the therapy of the cancer with radionuclides because of difference of the anthropomorphic phantoms, are free of engines that are one of the reason of present errors in the experimental mesurements. As a result of this work will be provided mathematical phantom that reproduces the anatomy of the human organism for a standard "reference man". This paper show the specific absorbed fraction of photon energy in the different organ source for energy of 1 MeV and the results are compared with the published values by Cristy and Eckerman in 1987[1].

  16. STK Integrated Message Production List Editor (SIMPLE) for CEO Operations

    NASA Technical Reports Server (NTRS)

    Trenchard, Mike; Heydorn, James

    2014-01-01

    Late in fiscal year 2011, the Crew Earth Observations (CEO) team was tasked to upgrade and replace its mission planning and mission operations software systems, which were developed in the Space Shuttle era of the 1980s and 1990s. The impetuses for this change were the planned transition of all workstations to the Windows 7 64-bit operating system and the desire for more efficient and effective use of Satellite Tool Kit (STK) software required for reliable International Space Station (ISS) Earth location tracking. An additional requirement of this new system was the use of the same SQL database of CEO science sites from the SMMS, which was also being developed. STK Integrated Message Production List Editor (SIMPLE) is the essential, all-in-one tool now used by CEO staff to perform daily ISS mission planning to meet its requirement to acquire astronaut photography of specific sites on Earth. The sites are part of a managed, long-term database that has been defined and developed for scientific, educational, and public interest. SIMPLE's end product is a set of basic time and location data computed for an operator-selected set of targets that the ISS crew will be asked to photograph (photography is typically planned 12 to 36 hours out). The CEO operator uses SIMPLE to (a) specify a payload operations planning period; (b) acquire and validate the best available ephemeris data (vectors) for the ISS during the planning period; (c) ingest and display mission-specific site information from the CEO database; (d) identify and display potential current dynamic event targets as map features; (e) compute and display time and location information for each target; (f) screen and select targets based on known crew availability constraints, obliquity constraints, and real-time evaluated constraints to target visibility due to illumination (sun elevation) and atmospheric conditions (weather); and finally (g) incorporate basic, computed time and location information for each selected

  17. Assessment of doses caused by electrons in thin layers of tissue-equivalent materials, using MCNP.

    PubMed

    Heide, Bernd

    2013-10-01

    Absorbed doses caused by electron irradiation were calculated with Monte Carlo N-Particle transport code (MCNP) for thin layers of tissue-equivalent materials. The layers were so thin that the calculation of energy deposition was on the border of the scope of MCNP. Therefore, in this article application of three different methods of calculation of energy deposition is discussed. This was done by means of two scenarios: in the first one, electrons were emitted from the centre of a sphere of water and also recorded in that sphere; and in the second, an irradiation with the PTB Secondary Standard BSS2 was modelled, where electrons were emitted from an (90)Sr/(90)Y area source and recorded inside a cuboid phantom made of tissue-equivalent material. The speed and accuracy of the different methods were of interest. While a significant difference in accuracy was visible for one method in the first scenario, the difference in accuracy of the three methods was insignificant for the second one. Considerable differences in speed were found for both scenarios. In order to demonstrate the need for calculating the dose in thin small zones, a third scenario was constructed and simulated as well. The third scenario was nearly equal to the second one, but a pike of lead was assumed to be inside the phantom in addition. A dose enhancement (caused by the pike of lead) of ∼113 % was recorded for a thin hollow cylinder at a depth of 0.007 cm, which the basal-skin layer is referred to in particular. Dose enhancements between 68 and 88 % were found for a slab with a radius of 0.09 cm for all depths. All dose enhancements were hardly noticeable for a slab with a cross-sectional area of 1 cm(2), which is usually applied to operational radiation protection. PMID:23576794

  18. ACTI - An MCNP Data Library for Prompt Gamma-Ray Spectroscopy.

    SciTech Connect

    Frankle, S. C.; Reedy, R. C.; Young, P. G. ,

    2002-01-01

    Prompt gamma-ray spectroscopy is used in a wide variety of applications for determining material compositions. High-quality photon-production data from thermal-neutron capture reactions are essential for these applications. Radiation transport codes, such as MCNP{trademark}, are often used to design detector systems, determine minimum detection thresholds, etc. These transport codes rely on evaluated nuclear databases such as ENDF (Evaluated Nuclear Data File) to provide the fundamental data used in the transport calculations. Often the photon-production data from incident neutron reactions in the evaluations are of relatively poor quality. We have compiled the best experimental data for thermal-neutron capture for the naturally occurring isotopes for elements from H through Zn as well as for {sup 70,72,73,74,76}Ge, {sup 149}Sm, {sup 155,157}Gd, {sup 181}Ta and {sup 182,183,184,186}W. This compilation has been used to update the ENDF evaluations for {sup 1}H, {sup 4}He, {sup 9}Be, {sup 14}N, {sup 16}O, {sup 19}F, Na, Mg, {sup 27}Al, {sup 32}S, S, {sup 35,37}Cl, K, Ca, {sup 45}Sc, Ti, {sup 51}V, {sup 50,52,53,54}Cr, {sup 55}Mn, {sup 54,56,57,58}Fe, {sup 58,60,61,62,64}Ni, {sup 63,65}Cu and {sup 182,183,184,186}W. In addition, the inelastic cross sections and corresponding secondary-photon distributions were updated for {sup 16}O. Complete new evaluations were submitted to ENDF for {sup 35,37}Cl. This paper will discuss the evaluation effort and the production of the MCNP data library, ACTI, based on the new evaluations. Data from the ENDF evaluations for {sup 28-30}Si were also included in the ACTI library for completeness. The silicon evaluations were updated in 1997 and include the latest experimental data for radiative capture.

  19. Visual cognition

    PubMed Central

    Cavanagh, Patrick

    2011-01-01

    Visual cognition, high-level vision, mid-level vision and top-down processing all refer to decision-based scene analyses that combine prior knowledge with retinal input to generate representations. The label “visual cognition” is little used at present, but research and experiments on mid- and high-level, inference-based vision have flourished, becoming in the 21st century a significant, if often understated part, of current vision research. How does visual cognition work? What are its moving parts? This paper reviews the origins and architecture of visual cognition and briefly describes some work in the areas of routines, attention, surfaces, objects, and events (motion, causality, and agency). Most vision scientists avoid being too explicit when presenting concepts about visual cognition, having learned that explicit models invite easy criticism. What we see in the literature is ample evidence for visual cognition, but few or only cautious attempts to detail how it might work. This is the great unfinished business of vision research: at some point we will be done with characterizing how the visual system measures the world and we will have to return to the question of how vision constructs models of objects, surfaces, scenes, and events. PMID:21329719

  20. Transferable Output ASCII Data (TOAD) editor version 1.0 user's guide

    NASA Technical Reports Server (NTRS)

    Bingel, Bradford D.; Shea, Anne L.; Hofler, Alicia S.

    1991-01-01

    The Transferable Output ASCII Data (TOAD) editor is an interactive software tool for manipulating the contents of TOAD files. The TOAD editor is specifically designed to work with tabular data. Selected subsets of data may be displayed to the user's screen, sorted, exchanged, duplicated, removed, replaced, inserted, or transferred to and from external files. It also offers a number of useful features including on-line help, macros, a command history, an 'undo' option, variables, and a full compliment of mathematical functions and conversion factors. Written in ANSI FORTRAN 77 and completely self-contained, the TOAD editor is very portable and has already been installed on SUN, SGI/IRIS, and CONVEX hosts.

  1. A Tcl/Tk-Based, Intelligent Graphical Editor for Preparing HST Programs

    NASA Astrophysics Data System (ADS)

    Asson, D. J.; Bose, A.; Krueger, A.

    The Space Telescope Science Institute (STScI) built the Proposal Editor (PED) system to be an intelligent graphical editor for creating a detailed observing program for the Hubble Space Telescope (HST). Previously, users would type in an observing program in a text editor, and then essentially compile it to check for errors. PED gives users an interactive session that provides menus and selections whenever possible, eliminating many possible errors resulting from typos. Multiple choice selections include the invalid values with explanations as to why they are invalid. A declarative constraint mechanism is used to encode legal and illegal values for individual program parts as well as relationships between parts. Error checking is provided on individual parts, as well as on the program as a whole.

  2. An Interactive, 3D Fault Editor for VR Environments

    NASA Astrophysics Data System (ADS)

    van Aalsburg, J.; Yikilmaz, M. B.; Kreylos, O.; Kellogg, L. H.; Rundle, J. B.

    2008-12-01

    Digitial Fault Models (DFM) play a vital role in the study of earthquake dynamics, fault-earthquake interactions, and seismicity. DFMs serve as input for finite-element method (FEM) or other earthquake simulations such as Virtual California. Generally, digital fault models are generated by importing a digitized and georeferenced (2D) fault map and/or a hillshade image of the study area into a geographical information system (GIS) application, where individual fault lines are traced by the user. Data assimilation and creation of a DFM, or updating an existing DFM based on new observations, is a tedious and time-consuming process. In order to facilitate the creation process, we are developing an immersive virtual reality (VR) application to visualize and edit fault models. This program is designed to run in immersive environments such as a CAVE (walk-in VR environment), but also works in a wide range of other environments, including desktop systems and GeoWalls. It is being developed at the UC Davis W.M. Keck Center for Active Visualization in the Earth Sciences (KeckCAVES, http://www.keckcaves.org). Our program allows users to create new models or modify existing ones; for instance by repositioning individual fault-segments, by changing the dip angle, or by modifying (or assigning) the value of a property associated with a particular fault segment (i.e. slip rate). With the addition of high resolution Digital Elevation Models (DEM) , georeferenced active tectonic fault maps and earthquake hypocenters, the user can accurately add new segments to an existing model or create a fault model entirely from scratch. Interactively created or modified models can be written to XML files at any time; from there the data may easily be converted into various formats required by the analysis software or simulation. We believe that the ease of interaction provided by VR technology is ideally suited to the problem of creating and editing digital fault models. Our software provides

  3. A visual programming environment for the Navier-Stokes computer

    NASA Technical Reports Server (NTRS)

    Tomboulian, Sherryl; Crockett, Thomas W.; Middleton, David

    1988-01-01

    The Navier-Stokes computer is a high-performance, reconfigurable, pipelined machine designed to solve large computational fluid dynamics problems. Due to the complexity of the architecture, development of effective, high-level language compilers for the system appears to be a very difficult task. Consequently, a visual programming methodology has been developed which allows users to program the system at an architectural level by constructing diagrams of the pipeline configuration. These schematic program representations can then be checked for validity and automatically translated into machine code. The visual environment is illustrated by using a prototype graphical editor to program an example problem.

  4. Visual impairment.

    PubMed

    Ellenberger, Carl

    2016-01-01

    This chapter can guide the use of imaging in the evaluation of common visual syndromes: transient visual disturbance, including migraine and amaurosis fugax; acute optic neuropathy complicating multiple sclerosis, neuromyelitis optica spectrum disorder, Leber hereditary optic neuropathy, and Susac syndrome; papilledema and pseudotumor cerebri syndrome; cerebral disturbances of vision, including posterior cerebral arterial occlusion, posterior reversible encephalopathy, hemianopia after anterior temporal lobe resection, posterior cortical atrophy, and conversion blindness. Finally, practical efforts in visual rehabilitation by sensory substitution for blind patients can improve their lives and disclose new information about the brain. PMID:27430448

  5. Guest Editor's introduction: Special issue on distributed virtual environments

    NASA Astrophysics Data System (ADS)

    Lea, Rodger

    1998-09-01

    Distributed virtual environments (DVEs) combine technology from 3D graphics, virtual reality and distributed systems to provide an interactive 3D scene that supports multiple participants. Each participant has a representation in the scene, often known as an avatar, and is free to navigate through the scene and interact with both the scene and other viewers of the scene. Changes to the scene, for example, position changes of one avatar as the associated viewer navigates through the scene, or changes to objects in the scene via manipulation, are propagated in real time to all viewers. This ensures that all viewers of a shared scene `see' the same representation of it, allowing sensible reasoning about the scene. Early work on such environments was restricted to their use in simulation, in particular in military simulation. However, over recent years a number of interesting and potentially far-reaching attempts have been made to exploit the technology for a range of other uses, including: Social spaces. Such spaces can be seen as logical extensions of the familiar text chat space. In 3D social spaces avatars, representing participants, can meet in shared 3D scenes and in addition to text chat can use visual cues and even in some cases spatial audio. Collaborative working. A number of recent projects have attempted to explore the use of DVEs to facilitate computer-supported collaborative working (CSCW), where the 3D space provides a context and work space for collaboration. Gaming. The shared 3D space is already familiar, albeit in a constrained manner, to the gaming community. DVEs are a logical superset of existing 3D games and can provide a rich framework for advanced gaming applications. e-commerce. The ability to navigate through a virtual shopping mall and to look at, and even interact with, 3D representations of articles has appealed to the e-commerce community as it searches for the best method of presenting merchandise to electronic consumers. The technology

  6. An interactive editor for definition of touch-sensitive zones for a graphic display

    NASA Technical Reports Server (NTRS)

    Monroe, Burt L., III; Jones, Denise R.

    1987-01-01

    In the continuing effort to develop more efficient man-machine communications methods, touch displays have shown potential as straightforward input systems. The development of software necessary to handle such systems, however, can become tedious. In order to reduce the need for redundant programming, a touch editor has been developed which allows a programmer to interactively define touch-sensitive areas for a graphic display. The information produced during the editing process is written to a data file, which can be accessed easily when needed by an application program. This paper outlines the structure, logic, and use of the editor, as well as the hardware with which it is presently compatible.

  7. Conflicts of interest for medical publishers and editors: protecting the integrity of scientific scholarship.

    PubMed

    Desai, Sapan S; Shortell, Cynthia K

    2011-09-01

    Competition of interest may exist at all levels in the medical publication process. Ensuring the integrity of scientific scholarship involves protecting editorial independence, promoting the use of scientific arbitration boards, promoting transparency throughout all stages of publication, and protecting the relationship between the publisher and its editors through an effective legal framework. It is incumbent upon the publisher, editors, authors, and readers to ensure that the highest standards of scientific scholarship are upheld. Doing so will help reduce fraud and misrepresentation in medical research and increase the trustworthiness of landmark findings in science. PMID:21872119

  8. Visual cognition

    SciTech Connect

    Pinker, S.

    1985-01-01

    This book consists of essays covering issues in visual cognition presenting experimental techniques from cognitive psychology, methods of modeling cognitive processes on computers from artificial intelligence, and methods of studying brain organization from neuropsychology. Topics considered include: parts of recognition; visual routines; upward direction; mental rotation, and discrimination of left and right turns in maps; individual differences in mental imagery, computational analysis and the neurological basis of mental imagery: componental analysis.

  9. Guest Editor's introduction: Special issue on distributed virtual environments

    NASA Astrophysics Data System (ADS)

    Lea, Rodger

    1998-09-01

    Distributed virtual environments (DVEs) combine technology from 3D graphics, virtual reality and distributed systems to provide an interactive 3D scene that supports multiple participants. Each participant has a representation in the scene, often known as an avatar, and is free to navigate through the scene and interact with both the scene and other viewers of the scene. Changes to the scene, for example, position changes of one avatar as the associated viewer navigates through the scene, or changes to objects in the scene via manipulation, are propagated in real time to all viewers. This ensures that all viewers of a shared scene `see' the same representation of it, allowing sensible reasoning about the scene. Early work on such environments was restricted to their use in simulation, in particular in military simulation. However, over recent years a number of interesting and potentially far-reaching attempts have been made to exploit the technology for a range of other uses, including: Social spaces. Such spaces can be seen as logical extensions of the familiar text chat space. In 3D social spaces avatars, representing participants, can meet in shared 3D scenes and in addition to text chat can use visual cues and even in some cases spatial audio. Collaborative working. A number of recent projects have attempted to explore the use of DVEs to facilitate computer-supported collaborative working (CSCW), where the 3D space provides a context and work space for collaboration. Gaming. The shared 3D space is already familiar, albeit in a constrained manner, to the gaming community. DVEs are a logical superset of existing 3D games and can provide a rich framework for advanced gaming applications. e-commerce. The ability to navigate through a virtual shopping mall and to look at, and even interact with, 3D representations of articles has appealed to the e-commerce community as it searches for the best method of presenting merchandise to electronic consumers. The technology

  10. Improving the quality of papers submitted to dental journals: Transcription of session for editors, associate editors, publishers and others with an interest in scientific publishing held at IADR meeting in Cape Town on Wednesday, 25 June 2014.

    PubMed

    Eaton, Kenneth A; Giannobile, William V; Sourgen, Deborah L; Balaji, S M; Honkala, Eino; Lynch, Christopher D

    2015-08-01

    This satellite symposium was the fourth in a series for editors, publishers, reviewers and all those with an interest in scientific publishing. It was held on Wednesday 25th June 2014 at the IADR International meeting in Cape Town, South Africa. The symposium attracted more than 180 attendees. This symposium placed an emphasis on how the quality of papers submitted to dental journals could be improved. The panel included representation from editors, researchers and publishers from North America, India and the Gulf States. The symposium identified a number of challenges for editors and publishers, including the poor quality of many papers submitted to dental and other scientific journals, plagiarism, attempted duplicate publication and sometimes fraudulent results. Where possible speakers are identified by name. A subsequent symposium was held during the IADR meeting in Boston on March 11th 2015. Involvement open to editors, associate editors, publishers and others with an interest in scientific publishing. PMID:25748020

  11. EDITORIAL: Editorial from the new Editor-in-Chief for 2014 Editorial from the new Editor-in-Chief for 2014

    NASA Astrophysics Data System (ADS)

    Graham, W. G.

    2014-02-01

    I am honoured to take on the leadership of Plasma Sources Science and Technology (PSST) as the successor to Professor Mark J Kushner, with whom I have had the pleasure to work on the journal for many years. Under Mark's insightful and energetic leadership over the last six years, PSST has cemented its position as the journal of choice within its subject area and is now one of the most successful journals in the field. In this first issue of 2014, I would like to reflect on some of the events and achievements of 2013. At the start of the year the PSST Editorial Board, recognizing the vital importance of atomic, molecular and optical (AMO) data to low-temperature plasma physics, agreed that PSST would accept papers reporting such new data, generated through both experiment and theory. Jonathan Tennyson joined the Editorial Board to represent this area. In March Anne Bourdon joined the Associate Editor team and has since then played a key part in the journal's review process alongside our other Editors. During the autumn, PSST moved to a new editorial management system. In December Deborah O'Connell was awarded the 2013 Hershkowitz Early Career Award and Review and joins the Editorial Board as of 2014. I would also like to thank Miles Turner for his work in leading the drafting of a guide on the details necessary in the reporting of the results of computer simulations; the main conclusions of this report have been incorporated into the journal policy. Overall 2013 has been another successful year for PSST; paper submissions were up by 8% on the previous year and there was the highest ever number of downloads of PSST papers in one year. Another noteworthy feature of 2013 was the continuing improvement in publication times while maintaining our high standards for acceptance and providing expert feedback coupled with encouragement particularly to younger researchers and groups. Largely as a result of the hard work of our referees and Associate Editors, the average time

  12. A Study of the Coorientation of High School Principals, Journalism Teachers, and Local Newspaper Editors in Selected Iowa Communities.

    ERIC Educational Resources Information Center

    Peterson, Jane W.

    A study investigated the extent to which high school journalism teachers, principals, and local newspaper editors in selected Iowa communities have a common understanding of each other and the issues of high school journalism. A questionnaire sent to 187 newspaper editors, high school principals, and journalism teachers was returned by 118…

  13. What Editors and Journalism Educators Expect from Journalism Education; An ANPA News Research Center Survey. News Research Bulletin No. 12.

    ERIC Educational Resources Information Center

    Hulteng, John L.

    The purpose of this survey was to assemble data about the expectations of editors and journalism educators as to journalism education, with the objective of providing a basis for an informed dialogue about ways to advance and support education for journalism. Some of the findings were: editors much less than educators perceived newly-hired…

  14. Referees, editors, and publication practices: Improving the reliability and usefulness of the peer review system

    NASA Astrophysics Data System (ADS)

    Cicchetti, Domenic V.

    1997-03-01

    The documented low levels of reliability of the peer review process present a serious challenge to editors who must often base their publication decisions on conflicting referee recommendations. The purpose of this article is to discuss this process and examine ways to produce a more reliable and useful peer review system.

  15. Letter to the Editor Re: Nissensohn M. et al.; Nutrients 2016, 8, 232.

    PubMed

    Ferreira-Pêgo, Cíntia; Babio, Nancy; Salas-Salvadó, Jordi

    2016-01-01

    Dear Editor, We read with interest the recently published original article entitled "Beverage Consumption Habits and Association with TotalWater and Energy Intakes in the Spanish Population: Findings of the ANIBES Study" by Nissensohn et al. [1] in Nutrients.[...]. PMID:27472360

  16. Print versus Electronic: Editors' Insights on the Costs and Benefits of Online Journals.

    ERIC Educational Resources Information Center

    Angell, Brian D.; Smith, Gabie E.

    1998-01-01

    Responses from 26 of 40 editors of electronic journals indicates that 57% were motivated to go online by creative possibilities; only 42% had existing print-journal counterparts; 34.6% felt they reach a broader or different audience online; and 50% felt online journals were less costly and had the advantage of speed of production. (SK)

  17. An International Call for Democratizing the Academic Journal Culture from a Community of Editors

    ERIC Educational Resources Information Center

    Mullen, Carol A.; Pryor, Caroline R.; Browne-Ferrigno, Tricia; Harris, Sandra L.

    2013-01-01

    In our reflective essay from our multiple perspectives as journal editors, peer reviewers, and published authors, we present ideas about editorial support, democracy, and innovation in the publishing process. As four tenured professors who work in universities in the states of Illinois, Virginia, Texas, and Kentucky, we are a community of editors…

  18. The Creators of "Making Up Megaboy": A Writer/Illustrator/Editor Conversation.

    ERIC Educational Resources Information Center

    Walter, Virginia; Roeckelein, Katrina; Jackson, Richard

    1998-01-01

    Presents a conversation between editor Richard Jackson, author Virginia Walter, and illustrator Katrina Roeckelein that traces the creation of "Making Up Megaboy," a story that reconstructs a killing by a 12-year-old boy. Highlights include questions about possible readership, types of illustrations needed, and the artfulness of books. (LRW)

  19. Using letters to the editor to try to bring science to the public

    NASA Astrophysics Data System (ADS)

    Aubrecht, Gordon

    2009-10-01

    The local paper here, the Delaware Gazette, publishes many letters from global warming skeptics and people ignorant of energy policy. I explain how I attempt to bring some sense to the situation through reply letters to the editor. Scientists need to express scientific views in public as our duty to fellow citizens.

  20. Evolution of Novice Programming Environments: The Structure Editors of Carnegie Mellon University.

    ERIC Educational Resources Information Center

    Miller, Philip; And Others

    1994-01-01

    Describes three projects at Carnegie Mellon University (Pennsylvania) that developed novice programming environments based on structure editors: GNOME, MacGNOME and ACSE (Advanced Computing for Science Education). Tracks the evolution of the programming environments and courses, documenting important lessons and discoveries about novice…

  1. Professional Wisdom and Writing for Publication: Qualitative Interviews with Editors and Authors in Early Childhood Education

    ERIC Educational Resources Information Center

    Jalongo, Mary Renck

    2013-01-01

    College and university faculty members specializing in early childhood education face some unique challenges in scholarly writing. The purpose of this research was to use open-ended interviews as a way to gather the collective wisdom of a group of key informants about academic writing and publishing in the field. Twenty-two editors and/or authors,…

  2. Improving the Yield of Rural Education Research: An Editor's Swan Song

    ERIC Educational Resources Information Center

    Coladarci, Theodore

    2007-01-01

    In my 15th and final year as JRRE editor, I identify methodological and substantive shortcomings in the rural education research literature and, in turn, suggest strategies for improvement. I structure my observations around the following considerations: describing the rural context of research, making the rural argument, framing the research…

  3. The Location of Knowledge: A Conversation with the Editors on Knowledge, Experience, and Place

    ERIC Educational Resources Information Center

    Shultz, Lynette; Kelly, Jennifer; Weber-Pillwax, Cora

    2009-01-01

    As co-editors of this theme issue of this journal, the authors have accepted that knowledge systems and teacher education programs are deeply interconnected. Further, they claim that teacher education programs must incorporate in theory and practice the fact that knowledge systems are a determining factor in the effectiveness of a teacher…

  4. Persnickety editor, Founding Father, Mentor and Friend: The Legacy of Fred Mumpton

    NASA Technical Reports Server (NTRS)

    Ming, Douglas W.

    2006-01-01

    This paper is a tribute to Dr Fred Munpton, the founder of the International Committee on Natural Zeolites (ICNZ), by one of his students, who later succeed him as president of the ICNZ. The tribute reflects on Dr. Mumpton's skills as an editor and his zeal for the study of natural zeolites.

  5. The Newspaper Editor As Graphic Strategist. ANPA News Research Report No. 27.

    ERIC Educational Resources Information Center

    Garcia, Mario R.

    This report discusses the graphic strategies available to editors for positioning the day's news. The purposes of the report are: (1) to introduce those in charge of designing the newspaper page to the structural approach to design (the structural approach is defined as incorporating horizontal and vertical structures in the available spaces,…

  6. IFLA General Conference, 1986. Education and Research Division. Section: RT of Editors of Library Journals. Paper.

    ERIC Educational Resources Information Center

    International Federation of Library Associations and Institutions, The Hague (Netherlands).

    Presented as part of a roundtable discussion by editors of library journals at the 1986 International Federation of Library Associations (IFLA) conference, "Electronic Publishing," by Hirokazu Iwata of Japan, discusses Dai Nippon Printing's response to new media and electronic publishing. Various aspects of the computerized processing and…

  7. More on Lexical Bias: How Efficient Can a "Lexical Editor'" Be?

    ERIC Educational Resources Information Center

    Nozari, Nazbanou; Dell, Gary S.

    2009-01-01

    The lexical bias effect (the tendency for phonological speech errors to create words more often than nonwords) has been debated for over 30 years. One account attributes the effect to a lexical editor, a strategic component of the production system that examines each planned phonological string, and suppresses it if it is a nonword. The…

  8. SPADE: A Grammar Based Editor for Planning and Debugging Programs. AI Memo 386.

    ERIC Educational Resources Information Center

    Miller, Mark L.; Goldstein, Ira P.

    The Structured Planning and Debugging Editor (SPADE) is a new kind of interactive programming environment in which computer programs are generated by explicitly articulating planning decisions. The design of SPADE is based upon the development of a grammar of plans from a taxonomy of basic planning techniques. The utility of this approach to…

  9. Editorial: Conflict of interest policy for Editors of The American Journal of Clinical Nutrition

    Technology Transfer Automated Retrieval System (TEKTRAN)

    Integrity in the publication process requires impartiality at all levels of review. The American Journal of Clinical Nutrition (AJCN) adheres to the policy of the International Committee of Medical Journal Editors (ICMJE), Uniform Requirements for Manuscripts Submitted to Biomedical Journals: Writin...

  10. Learning the Attachment Theory with the CM-ED Concept Map Editor

    ERIC Educational Resources Information Center

    Rueda, U.; Arruarte, A.; Elorriaga, J. A.; Herran, E.

    2009-01-01

    This paper presents a study carried out at the University of the Basque Country UPV/EHU with the aim of evaluating the CM-ED (concept map editor) with social education students. Concept mapping is a widely accepted technique that promotes meaningful learning. Graphically representing concepts of the learning domain and relationships between them…

  11. Guidelines for Reviewers and the Editor at the Nuclear Safety Information Center.

    ERIC Educational Resources Information Center

    Whetsel, H. B.

    The main purpose of this report is to help novice reviewers accelerate their apprenticeship at the Nuclear Safety Information Center, a computerized information service sponsored by the U.S. Atomic Energy Commission. Guidelines for reviewers are presented in Part 1; Part 2 contains guidelines for the novice editor. The goal of the reviewers and…

  12. Light chain editors of anti-DNA receptors in human B cells

    PubMed Central

    Kalinina, Olga; Wang, Yue; Sia, Kevin; Radic, Marko; Cazenave, Pierre-André

    2014-01-01

    Receptor editing is a mechanism of self-tolerance used in newly generated B cells. The expressed heavy (H) or light (L) chain of an autoreactive receptor is replaced by upstream V genes which eliminate or modify autoreactivity. Editing of anti-DNA receptors has been characterized in anti-DNA transgenic mouse models including 3H9, 3H9/56R, and their revertant 3H9GL. Certain L chains, termed editors, rescue anti-DNA B cells by neutralizing or modifying DNA binding of the H chain. This editing mechanism acts on the natural H chain repertoire; endogenous H chains with anti-DNA features are expressed primarily in combination with editor L chains. We ask whether a similar set of L chains exists in the human repertoire, and if so, do they edit H chains with anti-DNA signatures? We compared the protein sequences of mouse editors to all human L chains and found several human L chains similar to mouse editors. These L chains diminish or veto anti-DNA binding when expressed with anti-DNA H chains. The human H chains expressed with these L chains also have relatively high arginine (Arg) content in the H chain complementarity determining region (H3), suggesting that receptor editing plays a role in establishing tolerance to DNA in humans. PMID:24470445

  13. University-government relationships in the training of technical writers-editors

    NASA Technical Reports Server (NTRS)

    Stohrer, Freda F.; Pinelli, Thomas E.

    1979-01-01

    Traditional and nontraditional methods of training technical writers-editors are reviewed. Combining work experience with classroom instruction in the form of cooperative education provides a method of strengthening the Federal career service in professional occupations. The NASA Langley experience that successfully introduced students to the special demands of technical writing and editing is described.

  14. Calculation of detection efficiency of the fiber-optic sensor to measure radioactive contamination using MCNP simulation

    NASA Astrophysics Data System (ADS)

    Joo, Hanyoung; Lee, Arim; Kim, Rinah; Park, Chan Hee; Moon, Joo Hyun

    2015-09-01

    In this paper, a fiber-optic radiation sensor (FORS) was developed to measure gamma rays from the radionuclides frequently found in radioactively contaminated soil. The sensing probe of the FORS was made of an inorganic (Lu,Y)2SiO5:Ce (LYSO:Ce) scintillator, a mixture of epoxy resin and hardener and a plastic fiber. The FORS was applied to measure gamma rays from Cs-137 source (1.1 μCi) in a disk shape. Also, MCNP simulation was performed for the same geometry as that in the experimental setup. Comparison between measurements by the FORS and MCNP simulation showed that the detection efficiency of the fiber-optic sensor was about 19.2%. The FORS is expected to be useful in measuring gamma rays from the radioactive soil at nuclear facility site.

  15. ENDF/B-VI Release 3 Cross Section Library for Use with the MCNP Monte Carlo Code.

    Energy Science and Technology Software Center (ESTSC)

    2003-12-16

    Version 00 This continuous energy cross-section data library for MCNP is in ACE format. The present library was satisfactorily tested in thermal and fast criticality benchmarks. For analyses below 20 MeV, MCB63NEA.BOLlB was applied also in cell and core calculations dedicated to the study of the subcritical accelerator driven systems (ADS). This library provides users an additional ENDF/B-VI based, continuous-energy and multi-temperature library for MCNP with an important feature: there is a perfect consistency withmore » the twin library MCJEFF22NEA.BOLIB already released, in terms of nuclear data processing calculation methodology. Both libraries are based on the NJOY-94.66 data processing system. This may be important, in particular, for the users involved in nuclear data validation who have already used the MCJEF22NEA.BOLIB library.« less

  16. MCNP6 model of the University of Washington clinical neutron therapy system (CNTS).

    PubMed

    Moffitt, Gregory B; Stewart, Robert D; Sandison, George A; Goorley, John T; Argento, David C; Jevremovic, Tatjana

    2016-01-21

    A MCNP6 dosimetry model is presented for the Clinical Neutron Therapy System (CNTS) at the University of Washington. In the CNTS, fast neutrons are generated by a 50.5 MeV proton beam incident on a 10.5 mm thick Be target. The production, scattering and absorption of neutrons, photons, and other particles are explicitly tracked throughout the key components of the CNTS, including the target, primary collimator, flattening filter, monitor unit ionization chamber, and multi-leaf collimator. Simulations of the open field tissue maximum ratio (TMR), percentage depth dose profiles, and lateral dose profiles in a 40 cm × 40 cm × 40 cm water phantom are in good agreement with ionization chamber measurements. For a nominal 10 × 10 field, the measured and calculated TMR values for depths of 1.5 cm, 5 cm, 10 cm, and 20 cm (compared to the dose at 1.7 cm) are within 0.22%, 2.23%, 4.30%, and 6.27%, respectively. For the three field sizes studied, 2.8 cm × 2.8 cm, 10.4 cm × 10.3 cm, and 28.8 cm × 28.8 cm, a gamma test comparing the measured and simulated percent depth dose curves have pass rates of 96.4%, 100.0%, and 78.6% (depth from 1.5 to 15 cm), respectively, using a 3% or 3 mm agreement criterion. At a representative depth of 10 cm, simulated lateral dose profiles have in-field (⩾ 10% of central axis dose) pass rates of 89.7% (2.8 cm × 2.8 cm), 89.6% (10.4 cm × 10.3 cm), and 100.0% (28.8 cm × 28.8 cm) using a 3% and 3 mm criterion. The MCNP6 model of the CNTS meets the minimum requirements for use as a quality assurance tool for treatment planning and provides useful insights and information to aid in the advancement of fast neutron therapy. PMID:26738533

  17. MCNP6 model of the University of Washington clinical neutron therapy system (CNTS)

    NASA Astrophysics Data System (ADS)

    Moffitt, Gregory B.; Stewart, Robert D.; Sandison, George A.; Goorley, John T.; Argento, David C.; Jevremovic, Tatjana

    2016-01-01

    A MCNP6 dosimetry model is presented for the Clinical Neutron Therapy System (CNTS) at the University of Washington. In the CNTS, fast neutrons are generated by a 50.5 MeV proton beam incident on a 10.5 mm thick Be target. The production, scattering and absorption of neutrons, photons, and other particles are explicitly tracked throughout the key components of the CNTS, including the target, primary collimator, flattening filter, monitor unit ionization chamber, and multi-leaf collimator. Simulations of the open field tissue maximum ratio (TMR), percentage depth dose profiles, and lateral dose profiles in a 40 cm  ×  40 cm  ×  40 cm water phantom are in good agreement with ionization chamber measurements. For a nominal 10  ×  10 field, the measured and calculated TMR values for depths of 1.5 cm, 5 cm, 10 cm, and 20 cm (compared to the dose at 1.7 cm) are within 0.22%, 2.23%, 4.30%, and 6.27%, respectively. For the three field sizes studied, 2.8 cm  ×  2.8 cm, 10.4 cm  ×  10.3 cm, and 28.8 cm  ×  28.8 cm, a gamma test comparing the measured and simulated percent depth dose curves have pass rates of 96.4%, 100.0%, and 78.6% (depth from 1.5 to 15 cm), respectively, using a 3% or 3 mm agreement criterion. At a representative depth of 10 cm, simulated lateral dose profiles have in-field (⩾10% of central axis dose) pass rates of 89.7% (2.8 cm  ×  2.8 cm), 89.6% (10.4 cm  ×  10.3 cm), and 100.0% (28.8 cm  ×  28.8 cm) using a 3% and 3 mm criterion. The MCNP6 model of the CNTS meets the minimum requirements for use as a quality assurance tool for treatment planning and provides useful insights and information to aid in the advancement of fast neutron therapy.

  18. Implementation of a Monte Carlo based inverse planning model for clinical IMRT with MCNP code

    NASA Astrophysics Data System (ADS)

    He, Tongming Tony

    In IMRT inverse planning, inaccurate dose calculations and limitations in optimization algorithms introduce both systematic and convergence errors to treatment plans. The goal of this work is to practically implement a Monte Carlo based inverse planning model for clinical IMRT. The intention is to minimize both types of error in inverse planning and obtain treatment plans with better clinical accuracy than non-Monte Carlo based systems. The strategy is to calculate the dose matrices of small beamlets by using a Monte Carlo based method. Optimization of beamlet intensities is followed based on the calculated dose data using an optimization algorithm that is capable of escape from local minima and prevents possible pre-mature convergence. The MCNP 4B Monte Carlo code is improved to perform fast particle transport and dose tallying in lattice cells by adopting a selective transport and tallying algorithm. Efficient dose matrix calculation for small beamlets is made possible by adopting a scheme that allows concurrent calculation of multiple beamlets of single port. A finite-sized point source (FSPS) beam model is introduced for easy and accurate beam modeling. A DVH based objective function and a parallel platform based algorithm are developed for the optimization of intensities. The calculation accuracy of improved MCNP code and FSPS beam model is validated by dose measurements in phantoms. Agreements better than 1.5% or 0.2 cm have been achieved. Applications of the implemented model to clinical cases of brain, head/neck, lung, spine, pancreas and prostate have demonstrated the feasibility and capability of Monte Carlo based inverse planning for clinical IMRT. Dose distributions of selected treatment plans from a commercial non-Monte Carlo based system are evaluated in comparison with Monte Carlo based calculations. Systematic errors of up to 12% in tumor doses and up to 17% in critical structure doses have been observed. The clinical importance of Monte Carlo based

  19. Calculation of the store house worker dose in a lost wax foundry using MCNP-4C.

    PubMed

    Alegría, Natalia; Legarda, Fernando; Herranz, Margarita; Idoeta, Raquel

    2005-01-01

    Lost wax casting is an industrial process which permits the transmutation into metal of models made in wax. The wax model is covered with a silicaceous shell of the required thickness and once this shell is built the set is heated and wax melted. Liquid metal is then cast into the shell replacing the wax. When the metal is cool, the shell is broken away in order to recover the metallic piece. In this process zircon sands are used for the preparation of the silicaceous shell. These sands have varying concentrations of natural radionuclides: 238U, 232Th and 235U together with their progenics. The zircon sand is distributed in bags of 50 kg, and 30 bags are on a pallet, weighing 1,500 kg. The pallets with the bags have dimensions 80 cm x 120 cm x 80 cm, and constitute the radiation source in this case. The only pathway of exposure to workers in the store house is external radiation. In this case there is no dust because the bags are closed and covered by plastic, the store house has a good ventilation rate and so radon accumulation is not possible. The workers do not touch with their hands the bags and consequently skin contamination will not take place. In this study all situations of external irradiation to the workers have been considered; transportation of the pallets from vehicle to store house, lifting the pallets to the shelf, resting of the stock on the shelf, getting down the pallets, and carrying the pallets to production area. Using MCNP-4C exposure situations have been simulated, considering that the source has a homogeneous composition, the minimum stock in the store house is constituted by 7 pallets, and the several distances between pallets and workers when they are at work. The photons flux obtained by MCNP-4C is multiplied by the conversion factor of Flux to Kerma for air by conversion factor to Effective Dose by Kerma unit, and by the number of emitted photons. Those conversion factors are obtained of ICRP 74 table 1 and table 17 respectively. This

  20. MCNP simulation of radiation doses distributions in a water phantoms simulating interventional radiology patients

    NASA Astrophysics Data System (ADS)

    He, Wenjun; Mah, Eugene; Huda, Walter; Selby, Bayne; Yao, Hai

    2011-03-01

    Purpose: To investigate the dose distributions in water cylinders simulating patients undergoing Interventional Radiological examinations. Method: The irradiation geometry consisted of an x-ray source, dose-area-product chamber, and image intensifier as currently used in Interventional Radiology. Water cylinders of diameters ranging between 17 and 30 cm were used to simulate patients weighing between 20 and 90 kg. X-ray spectra data with peak x-ray tube voltages ranging from 60 to 120 kV were generated using XCOMP3R. Radiation dose distributions inside the water cylinder (Dw) were obtained using MCNP5. The depth dose distribution along the x-ray beam central axis was normalized to free-in-air air kerma (AK) that is incident on the phantom. Scattered radiation within the water cylinders but outside the directly irradiated region was normalized to the dose at the edge of the radiation field. The total absorbed energy to the directly irradiated volume (Ep) and indirectly irradiated volume (Es) were also determined and investigated as a function of x-ray tube voltage and phantom size. Results: At 80 kV, the average Dw/AK near the x-ray entrance point was 1.3. The ratio of Dw near the entrance point to Dw near the exit point increased from ~ 26 for the 17 cm water cylinder to ~ 290 for the 30 cm water cylinder. At 80 kV, the relative dose for a 17 cm water cylinder fell to 0.1% at 49 cm away from the central ray of the x-ray beam. For a 30 cm water cylinder, the relative dose fell to 0.1% at 53 cm away from the central ray of the x-ray beam. At a fixed x-ray tube voltage of 80 kV, increasing the water cylinder diameter from 17 to 30 cm increased the Es/(Ep+Es) ratio by about 50%. At a fixed water cylinder diameter of 24 cm, increasing the tube voltage from 60 kV to 120 kV increased the Es/(Ep+Es) ratio by about 12%. The absorbed energy from scattered radiation was between 20-30% of the total energy absorbed by the water cylinder, and was affected more by patient size