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Sample records for mcnp visual editor

  1. 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

  2. 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.

  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. 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.

  6. Using NJOY to Create MCNP ACE Files and Visualize Nuclear Data

    SciTech Connect

    Kahler, Albert Comstock

    2016-10-14

    We provide lecture materials that describe the input requirements to create various MCNP ACE files (Fast, Thermal, Dosimetry, Photo-nuclear and Photo-atomic) with the NJOY Nuclear Data Processing code system. Input instructions to visualize nuclear data with NJOY are also provided.

  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. Avogadro: an advanced semantic chemical editor, visualization, and analysis platform

    PubMed Central

    2012-01-01

    Background The Avogadro project has developed an advanced molecule editor and visualizer designed for cross-platform use in computational chemistry, molecular modeling, bioinformatics, materials science, and related areas. It offers flexible, high quality rendering, and a powerful plugin architecture. Typical uses include building molecular structures, formatting input files, and analyzing output of a wide variety of computational chemistry packages. By using the CML file format as its native document type, Avogadro seeks to enhance the semantic accessibility of chemical data types. Results The work presented here details the Avogadro library, which is a framework providing a code library and application programming interface (API) with three-dimensional visualization capabilities; and has direct applications to research and education in the fields of chemistry, physics, materials science, and biology. The Avogadro application provides a rich graphical interface using dynamically loaded plugins through the library itself. The application and library can each be extended by implementing a plugin module in C++ or Python to explore different visualization techniques, build/manipulate molecular structures, and interact with other programs. We describe some example extensions, one which uses a genetic algorithm to find stable crystal structures, and one which interfaces with the PackMol program to create packed, solvated structures for molecular dynamics simulations. The 1.0 release series of Avogadro is the main focus of the results discussed here. Conclusions Avogadro offers a semantic chemical builder and platform for visualization and analysis. For users, it offers an easy-to-use builder, integrated support for downloading from common databases such as PubChem and the Protein Data Bank, extracting chemical data from a wide variety of formats, including computational chemistry output, and native, semantic support for the CML file format. For developers, it can be

  9. 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.

  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. 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.

  13. MatMCNP

    SciTech Connect

    2015-10-19

    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 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.

  15. 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.

  16. 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.

  17. 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.

  18. SIERRA Editor v. 1.2.1

    SciTech Connect

    Hoffman, Edward; Friedman-Hill, Ernest; Gibson, Marcus; Heinstein, Martin; & Whittford, Greg

    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.

  19. 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.

  20. Editor's note

    NASA Astrophysics Data System (ADS)

    Umapathy, Siva

    2017-01-01

    This is an editor's note related to the publication 'Biologically active and thermally stable polymeric Schiff base and its metal polychelates: Their synthesis and spectral aspects' by Raza Rasool and Sumaiya Hasnain, which appeared in Spectrochimica Acta Part A: Molecular and Biomolecular Spectroscopy 148 (2015) 435-443.

  1. WRR editors

    NASA Astrophysics Data System (ADS)

    New editors of AGU's Water Resources Research journal will be Soroosh Sorooshian and Roger E. Smith.Soroosh Sorooshian was born in Kerman, Iran. He received his B.S. degree in mechanical engineering from California State Polytechnic University, San Luis Obispo, in 1971. He received his M.S. degree in operations research in 1973 and his Ph.D. degree in water resources systems engineering in 1978, both from the University of California, Los Angeles.

  2. 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

  3. 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.

  4. MCNP{trademark} Monte Carlo: A precis of MCNP

    SciTech Connect

    Adams, K.J.

    1996-06-01

    MCNP{trademark} is a general purpose three-dimensional time-dependent neutron, photon, and electron transport code. It is highly portable and user-oriented, and backed by stringent software quality assurance practices and extensive experimental benchmarks. The cross section database is based upon the best evaluations available. MCNP incorporates state-of-the-art analog and adaptive Monte Carlo techniques. The code is documented in a 600 page manual which is augmented by numerous Los Alamos technical reports which detail various aspects of the code. MCNP represents over a megahour of development and refinement over the past 50 years and an ongoing commitment to excellence.

  5. QUADRENNIAL MCNP TIMING STUDY

    SciTech Connect

    E. C. SELCOW; B. D. LANSRUD

    2000-09-01

    The Los Alamos National Laboratory Monte Carlo N-Particle radiation transport code, MCNP, is widely used around the world for many radiation protection and shielding applications. As a well-known standard it is also an excellent vehicle for assessing the relative performance of scientific computing platforms. Every three-to-four years a new version of MCNP is released internationally by the Radiation Safety Information Computational Center (RSICC) in Oak Ridge, Tennessee. For each of the past few releases, we have also done a timing study to assess the progress of scientific computing platforms and software. These quadrennial timing studies are valuable to the radiation protection and shielding community because (a) they are performed by a recognized scientific team, not a computer vendor, (b) they use an internationally recognized code for radiation protection and shielding calculations, (c) they are eminently reproducible since the code and the test problems are internationally distributed. Further, if one has a computer platform, operating system, or compiler not presented in our results, its performance is directly comparable to the ones we report because it can use the same code, data, and test problems as we used. Our results, using a single processor per platform, indicate that hardware advances during the past three years have improved performance by less than a factor of two and software improvements have had a marginal effect on performance. The most significant impacts on performance have resulted from developments in multiprocessing and multitasking. The other most significant advance in the last three years has been the accelerated improvements in personal computers. In the last timing study, the tested personal computer was approximately a factor of four slower that the fastest machine tested, a DEC Alphastation 500. In the present study, the fastest PC tested was less than a factor of two slower than the fastest platform, which is a Compaq

  6. 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.

  7. 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.

  8. 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.

  9. MCNP and GADRAS Comparisons

    SciTech Connect

    Klasky, Marc Louis; Myers, Steven Charles; James, Michael R.; Mayo, Douglas R.

    2016-04-19

    To facilitate the timely execution of System Threat Reviews (STRs) for DNDO, and also to develop a methodology for performing STRs, LANL performed comparisons of several radiation transport codes (MCNP, GADRAS, and Gamma-Designer) that have been previously utilized to compute radiation signatures. While each of these codes has strengths, it is of paramount interest to determine the limitations of each of the respective codes and also to identify the most time efficient means by which to produce computational results, given the large number of parametric cases that are anticipated in performing STR's. These comparisons serve to identify regions of applicability for each code and provide estimates of uncertainty that may be anticipated. Furthermore, while performing these comparisons, examination of the sensitivity of the results to modeling assumptions was also examined. These investigations serve to enable the creation of the LANL methodology for performing STRs. Given the wide variety of radiation test sources, scenarios, and detectors, LANL calculated comparisons of the following parameters: decay data, multiplicity, device (n,γ) leakages, and radiation transport through representative scenes and shielding. This investigation was performed to understand potential limitations utilizing specific codes for different aspects of the STR challenges.

  10. 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.

  11. 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).

  12. 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.

  13. 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.

  14. 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

  15. 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

  16. 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.

  17. 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.

  18. 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

  19. 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.

  20. 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)

  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. 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

  3. 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.

  4. 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.

  5. 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.

  6. 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.

  7. 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.

  8. MSSP Associate Editors

    NASA Astrophysics Data System (ADS)

    Mottershead, John E.

    2015-08-01

    MSSP is pleased to announce the appointment of three distinguished researchers, Professors Jerome Antoni, Spilios Fassois and Paolo Pennacchi, as Associate Editors. The broad coverage of MSSP research topics demands editorial expertise in several disciplines and the appointment of an editorial team of the highest quality is essential in maintaining and further enhancing the reputation of MSSP as a journal at the forefront of modern experimental mechanics that combines dynamic systems with measurement technology, signal processing and active control. Brief descriptions of the backgrounds and experience of the Associate Editors are provided in the following paragraphs.

  9. 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

  10. YUMMY: The Yucca Mountain MCNP-Library

    SciTech Connect

    Alpan, FA

    2004-12-10

    Point-wise libraries provided with the MCNP code contain neutron data for a limited number of temperatures. However, it is important to have the option of using data from a wide range of temperatures for transport calculations. For this purpose, a multi-temperature, ACE-format neutron library was generated for 134 nuclides, as requested by Yucca Mountain Project (YMP) staff. The library is referred to as YUMMY (YUcca Mountain MCNP-librarY). The neutron cross section data are based on ENDF/B-V or ENDF/B-VI evaluations that were requested by YMP staff. This document provides the details of the new library and its use in criticality safety benchmark problems, a Pressurized Water Reactor design and waste package models in MCNP4C.

  11. 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.

  12. LDAP Browser/Editor

    SciTech Connect

    Gawor, Jarek; Laszewski, Gregor von

    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.

  13. 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…

  14. 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…

  15. 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.

  16. 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.

  17. Adjoint-Based Uncertainty Quantification with MCNP

    NASA Astrophysics Data System (ADS)

    Seifried, Jeffrey Edwin

    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.

  18. 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.

  19. MCNP analysis of the FOEHN critical experiment

    SciTech Connect

    Ougouag, A.M.; Wemple, C.A.; Rubio, G.A.; Ryskamp, J.M.

    1993-10-01

    A very high fidelity MCNP model of the Franco-German FOEHN critical experiment has been developed. The results obtained show a high degree of agreement with each of the three configurations of the experiment. In particular, it is shown that the model reproduces the power density production distribution for all but a few of the experimental points internal to the core. Agreement for points of the axial ends at the core is less comprehensive. In the configurations that include boron axial core end covers, the agreement is similar within the core, but a few additional disagreement points arise at the axial ends of the core. The results remain consistent, however, with the statistical interpretation of MCNP tallies. The quantities computed also include the thermal flux in the reflector and the core multiplication factor for various critical configurations. It is found that the fluxes agree with the experiment within the experimental error bounds and two computational standard deviations. Most of the core multiplication results agree within three MCNP standard deviations. The overall conclusion of this study is that MCNP is an appropriate and valid computational tool for the static neutronic design of plate-fueled, heavy-water-moderated reactors, such as FOEHN or the Advanced Neutron Source.

  20. Guest Editors' Preface

    NASA Astrophysics Data System (ADS)

    Gille, Peter; Miller, Wolfram; Sangwal, Keshra; Talik, Ewa

    2014-09-01

    The 17th International Conference on Crystal Growth and Epitaxy (ICCGE-17) was held in Warsaw during 11 and 16 August 2013. The contributions during the ICCGE-17 were of three types: Invited lectures, oral presentations and poster presentions. The conference participants were also invited to submit manuscripts based on their contributions for publication in the ICCGE-17 Proceedings volume of Journal of Crystal Growth. The present volume contains manuscripts accepted by the guest editors for this conference volume.

  1. 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.

  2. 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.

  3. 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

  4. 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

  5. Improved MCNP Memory Locality by Neutron Grouping

    NASA Astrophysics Data System (ADS)

    Bly, Aaron

    This research presents new code for Monte Carlo N-Particle (MCNP) to achieve an improved time during criticality calculations. Modifications implementing the grouping and sorting of neutrons takes advantage of memory locality by processing all neutrons in a group to achieve the temporal reuse of cross section data. This prevents unnecessary data lookups. Various groupings and their results are compared. The modified code utilizing neutron energy groups provided the best result of a 16.7% +/- 0.5% speedup for a criticality determination of a two slab tank experiment. This is a savings of 2 ½ hours for a system that normally takes approximately 15 ½ hours to execute. The code implemented was chosen to require minimal modifications to the MCNP program thus avoiding the need to rewrite a new version. Verification and validation is still needed in order to show that a speedup using neutron groups can be achieved in all cases.

  6. Fission Matrix Capability for MCNP Monte Carlo

    NASA Astrophysics Data System (ADS)

    Brown, Forrest; Carney, Sean; Kiedrowski, Brian; Martin, William

    2014-06-01

    We describe recent experience and results from implementing a fission matrix capability into the MCNP Monte Carlo code. The fission matrix can be used to provide estimates of the fundamental mode fission distribution, the dominance ratio, the eigenvalue spectrum, and higher mode forward and adjoint eigenfunctions of the fission neutron source distribution. It can also be used to accelerate the convergence of the power method iterations and to provide basis functions for higher-order perturbation theory. The higher-mode fission sources can be used in MCNP to determine higher-mode forward fluxes and tallies, and work is underway to provide higher-mode adjoint-weighted fluxes and tallies. Past difficulties and limitations of the fission matrix approach are overcome with a new sparse representation of the matrix, permitting much larger and more accurate fission matrix representations. The new fission matrix capabilities provide a significant advance in the state-of-the-art for Monte Carlo criticality calculations.

  7. Criticality Calculations with MCNP6 - Practical Lectures

    SciTech Connect

    Brown, Forrest B.; Rising, Michael Evan; Alwin, Jennifer Louise

    2016-11-29

    These slides are used to teach MCNP (Monte Carlo N-Particle) usage to nuclear criticality safety analysts. The following are the lecture topics: course information, introduction, MCNP basics, criticality calculations, advanced geometry, tallies, adjoint-weighted tallies and sensitivities, physics and nuclear data, parameter studies, NCS validation I, NCS validation II, NCS validation III, case study 1 - solution tanks, case study 2 - fuel vault, case study 3 - B&W core, case study 4 - simple TRIGA, case study 5 - fissile mat. vault, criticality accident alarm systems. After completion of this course, you should be able to: Develop an input model for MCNP; Describe how cross section data impact Monte Carlo and deterministic codes; Describe the importance of validation of computer codes and how it is accomplished; Describe the methodology supporting Monte Carlo codes and deterministic codes; Describe pitfalls of Monte Carlo calculations; Discuss the strengths and weaknesses of Monte Carlo and Discrete Ordinants codes; The diffusion theory model is not strictly valid for treating fissile systems in which neutron absorption, voids, and/or material boundaries are present. In the context of these limitations, identify a fissile system for which a diffusion theory solution would be adequate.

  8. New TOR editor

    NASA Astrophysics Data System (ADS)

    Richman, Barbara T.

    1984-04-01

    David A. Brooks, associate professor at Texas A&M University's oceanography department, has been appointed editor designate of The Oceanography Report (TOR). He succeeds Arnold L. Gordon of the Lamont-Doherty Geological Observatory. Gordon, who initiated TOR in September 1981, is the new president-elect of the AGU Ocean Sciences Section.Brooks, a physical oceanographer, has been at Texas A&M for 6 years. His research interests include waves and tides, the interaction of waves and currents, Gulf Stream fluctuations, and Gulf of Mexico and Gulf of Maine circulation. Before going to Texas A&M, Brooks was a research associate and graduate faculty member at North Carolina State University in Raleigh.

  9. 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.

  10. 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

  11. 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

  12. 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...

  13. 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/.

  14. 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.

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

    SciTech Connect

    SARTORI, ENRICO

    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 with 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.

  16. The MCNP6 Analytic Criticality Benchmark Suite

    SciTech Connect

    Brown, Forrest B.

    2016-06-16

    Analytical benchmarks provide an invaluable tool for verifying computer codes used to simulate neutron transport. Several collections of analytical benchmark problems [1-4] are used routinely in the verification of production Monte Carlo codes such as MCNP® [5,6]. Verification of a computer code is a necessary prerequisite to the more complex validation process. The verification process confirms that a code performs its intended functions correctly. The validation process involves determining the absolute accuracy of code results vs. nature. In typical validations, results are computed for a set of benchmark experiments using a particular methodology (code, cross-section data with uncertainties, and modeling) and compared to the measured results from the set of benchmark experiments. The validation process determines bias, bias uncertainty, and possibly additional margins. Verification is generally performed by the code developers, while validation is generally performed by code users for a particular application space. The VERIFICATION_KEFF suite of criticality problems [1,2] was originally a set of 75 criticality problems found in the literature for which exact analytical solutions are available. Even though the spatial and energy detail is necessarily limited in analytical benchmarks, typically to a few regions or energy groups, the exact solutions obtained can be used to verify that the basic algorithms, mathematics, and methods used in complex production codes perform correctly. The present work has focused on revisiting this benchmark suite. A thorough review of the problems resulted in discarding some of them as not suitable for MCNP benchmarking. For the remaining problems, many of them were reformulated to permit execution in either multigroup mode or in the normal continuous-energy mode for MCNP. Execution of the benchmarks in continuous-energy mode provides a significant advance to MCNP verification methods.

  17. 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.

  18. Letter from the Editor

    NASA Astrophysics Data System (ADS)

    Strassmeier, Klaus G.

    2008-01-01

    As of 2006, Astronomische Nachrichten -- Astronomical Notes has reached its all-time high regarding the ISI journal impact factor, with an impressive increase of 60% compared to 2005. We now rank at position 1,399, as shown in the statistics below. This is solely due to the increased number and quality of published articles: In 2006, Astronomische Nachrichten -- Astronomical Notes published 208 research papers and received 1,033 citations -- five citations per paper on average. In 2007, we have published 177 research papers, and one may be curious to see how their factor will develop. In co-operation with Wiley InterScience we have achieved an average o nline publication time of just 4.5 months. As in the past, publication in Astronomische Nachrichten -- Astronomical Notes} continues to be free of charge. Also, all articles of the first issue of each volume can be downloaded free of charge, as can all articles labelled ``Editor's Choice'', which are additionally featured with a color image on the front cover.

  19. Letter from the Editor

    NASA Astrophysics Data System (ADS)

    Strassmeier, Klaus G.

    2009-01-01

    As of 2007, Astronomische Nachrichten -- Astronomical Notes has reached its all-time high regarding the ISI journal impact factor, with an impressive increase of 60% compared to 2005. We now rank at 1,461, as shown in the statistics below. This is solely due to the increased quality of the published articles: In 2006, Astronomische Nachrichten -- Astronomical Notes published 208 research papers and received 1,033 citations -- five citations per paper on average. In 2007, we have published 177 research papers with roughly the same number of citations. In co-operation with Wiley InterScience we have achieved an average online publication time of just 4.5 months. We hope that the year 2008 will be comparably prosperous. As in the past, publication in Astronomische Nachrichten -- Astronomical Notes continues to be free of charge. Also, all articles of the first issue of each volume can be downloaded free of charge, as can all articles labelled ``Editor's Choice'', which are additionally featured with a color image on the front cover.

  20. 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.

  1. Validation of MCNP4A for repository scattered radiation analysis

    SciTech Connect

    Haas, M.N.; Su, S.

    1998-02-01

    Comparison is made between experimentally determined albedo (scattered) radiation and MCNP4A predictions in order to provide independent validation for repository shielding analysis. Both neutron and gamma scattered radiation fields from concrete ducts are compared in this paper. Satisfactory agreement is found between actual and calculated results with conservative values calculated by the MCNP4A code for all conditions.

  2. 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.

  3. Semi-Analytical Benchmarks for MCNP6

    SciTech Connect

    Grechanuk, Pavel Aleksandrovi

    2016-11-07

    Code verification is an extremely important process that involves proving or disproving the validity of code algorithms by comparing them against analytical results of the underlying physics or mathematical theory on which the code is based. Monte Carlo codes such as MCNP6 must undergo verification and testing upon every release to ensure that the codes are properly simulating nature. Specifically, MCNP6 has multiple sets of problems with known analytic solutions that are used for code verification. Monte Carlo codes primarily specify either current boundary sources or a volumetric fixed source, either of which can be very complicated functions of space, energy, direction and time. Thus, most of the challenges with modeling analytic benchmark problems in Monte Carlo codes come from identifying the correct source definition to properly simulate the correct boundary conditions. The problems included in this suite all deal with mono-energetic neutron transport without energy loss, in a homogeneous material. The variables that differ between the problems are source type (isotropic/beam), medium dimensionality (infinite/semi-infinite), etc.

  4. 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.

  5. 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.

  6. STE - The Software Tools Editor

    NASA Astrophysics Data System (ADS)

    Software tools is an excellent book written by B. W. Kernighan and P. J. Plauger, published by Addison-Wesley. In it the authors discuss how to write programs that make good tools, and how to program well in the process. One of the tools they develop is a fairly powerful editor, written in Ratfor (a structured form of FORTRAN IV). This program has been implemented on the UCL Starlink VAX (with a few modifications and extensions) and is recommended as the editor to use on the VAX. This note gives a brief introduction to, and description of, the editor which has been abstracted from the book (which you are recommended to buy). There are some short command summary sections at the end of this note. After reading this note you may like to print these short files and use them for reference when using the editor.

  7. Remarks from a retiring Editor

    NASA Astrophysics Data System (ADS)

    Mansur, Louis K.

    2015-10-01

    At the end of 2015 I plan to step down as Chairman of Editors for the Journal of Nuclear Materials. I use the opportunity to express thoughts that have recurred to me but were muted in comparison with the day to day priorities of editorial work. The most important is that I hold the deepest gratitude for your enduring support- authors, reviewers, readers, the Advisory Editorial Board, and my fellow Editors.

  8. Enhancements to the MCNP6 background source

    DOE PAGES

    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

  9. 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.

  10. 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.

  11. Lecture Notes on Criticality Safety Validation Using MCNP & Whisper

    SciTech Connect

    Brown, Forrest B.; Rising, Michael Evan; Alwin, Jennifer Louise

    2016-03-11

    Training classes for nuclear criticality safety, MCNP documentation. The need for, and problems surrounding, validation of computer codes and data area considered first. Then some background for MCNP & Whisper is given--best practices for Monte Carlo criticality calculations, neutron spectra, S(α,β) thermal neutron scattering data, nuclear data sensitivities, covariance data, and correlation coefficients. Whisper is computational software designed to assist the nuclear criticality safety analyst with validation studies with the Monte Carlo radiation transport package MCNP. Whisper's methodology (benchmark selection – Ck's, weights; extreme value theory – bias, bias uncertainty; MOS for nuclear data uncertainty – GLLS) and usage are discussed.

  12. Guest Editor's introduction

    NASA Astrophysics Data System (ADS)

    1996-03-01

    pleasure to be Guest Editor and I look forward to future developments in this growing research area and expositions in Distributed Systems Engineering. Peter G Harrison Imperial College, London

  13. 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.

  14. 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.

  15. 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!

  16. 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)

  17. 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.

  18. 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…

  19. 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.

  20. 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.

  1. 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.

  2. A Syntax Directed Editor Environment.

    DTIC Science & Technology

    1983-12-05

    Much of his work was based on research by Bruce J. MacLennan of the Naval Postgraduate School (Ref 9) and two of Mister MacLennan’s former thesis...of Defense. Requirement for ADA Programming Suport | .:Environments - Stoneman. Washington, D.C. 1980. • .,6. Feiler , Peter H. and Raul Medina-Mora...1982. (AD-A053032). 9. MacLennan, Bruce J. The Automatic Generation of Syntax-Directed Editors. Naval Postgraduate School, Monterey, CA., 1981. 10

  3. 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.

  4. 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

  5. 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.

  6. 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.

  7. Verification of the pulse height tally in MCNP 5

    NASA Astrophysics Data System (ADS)

    Sood, Avneet; Forster, R. A.; Adams, Bryce J.; White, Morgan C.

    2004-01-01

    Pulse height tallies are commonly used in Monte Carlo codes to predict detailed measured photon spectra for spectrometry purposes. The pulse height tally is unique among the various tallies in MCNP. Unlike flux or current tallies, which are calculated as soon as the particle exits or collides in the cell, the entire set of tracks for a history must be completed before the pulse height tally can be made. The objective of this work was to verify the pulse height tally and prepare to verify the new MCNP 5 variance reduction features with the pulse height tally. In this paper, we give details to the analytic solution of the pulse height distribution using a modification to Shuttleworth's fictitious elements, report MCNP 5 results for the pulse height tally, energy deposited and current tallies for the problem.

  8. 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.

  9. 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.

  10. 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.

  11. New probability table treatment in MCNP for unresolved resonances

    SciTech Connect

    Carter, L.L.; Little, R.C.; Hendricks, J.S.; MacFarlane, R.E.

    1998-04-01

    An upgrade for MCNP has been implemented to sample the neutron cross sections in the unresolved resonance range using probability tables. These probability tables are generated with the cross section processor code NJOY, by using the evaluated statistical information about the resonances to calculate cumulative probability distribution functions for the microscopic total cross section. The elastic, fission, and radiative capture cross sections are also tabulated as the average values of each of these partials conditional upon the value of the total. This paper summarizes how the probability tables are utilized in this MCNP upgrade and compares this treatment with the approximate smooth treatment for some example problems.

  12. 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.

  13. 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.

  14. 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)

  15. 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.

  16. Donald R. Nielsen New WRR Editor

    NASA Astrophysics Data System (ADS)

    Robb, David W.

    Bridging the gap between the disciplines of engineering and agriculture is a major goal for Water Resources Research (WRR), says Donald R. Nielsen, who was appointed to a 4-year term as WRR editor, effective January 1, 1985. Nielsen succeeds Stephen J. Burges as the WRR editor for hydrology, physical, chemical, and biological sciences. Ronald G. Cummings, at the University of New Mexico, is the WRR editor for policy sciences, including economics, systems analysis, sociology, and law.

  17. 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.

  18. On-The-Fly Neutron Doppler Broadening in MCNP

    NASA Astrophysics Data System (ADS)

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

    2014-06-01

    Multi-physics calculations may involve coupling continuous-energy Monte Carlo neutronics codes to CFD codes that provide many thousands or even millions of region temperatures. The traditional Monte Carlo approach - using precalculated Doppler broadened nuclear cross-sections - is not feasible for these large multiphysics problems. Instead, an On-the-Fly (OTF) Doppler broadening methodology is required, whereby neutron cross-sections are broadened during the Monte Carlo transport. To this end, we have developed a methodology for MCNP to provide OTF broadening based on cell temperatures during neutron tracking. The method enables the use of many thousands or more temperatures in MCNP Monte Carlo calculations for multiphysics applications, significantly advancing the state-of-the-art by permitting the solution of problems that were not previously possible with continuous-energy Monte Carlo codes. A production library with an extended set of isotopes has been developed for use with MCNP6. Calculations of test problems with MCNP6 and the new library demonstrate the accuracy and effectiveness of the OTF approach.

  19. 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.

  20. 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)

  1. 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

  2. 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.

  3. 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…

  4. 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

  5. PROGRAMMABLE DISPLAY PUSHBUTTON LEGEND EDITOR

    NASA Technical Reports Server (NTRS)

    Busquets, A. M.

    1994-01-01

    The Programmable Display Pushbutton (PDP) is a pushbutton device available from Micro Switch which has a programmable 16 x 35 matrix of LEDs on the pushbutton surface. Any desired legends can be displayed on the PDPs, producing user-friendly applications which greatly reduce the need for dedicated manual controls. Because the PDP can interact with the operator, it can call for the correct response before transmitting its next message. It is both a simple manual control and a sophisticated programmable link between the operator and the host system. The Programmable Display Pushbutton Legend Editor, PDPE, is used to create the LED displays for the pushbuttons. PDPE encodes PDP control commands and legend data into message byte strings sent to a Logic Refresh and Control Unit (LRCU). The LRCU serves as the driver for a set of four PDPs. The legend editor (PDPE) transmits to the LRCU user specified commands that control what is displayed on the LED face of the individual pushbuttons. Upon receiving a command, the LRCU transmits an acknowledgement that the message was received and executed successfully. The user then observes the effect of the command on the PDP displays and decides whether or not to send the byte code of the message to a data file so that it may be called by an applications program. The PDPE program is written in FORTRAN for interactive execution. It was developed on a DEC VAX 11/780 under VMS. It has a central memory requirement of approximately 12800 bytes. It requires four Micro Switch PDPs and two RS-232 VAX 11/780 terminal ports. The PDPE program was developed in 1985.

  6. [Report of the editors, 2011].

    PubMed

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

    2012-01-01

    The editors of Revista Clínica Española (Rev Clin Esp) inform on their editorial activity during the last 12 months (November 2010 to October 2011): (a) Objectives and attainments during 2011, (b) editorial activity, and (c) objectives for 2012. In 2011 we have updated the editorial algorithm (revision by the responsible editor of all manuscripts sent to peer review and incorporated an «editorial coordinator»), we have renovated two advise facilities (editorial and scientific committees), we have created a new section called «monthly e-image», and we have promoted Rev Clin Esp annual prizes. From the first January 2010 to 31(st) October 2011 we handled 422 manuscripts (42,2 manuscripts per month, higher than the 2010 figure of 40,4 manuscript/month). Overall we have accepted 26% (originals, 16%). We asked for 343 revisions and obtained 231 (67%). Seventy two percent of the reviewers sent their comments in less than two weeks. The mean time taken to accept or reject a given manuscript has been 26 days. The mean time taken since a manuscript is received to publication (october, novembrer and december issues) has dropped from 334 days in 2010 to 254 in 2011 (24% decrease). The collaboration with the working groups has reported about 2 published manuscripts per issue. Our objectives for 2012 are: (a) to improve the editorial process; (b) main article translation into English; (c) improve some sections (i.e. clinical conference); (d) estimulate working groups collaboration; and (e) improve continued medical education. Revista Clínica Española is an open forum for all internal medicine specialists. We all have the responsibility to make our journal, each day, better.

  7. 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

  8. Editorial Commentary: Editor's Conflict of Interest.

    PubMed

    Lubowitz, James H

    2015-09-01

    The Editor-in-chief has recused himself from industry consulting, which he performed before assuming the position, and returned related royalties and divested related stock options, in order to mitigate against conflict-of-interest. The Editor discloses affiliation with an institution that receives support from diverse industry partners in support of research and education.

  9. 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…

  10. Electron/Photon Verification Calculations Using MCNP4B

    SciTech Connect

    D. P. Gierga; K. J. Adams

    1999-04-01

    MCNP4BW 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. The impact of several MCNP tally options and physics parameters was explored in detail. The agreement between experiment and simulation was usually within two standard deviations of the experimental and calculational errors. Furthermore, sub-step artifacts for bremsstrahlung production were shown to be mitigated. A detailed suite of electron depth dose calculations in water is also presented. Areas for future code development have also been explored and include the dependence of cell and detector tallies on different bremsstrahlung angular models and alternative variance reduction splitting schemes for bremsstrahlung production.

  11. 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.

  12. 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.

  13. MCNP/X Transport in the Tabular Regime

    NASA Astrophysics Data System (ADS)

    Hughes, H. Grady

    2007-03-01

    We 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, we 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. We also briefly touch on the current situation in regard to photon, electron, and proton transport tables.

  14. 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.

  15. Benchmark study of TRIPOLI-4 through experiment and MCNP codes

    SciTech Connect

    Michel, M.; Coulon, R.; Normand, S.; Huot, N.; Petit, O.

    2011-07-01

    Reliability on simulation results is essential in nuclear physics. Although MCNP5 and MCNPX are the world widely used 3D Monte Carlo radiation transport codes, alternative Monte Carlo simulation tools exist to simulate neutral and charged particles' interactions with matter. Therefore, benchmark are required in order to validate these simulation codes. For instance, TRIPOLI-4.7, developed at the French Alternative Energies and Atomic Energy Commission for neutron and photon transport, now also provides the user with a full feature electron-photon electromagnetic shower. Whereas the reliability of TRIPOLI-4.7 for neutron and photon transport has been validated yet, the new development regarding electron-photon matter interaction needs additional validation benchmarks. We will thus demonstrate how accurately TRIPOLI-4's 'deposited spectrum' tally can simulate gamma spectrometry problems, compared to MCNP's 'F8' tally. The experimental setup is based on an HPGe detector measuring the decay spectrum of an {sup 152}Eu source. These results are then compared with those given by MCNPX 2.6d and TRIPOLI-4 codes. This paper deals with both the experimental aspect and simulation. We will demonstrate that TRIPOLI-4 is a potential alternative to both MCNPX and MCNP5 for gamma-electron interaction simulation. (authors)

  16. 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)

  17. The CZMIL manual editor (CME): a new tool for analyzing bathymetric lidar waveforms and editing point clouds

    NASA Astrophysics Data System (ADS)

    Morris, Gary Q.; Depner, Jan; Hilderbrand, Ronnie; Ramnath, Vinod

    2010-04-01

    The University of Southern Mississippi's Center of Higher Learning has developed a Waveform Viewer, Attribute Viewer, and a 3D Editor for use in the CZMIL Point Cloud Manual Editor (CME). The Waveform Viewer displays various channels of CZMIL waveforms within the 2D/3D editor interface of CME. This module provides the user an interactive tool set consisting of a cross sectioning mechanism for the intensity time-bin relationship, waveform file output, and zooming capabilities. The Attribute Viewer provides the data analyst with information to analyze various environmental and spatial parameters that might contribute to errors in the measured points. The 3D Editor offers the benefits of capturing depth outliers; an intuitive visual connectivity with the 2D editor; and the implementation of volumetric directional slice isolation of data outliers.

  18. [2009 report from the editors].

    PubMed

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

    2010-01-01

    The editors of the Rev Clin Esp present the editorial course of action of the journal over the past year. We have up-dated the design of the journal, its contents (sections) and computerized the editorial process. We processed 467 manuscripts and made an editorial decision on 402 of them between November 2008 and October 2009. A total of 92 manuscripts (23%) were accepted. Fifteen (13%) out of the 119 original articles for which the editorial process was completed were accepted. Our goal for the year 2010 is to make the journal available on the Internet for all those who are subscribers to the Rev Clin Esp as well as for internal medicine residents (for which they must be members of each regional society). Other objectives of the editorial team are to edit the E-cases, for the journal to be a continuing education tool and that the coordinators of the work groups develop a monographic number at least once every two years. These actions aim to increase the impact factor and the quality of the Rev Clin Esp, official publication of the Spanish Society of Internal Medicine and of Spanish-speaking internal medicine physicians.

  19. 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.

  20. Systems guide to MCNP (Monte Carlo Neutron and Photon Transport Code)

    SciTech Connect

    Kirk, B.L.; West, J.T.

    1984-06-01

    The subject of this report is the implementation of the Los Alamos National Laboratory Monte Carlo Neutron and Photon Transport Code - Version 3 (MCNP) on the different types of computer systems, especially the IBM MVS system. The report supplements the documentation of the RSIC computer code package CCC-200/MCNP. Details of the procedure to follow in executing MCNP on the IBM computers, either in batch mode or interactive mode, are provided.

  1. Use of MCNP code in energy dispersive X-ray fluorescence

    NASA Astrophysics Data System (ADS)

    Trojek, T.; Čechák, T.

    2007-10-01

    Monte Carlo simulations enable us to improve the applicability of analytical techniques based on emission of characteristic radiation. In particular, the MCNP4C2 code was tested for interpretation of measured data obtained with the use of energy dispersive X-ray fluorescence analysis. This paper describes MCNP outputs and compares them with the results of analytical calculations or experiments. Then the application of Monte Carlo simulations to the prediction of measurement results is shown, and the MCNP results are verified.

  2. 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.

  3. 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)

  4. Comparison of CAP88 and MCNP for Overhead Gamma-emitting Plumes

    SciTech Connect

    Mcnaughton, Michael; Gillis, Jessica Mcdonnel; McClory, Aysha Reede; Whicker, Jeffrey Jay; Fuehne, David Patrick

    2016-01-08

    The purpose of this paper is to use the Monte Carlo N-Particle Code (MCNP) to investigate the dose from gamma-emitting radionuclides such as Carbon-11 when a plume passes overhead. MCNP results are compared with results from the EPA program, CAP88. In some cases, typically near the source during stable conditions, the CAP88 results are less than the MCNP results. However, in the case of a receptor 800 m from a source at the Los Alamos Neutron Science Center (LANSCE), the CAP88 result is greater than the MCNP result.

  5. 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.

  6. [Report of the editors, 2010].

    PubMed

    García Puig, Juan; Alonso-Vega, Gabriel Gaspar; Blanco, Juan José Ríos

    2011-01-01

    The Editors of the Rev Clin Esp inform herein on their editorial activity in the last year (November 2009 to October 2010) according to three different sections: (a) Objectives and achievements during 2010, (b) editorial activity, and (c) objectives for 2011. During 2010, we have updated the editorial algorithm (manuscript time lag). We have developed the "E-case reports" section and we have linked the abstracts of the Annual Congress of the Spanish Society of Internal Medicine (SEMI) to a journal supplement (electronically available). Since 2010, the subscribers have been able to receive all of the contents of the Rev Clin Esp on-line and to perform self-evaluations in order to obtain 1.7 credits per each journal issue (continuing education). In 2010 we handled 402 manuscripts (7.2% more than in 2009), 35% of which were accepted for publication. We asked 186 reviewers for their expert opinion, 75% of whom sent their reports in less than two weeks. The mean time needed to reach an editorial decision concerning original manuscripts ("accepted / rejected") was 44.5 days and for papers not sent to external reviewers 19.5 days. Collaboration with the work groups produced good results (2.4 published manuscripts per issue), but this could be improved if all the groups collaborated in all the journal sections. Our objectives for 2011 are to complete the renewal of the Rev Clin Esp scientific committee, in accordance with the SEMI Council, and to continue to proceed with the actions initiated to increase the journal impact factor. Rev Clim Esp is an open forum for all internal medicine specialists. Responsibility falls on all of us to collaborate in order to make our journal a little better day by day.

  7. 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.

  8. 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.

  9. How are Editors Selected, Recruited and Approved?

    PubMed

    Teixeira da Silva, Jaime A; Al-Khatib, Aceil

    2016-11-28

    The editors of scholarly journals have a duty to uphold and promote the highest standards of ethical conduct of research. They also have a responsibility to maintain the integrity of the literature, and to promote transparency and honesty in reporting research findings. In the process of screening manuscripts they receive for possible publication, editors have the obligation to report infractions to the institutions of offending authors, and request an investigation. Since editors can reject a paper on ethical grounds, they can be considered to be the guardians of ethics who should express high ethical standards in conducting and publishing their own research. An examination of several publishers' websites reveals no such requirement or clear selection criteria for journal editors. Therefore, we aim to discuss the factors that publishers, in a broad sense, should consider when selecting editors for scholarly journals and believe that such criteria should be made public to ensure accountability. This would restore some of the eroding public trust in disseminated research, fortify confidence in the composition and qualification of members of an editorial board, and help to protect the reputations of publishers and editors.

  10. 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

  11. 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

  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. [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

  14. 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.

  15. 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.

  16. MCNP calculations for container inspection with tagged neutrons

    NASA Astrophysics Data System (ADS)

    Boghen, G.; Donzella, A.; Filippini, V.; Fontana, A.; Lunardon, M.; Moretto, S.; Pesente, S.; Zenoni, A.

    2005-12-01

    We are developing an innovative tagged neutrons inspection system (TNIS) for cargo containers: the system will allow us to assay the chemical composition of suspect objects, previously identified by a standard X-ray radiography. The operation of the system is extensively being simulated by using the MCNP Monte Carlo code to study different inspection geometries, cargo loads and hidden threat materials. Preliminary simulations evaluating the signal and the signal over background ratio expected as a function of the system parameters are presented. The results for a selection of cases are briefly discussed and demonstrate that the system can operate successfully in different filling conditions.

  17. [The Chilean Association of Biomedical Journal Editors].

    PubMed

    Reyes, H

    2001-01-01

    On September 29th, 2000, The Chilean Association of Biomedical Journal Editors was founded, sponsored by the "Comisión Nacional de Investigación Científica y Tecnológica (CONICYT)" (the Governmental Agency promoting and funding scientific research and technological development in Chile) and the "Sociedad Médica de Santiago" (Chilean Society of Internal Medicine). The Association adopted the goals of the World Association of Medical Editors (WAME) and therefore it will foster "cooperation and communication among Editors of Chilean biomedical journals; to improve editorial standards, to promote professionalism in medical editing through education, self-criticism and self-regulation; and to encourage research on the principles and practice of medical editing". Twenty nine journals covering a closely similar number of different biomedical sciences, medical specialties, veterinary, dentistry and nursing, became Founding Members of the Association. A Governing Board was elected: President: Humberto Reyes, M.D. (Editor, Revista Médica de Chile); Vice-President: Mariano del Sol, M.D. (Editor, Revista Chilena de Anatomía); Secretary: Anna María Prat (CONICYT); Councilors: Manuel Krauskopff, Ph.D. (Editor, Biological Research) and Maritza Rahal, M.D. (Editor, Revista de Otorrinolaringología y Cirugía de Cabeza y Cuello). The Association will organize a Symposium on Biomedical Journal Editing and will spread information stimulating Chilean biomedical journals to become indexed in international databases and in SciELO-Chile, the main Chilean scientific website (www.scielo.cl).

  18. 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.

  19. A standard syntax-directed editor for hyperprogramming systems

    SciTech Connect

    Zhogolev, E.A.; Kuz`menkova, E.A.; Mailingova, O.L.; Poprygaev, E.V.

    1995-05-01

    The main operations of a syntax-directed editor are considered. The requirements to the standard syntax-directed editor are stated. The structure of the standard syntax-directed editor and the functions of its components are discussed. The language base properties needed for syntax-directed editor development are described. Methods for transforming the standard syntax-directed editor into a specialized one are carried out.

  20. 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!

  1. 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

  2. EDITORIAL: Message from the Editor

    NASA Astrophysics Data System (ADS)

    Thomas, Paul

    2008-01-01

    To begin, I would like to wish our readers, authors, referees and Board of Editors a successful and happy 2008 and thank them for their contributions to Nuclear Fusion in 2007. I took over the editorship of Nuclear Fusion in January, and the year has been one in which the community as a whole has been busier than ever with a variety of duties associated with the ITER project. It was with pride that we published the Progress in the ITER Physics Basis in the June issue of the journal (stacks.iop.org/NF/47/i=6). The task undertaken by the coordinators, authors and referees was a daunting one but one which led to an outstandingly successful issue. The response from readers has been phenomenal and there were in the region of 10 000 downloads of papers in the first month following publication. Looking to 2008 and beyond, the journal will endeavour to continue to support the work of the fusion community. Refereeing As we have done since January 2005, we would like to thank our top ten most loyal referees who have helped the journal with its double-referee peer-review procedure in the past year. At the Nuclear Fusion Editorial Office we are fully aware of the load we put on the shoulders of our referees. At the end of 2004 the Editorial Board decided that a gesture of gratitude should be made to our most loyal referees. We offer them a personal subscription to Nuclear Fusion with electronic access for one year, free of charge. To select the top referees we have adopted the criterion that a researcher should have acted as a referee or adjudicator for at least three different manuscripts during the period from summer 2006 to the end of 2007. We have excluded our Board members and those referees who were already listed in the top ten in the last two years. According to our records the following people met this criterion. Congratulations and many, many thanks! H.L. Berk (Texas University, USA) J.S. DeGrassie (GAT, USA) C. Deutsch (Paris University, France) N. Hayashi (JAEA

  3. Preliminary Benchmarking Efforts and MCNP Simulation Results for Homeland Security

    SciTech Connect

    Robert Hayes

    2008-04-18

    It is shown in this work that basic measurements made from well defined source detector configurations can be readily converted in to benchmark quality results by which Monte Carlo N-Particle (MCNP) input stacks can be validated. Specifically, a recent measurement made in support of national security at the Nevada Test Site (NTS) is described with sufficient detail to be submitted to the American Nuclear Society’s (ANS) Joint Benchmark Committee (JBC) for consideration as a radiation measurement benchmark. From this very basic measurement, MCNP input stacks are generated and validated both in predicted signal amplitude and spectral shape. Not modeled at this time are those perturbations from the more recent pulse height light (PHL) tally feature, although what spectral deviations are seen can be largely attributed to not including this small correction. The value of this work is as a proof-of-concept demonstration that with well documented historical testing can be converted into formal radiation measurement benchmarks. This effort would support virtual testing of algorithms and new detector configurations.

  4. 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.

  5. 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.

  6. 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.

  7. A Command Editor Tool for NEXTSTEP

    DTIC Science & Technology

    1993-07-01

    appears and presents the hierarchy of CEMenuCells A Command Editor Tool for NEXTSTEP 2 of 27 m arble Final Report for Contract # DAAHO1-93-C-R013 in the...icon, "Default" status, state list, textual description, tool sta- A Command Editor Tool for NEXTSTEP 3 of 27 m arble Final Report for Contract... arble Final Report for Contract # DAAH01-93-C-R013 FIGURE 7 Configuration of a TAV 3.0.. Acietr O ev 3.1 luBman d aetn Cmoe a ConQ summw t. Paletta e

  8. Voxel2MCNP: a framework for modeling, simulation and evaluation of radiation transport scenarios for Monte Carlo codes.

    PubMed

    Pölz, Stefan; Laubersheimer, Sven; Eberhardt, Jakob S; Harrendorf, Marco A; Keck, Thomas; Benzler, Andreas; Breustedt, Bastian

    2013-08-21

    The basic idea of Voxel2MCNP is to provide a framework supporting users in modeling radiation transport scenarios using voxel phantoms and other geometric models, generating corresponding input for the Monte Carlo code MCNPX, and evaluating simulation output. Applications at Karlsruhe Institute of Technology are primarily whole and partial body counter calibration and calculation of dose conversion coefficients. A new generic data model describing data related to radiation transport, including phantom and detector geometries and their properties, sources, tallies and materials, has been developed. It is modular and generally independent of the targeted Monte Carlo code. The data model has been implemented as an XML-based file format to facilitate data exchange, and integrated with Voxel2MCNP to provide a common interface for modeling, visualization, and evaluation of data. Also, extensions to allow compatibility with several file formats, such as ENSDF for nuclear structure properties and radioactive decay data, SimpleGeo for solid geometry modeling, ImageJ for voxel lattices, and MCNPX's MCTAL for simulation results have been added. The framework is presented and discussed in this paper and example workflows for body counter calibration and calculation of dose conversion coefficients is given to illustrate its application.

  9. 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

  10. 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).

  11. 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…

  12. Open Simulation Laboratories [Guest editors' introduction

    DOE PAGES

    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.

  13. 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.

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

    DOE PAGES

    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

  15. 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.

  16. 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.

  17. 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.

  18. 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.

  19. 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.

  20. 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.

  1. 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…

  2. Comparison of EGS4 and MCNP Monte Carlo codes when calculating radiotherapy depth doses.

    PubMed

    Love, P A; Lewis, D G; Al-Affan, I A; Smith, C W

    1998-05-01

    The Monte Carlo codes EGS4 and MCNP have been compared when calculating radiotherapy depth doses in water. The aims of the work were to study (i) the differences between calculated depth doses in water for a range of monoenergetic photon energies and (ii) the relative efficiency of the two codes for different electron transport energy cut-offs. The depth doses from the two codes agree with each other within the statistical uncertainties of the calculations (1-2%). The relative depth doses also agree with data tabulated in the British Journal of Radiology Supplement 25. A discrepancy in the dose build-up region may by attributed to the different electron transport algorithims used by EGS4 and MCNP. This discrepancy is considerably reduced when the improved electron transport routines are used in the latest (4B) version of MCNP. Timing calculations show that EGS4 is at least 50% faster than MCNP for the geometries used in the simulations.

  3. 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

  4. 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.

  5. 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.

  6. 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.

  7. Unified Meta-Component Model Specification Editor

    DTIC Science & Technology

    2004-04-20

    relationship between the two major user interface modules, the editor and wizard, and their associated features. Functional to module mapping diagrams are...SUBJECT TERMS 16. SECURITY CLASSIFICATION OF: 17. LIMITATION OF ABSTRACT Same as Report (SAR) 18 . NUMBER OF PAGES 148 19a. NAME OF RESPONSIBLE...PERSON a. REPORT unclassified b. ABSTRACT unclassified c. THIS PAGE unclassified Standard Form 298 (Rev. 8-98) Prescribed by ANSI Std Z39- 18

  8. 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)

  9. 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.

  10. 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.

  11. 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.

  12. 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

  13. 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

  14. 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.

  15. 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

  16. 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.

  17. Meet the Editor: Global Biogeochemical Cycles

    NASA Astrophysics Data System (ADS)

    Kumar, Mohi

    Meinrat Andreae was named the editor of the AGU's journal Global Biogeochemical Cycles last year.Andreae, director of the biogeochemistry department at the Max Plank Institute for Chemistry (MPIC), located in Mainz, Germany said that he plans to maintain the journal as a resource that highlights the broad spectrum of interdisciplinary themes that showcase the interactions between the biosphere and the geosphere. “Our special niche is in the field of larger-scale, more integrative studies that have global scope,” he explained.

  18. 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

  19. 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.

  20. 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

  1. 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

  2. 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.

  3. Web-Based Media Contents Editor for UCC Websites

    NASA Astrophysics Data System (ADS)

    Kim, Seoksoo

    The purpose of this research is to "design web-based media contents editor for establishing UCC(User Created Contents)-based websites." The web-based editor features user-oriented interfaces and increased convenience, significantly different from previous off-line editors. It allows users to edit media contents online and can be effectively used for online promotion activities of enterprises and organizations. In addition to development of the editor, the research aims to support the entry of enterprises and public agencies to the online market by combining the technology with various UCC items.

  4. 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

  5. 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.

  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. 3D neutronic calculations: CAD-MCNP methodology applied to vessel activation in KOYO-F

    NASA Astrophysics Data System (ADS)

    Herreras, Y.; Lafuente, A.; Sordo, F.; Cabellos, O.; Perlado, J. M.

    2008-05-01

    This paper presents a methodology for 3D neutronic calculations suitable for complex and extensive geometries. The geometry of the system design is first fully modelled with a CAD program, and subsequently processed through a MCNP-CAD interface in order to generate an MCNP geometry file. Neutronic irradiation results are finally achieved running the MCNPX program, where the geometry input card used is directly the MCNP-CAD interface output. This methodology enables accurate neutronic calculations for complex geometries characterised by high detail levels. This procedure will be applied to the Fast Ignition Fusion Reactor KOYO-F to determine first neutron fluxes calculations along the blanket as well as the material activation in the reduced martensitic 9Cr-1Mo steel vessel.

  8. 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.

  9. 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.

  10. 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.

  11. 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.

  12. A former Editor views the editorial process

    NASA Astrophysics Data System (ADS)

    Freeze, R. Allan

    It was at the AGU Fall Meeting in San Francisco in December 1976, shortly after my appointment as coeditor of Water Resources Research that I first began to realize the strong emotional ties that exist between a scientific community and its journals. Feelings run high, regardless of whether they come from readers, contributors, reviewers, active scientists, or scientific administrators. Opinions are often positive, sometimes negative, usually a mixture of the two; but regardless of their tenor they are delivered to the editor, in person, usually fortissimo. From that day until this, conference life has never been dull. When I meet a colleague in the halls there is never a loss for words, no need to search for a topic of mutual interest; WRR is always there at the ready.

  13. 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

  14. Contribution to the validation of MCNP neutronics design of the advanced neutron source reactor

    SciTech Connect

    Rubio, G.A.; Ougouag, A.M.; Wemple, C.A.; Ryskamp, J.M. )

    1993-01-01

    In the research and development plan of the advanced neutron source (ANS) reactor, one of the steps planned for neutronics design methods validation is to compare computational model results and experimental results for a critical facility exhibiting similarities with the ANS reactor. One such facility is the FOEHN experiment. In this paper, an MCNP model of the FOEHN experiment is developed, and its results are compared with experimental data from the literature. The MCNP models reproduces measured quantities of interest with a high level of agreement.

  15. Implementation of a tree algorithm in MCNP code for nuclear well logging applications.

    PubMed

    Li, Fusheng; Han, Xiaogang

    2012-07-01

    The goal of this paper is to develop some modeling capabilities that are missing in the current MCNP code. Those missing capabilities can greatly help for some certain nuclear tools designs, such as a nuclear lithology/mineralogy spectroscopy tool. The new capabilities to be developed in this paper include the following: zone tally, neutron interaction tally, gamma rays index tally and enhanced pulse-height tally. The patched MCNP code also can be used to compute neutron slowing-down length and thermal neutron diffusion length.

  16. 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)

  17. 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...

  18. 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…

  19. March 2017 Letters to the Editor-in-Chief.

    PubMed

    2017-03-01

    Letters to the Editor-in-Chief of JOSPT as follows: "Regarding 'Unraveling the Complexity of Low Back Pain'" with Authors' Response "Beall's List Has Vanished: What Next?" with Editor-in-Chief Response J Orthop Sports Phys Ther 2017;47(3):219-223. doi:10.2519/jospt.2017.0202.

  20. 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…

  1. 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

  2. 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.

  3. MCNP-PoliMi: a Monte-Carlo code for correlation measurements

    NASA Astrophysics Data System (ADS)

    Pozzi, Sara A.; Padovani, Enrico; Marseguerra, Marzio

    2003-11-01

    The Monte-Carlo simulation of correlation measurements that rely on the detection of fast neutrons and photons from fission requires that particle interactions in each history be described as closely as possible. The MCNP-PoliMi code has been developed from the standard MCNP code to simulate each neutron-nucleus interaction as closely as possible. In particular, neutron interaction and photon production are made correlated and correct neutron and photon fission multiplicities have been implemented. The code output consists in relevant information about each collision, for example the type of collision, the collision target, the energy deposited, and the position of the interaction. A post-processing code has also been developed and can be tailored to model specific detector characteristics. These features make MCNP-PoliMi a versatile tool to simulate particle interactions and detection processes. The application of the MCNP-PoliMi code to simulate neutron and gamma ray detection in a plastic scintillator is presented. PoliMi stands for Politecnico di Milano.

  4. 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.

  5. 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.

  6. 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.

  7. Determination of neutron flux distribution in an Am-Be irradiator using the MCNP.

    PubMed

    Shtejer-Diaz, K; Zamboni, C B; Zahn, G S; Zevallos-Chávez, J Y

    2003-10-01

    A neutron irradiator has been assembled at IPEN facilities to perform qualitative-quantitative analysis of many materials using thermal and fast neutrons outside the nuclear reactor premises. To establish the prototype specifications, the neutron flux distribution and the absorbed dose rates were calculated using the MCNP computer code. These theoretical predictions then allow one to discuss the optimum irradiator design and its performance.

  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. 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.

  10. Performance of the improved version of monte Carlo code A3MCNP for large-scale shielding problems.

    PubMed

    Omura, M; Miyake, Y; Hasegawa, T; Ueki, K; Sato, O; Haghighat, A; Sjoden, G E

    2005-01-01

    A3MCNP (Automatic Adjoint Accelerated MCNP) is a revised version of the MCNP Monte Carlo code, which automatically prepares variance reduction parameters for the CADIS (Consistent Adjoint Driven Importance Sampling) methodology. Using a deterministic 'importance' (or adjoint) function, CADIS performs source and transport biasing within the weight-window technique. The current version of A3MCNP uses the three-dimensional (3-D) Sn transport TORT code to determine a 3-D importance function distribution. Based on simulation of several real-life problems, it is demonstrated that A3MCNP provides precise calculation results with a remarkably short computation time by using the proper and objective variance reduction parameters. However, since the first version of A3MCNP provided only a point source configuration option for large-scale shielding problems, such as spent-fuel transport casks, a large amount of memory may be necessary to store enough points to properly represent the source. Hence, we have developed an improved version of A3MCNP (referred to as A3MCNPV) which has a volumetric source configuration option. This paper describes the successful use of A3MCNPV for a concrete cask neutron and gamma-ray shielding problem, and a PWR dosimetry problem.

  11. Editors' message--Hydrogeology Journal in 2003

    USGS Publications Warehouse

    Voss, Clifford; Olcott, Perry; Schneider, Robert

    2004-01-01

    Hydrogeology Journal appeared in six issues containing a total of 710 pages and 48 major articles, including 31 Papers and 14 Reports, as well as some Technical Notes and Book Reviews. The number of submitted manuscripts continues to increase. The final issue of 2003 also contained the annual volume index. Hydrogeology Journal (HJ) is an international forum for hydrogeology and related disciplines and authors in 2003 were from about 28 countries. Articles advanced hydrogeologic science and described hydrogeologic systems in many regions worldwide. These articles focused on a variety of general topics and on studies of hydrogeology in 24 countries: Afghanistan, Algeria, Argentina, Australia, Bangladesh, Belgium, Canada, Chile, China, Denmark, France, India, Italy, Mexico, Netherlands, New Zealand, Nigeria, Norway, Portugal, Russia, South Africa, Switzerland, Turkey, and U.S.A. The Guest Editor of the 2003 HJ theme issue on “Hydromechanics in Geology and Geotechnics”, Ove Stephansson, assembled a valuable collection of technical reviews and research papers from eminent authors on important aspects of the subject area.

  12. 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.

  13. 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.

  14. 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

  15. 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

  16. 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.

  17. The Letters Not Sent by a Journal Editor

    NASA Astrophysics Data System (ADS)

    2013-04-01

    In the late hours of the night, even the most conscientious of journal editors may slip into writing imaginary letters to cherished authors and reviewers. Here are some of the letters that I composed:

  18. Bibliography or Bust: The "Angst" of Scholarly Editors.

    ERIC Educational Resources Information Center

    Costa, Richard Hauer

    1980-01-01

    Provides evidence indicating not only that the market for articles on literature and language is saturated with submissions, but that the glut creates burgeoning problems for editors, including the problem of rejecting publishable items. (RL)

  19. ANNOUNCEMENT: Greetings from the Editor and Publisher

    NASA Astrophysics Data System (ADS)

    Wäppling, Roger; Williams, Sarah

    2006-01-01

    Physica Scripta is an international physics journal published for the Royal Swedish Academy of Sciences on behalf of the Nordic Science Academies and Physical Societies. This issue marks the beginning of the partnership between the Royal Swedish Academy of Sciences and Institute of Physics Publishing (IOP). We look forward to a fruitful relationship in which Physica Scripta can profit from the international reach of IOP. Authors and readers will benefit from advance publication of articles on the web prior to receiving each month's journal issue. The peer-review system will continue to be managed by Professor Roger Wäppling who will assess each paper before assigning it to an external editor or sending it for refereeing. IOP will receive new article submissions and generate electronic documents suitable for use in the refereeing process. The editorial office in Sweden will then be responsible for these manuscripts up to the final publication decision. Accepted articles will be sent to IOP for copy-editing, typesetting, production and distribution. We aim to provide our authors, referees and readers with an enhanced service for this well-established journal. IOP will maintain and augment Physica Scripta's record in publishing a broad range of high-quality research papers and we will continue to publish Topical Issues as supplements to the regular 12 issues. The popular Comments articles will continue to be published in conjunction with regular papers under this new partnership. We hope that our subscribers will continue to enjoy reading Physica Scripta as a valuable resource for general physics research.

  20. Adapting a thesis to publication style: meeting editors' expectations.

    PubMed

    Johnson, S H

    1996-01-01

    Every year hundreds of thesis reports are completed by graduate students. Many of these end up on nursing journal editors' desks, only to be rejected. What characteristics of a thesis lead to rejection? How can authors develop quality research manuscripts? How can faculty teach graduate students the difference between a thesis and manuscript. This article answers these questions by providing advice from 15 critical care and research journal editors.

  1. Substrate Utilization in the Critically Ill (Letter to the Editor)

    DTIC Science & Technology

    2009-02-01

    pen.sagepub.com/ Nutrition Journal of Parenteral and Enteral http://pen.sagepub.com/content/33/1/111 The online version of this article can be found at: DOI...Published by: http://www.sagepublications.com On behalf of: The American Society for Parenteral & Enteral Nutrition can be found at:Journal of...the Editor Dear Editor, Journal of Parenteral and Enteral Nutrition Volume 33 Number 1 January/February 2009 111 © 2009 American Society for Parenteral

  2. 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.

  3. 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.

  4. 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.

  5. 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.

  6. 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.

  7. 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.

  8. 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.

  9. 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.

  10. 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.

  11. 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.

  12. MCNP optimization of filtered neutron beams for calibration of the SIMPLE detector

    NASA Astrophysics Data System (ADS)

    Oliveira, C.; Giuliani, F.; Girard, T. A.; Marques, J. G.; Salgado, J.; Collar, J. I.; Morlat, T.; Limagne, D.; Waysand, G.

    2004-01-01

    We report an MCNP study of filtered monochromatic neutron beams of energies 25, 54 and 149 keV for response studies of a superheated droplet detector for the SIMPLE experiment. The results identify the importance of the detector temperature stabilizing water bath and the aqueous gel of the detector on the beam quality, in general agreement with recent measurements made on the thermal port of the Portuguese research reactor.

  13. 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.

  14. An investigation of MCNP6.1 beryllium oxide S(α, β) cross sections

    DOE PAGES

    Sartor, Raymond F.; Glazener, Natasha N.

    2016-03-08

    In MCNP6.1, materials are constructed by identifying the constituent isotopes (or elements in a few cases) individually. This list selects the corresponding microscopic cross sections calculated from the free-gas model to create the material macroscopic cross sections. Furthermore, the free-gas model and the corresponding material macroscopic cross sections assume that the interactions of atoms do not affect the nuclear cross sections.

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

    SciTech Connect

    MASSIMO,; PESCARINI,

    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).

  16. 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.

  17. High Altitude Neutral Particle Transport Using the Monte Carlo Simulation Code MCNP with Variable Density Atmosphere

    DTIC Science & Technology

    1991-03-01

    Monti Captain# USAF AFIT.’GNE/F•P/91M-6 (LO IA Approved for public release; distribution unlimited AFIT/IGNE/ENP/91M-6 HIGH ALTITUDE NEUTRAL... distribution unlimited Preface The purpose of this study was to perform Monte Carlo simulations of neutral particle transport with primary and secondary...21 4. Spatial Cell Geometry for Co-Altitude Detectors .................... .................. 44 5. MCNP vs. SMAUG Neutron Fluence at Source Co

  18. 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

  19. 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.

  20. 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.

  1. 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.

  2. 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

  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. 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.

  5. Implementing a computerized text-management system: an editor's view

    SciTech Connect

    Mason, J.D.

    1980-01-01

    The advent of sophisticated function-key-driven programs for handling text on a video-display terminal enables the editorial staff of a publications department to take an active role on a computerized text-management team, along with compositors and other keyboard operators. Although there are still many things that editors cannot do on a computer terminal, the bulk of manipulating straight text can be speeded, and the problems of rekeyboarding and interpretation of editorial markings can be largely bypassed. The computer also gives editors new tools that open the way for greater control over both the editorial process and the quality of technical publishing. 5 figures.

  6. 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

  7. 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

  8. Righting the Wrongs of Writing: Copy Editors Speak Out

    ERIC Educational Resources Information Center

    Alexander, Jaclyn J.; Wall, Judy

    1975-01-01

    The major part of APGA Press production editors' jobs is copy editing manuscripts before they are set in type. Two APGA Press Staff members use specific examples to illustrate the grammatical and stylistic errors that cause problems for them and, if not corrected, for readers. (Author)

  9. 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.

  10. 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…

  11. Particle size fraction -Response: Letter to the Editors

    EPA Science Inventory

    To the Editors: We, the undersigned, would like to comment on the article by Cho et al. (Cho et al. 2009), which was published in the November 2009 issue (volume 11, number 11, page 1682-1689) of Environmental Health Perspectives. We read the paper with great interest as the dis...

  12. 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-...

  13. 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…

  14. 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.

  15. Ethical dilemmas in scientific publication: pitfalls and solutions for editors.

    PubMed

    Gollogly, Laragh; Momen, Hooman

    2006-08-01

    Editors of scientific journals need to be conversant with the mechanisms by which scientific misconduct is amplified by publication practices. This paper provides definitions, ways to document the extent of the problem, and examples of editorial attempts to counter fraud. Fabrication, falsification, duplication, ghost authorship, gift authorship, lack of ethics approval, non-disclosure, 'salami' publication, conflicts of interest, auto-citation, duplicate submission, duplicate publications, and plagiarism are common problems. Editorial misconduct includes failure to observe due process, undue delay in reaching decisions and communicating these to authors, inappropriate review procedures, and confounding a journal's content with its advertising or promotional potential. Editors also can be admonished by their peers for failure to investigate suspected misconduct, failure to retract when indicated, and failure to abide voluntarily by the six main sources of relevant international guidelines on research, its reporting and editorial practice. Editors are in a good position to promulgate reasonable standards of practice, and can start by using consensus guidelines on publication ethics to state explicitly how their journals function. Reviewers, editors, authors and readers all then have a better chance to understand, and abide by, the rules of publishing.

  16. New Tools to Prepare ACE Cross-section Files for MCNP Analytic Test Problems

    SciTech Connect

    Brown, Forrest B.

    2016-06-17

    Monte Carlo calculations using one-group cross sections, multigroup cross sections, or simple continuous energy cross sections are often used to: (1) verify production codes against known analytical solutions, (2) verify new methods and algorithms that do not involve detailed collision physics, (3) compare Monte Carlo calculation methods with deterministic methods, and (4) teach fundamentals to students. In this work we describe 2 new tools for preparing the ACE cross-section files to be used by MCNP® for these analytic test problems, simple_ace.pl and simple_ace_mg.pl.

  17. A system of materials composition and geometry arrangement for fast neutron beam thermalization: An MCNP study

    NASA Astrophysics Data System (ADS)

    Uhlář, Radim; Alexa, Petr; Pištora, Jaromír

    2013-03-01

    Compact deuterium-tritium neutron generators emit fast neutrons (14.2 MeV) that have to be thermalized for neutron activation analysis experiments. To maximize thermal neutron flux and minimize epithermal and fast neutron fluxes across the output surface of the neutron generator facility, Monte Carlo calculations (MCNP5; Los Alamos National Laboratory) for different moderator types and widths and collimator and reflector designs have been performed. A thin lead layer close to the neutron generator as neutron multiplier followed by polyethylene moderator and surrounded by a massive lead and nickel collimator and reflector was obtained as the optimum setup.

  18. 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

  19. Neutronic conceptual design of the ETRR-2 cold-neutron source using the MCNP code

    NASA Astrophysics Data System (ADS)

    Khalil, M. Y.; Shaat, M. K.; Abdelfattah, A. Y.

    2005-04-01

    A conceptual neutronic design of the cold-neutron source (CNS) for the Egyptian second research reactor (ETRR-2) was done using the MCNP code. Parametric analysis to chose the type and geometry of the moderator, and the required CNS dimensions to maximize the cold neutron production was performed. The moderator cell has a spherical annulus structure containing liquid hydrogen. The cold neutron gain and cold neutron brightness are calculated together with the nuclear heat load of the CNS. Analysis of the estimated performance of the CNS has been done regarding the effect of void fraction in the moderator cell together with the ortho: para ratio.

  20. MCNP simulation and spectrum unfolding for an NaI monitor of radioactivity in aquatic systems

    NASA Astrophysics Data System (ADS)

    Mertens, C.; De Lellis, C.; Van Put, P.; Tondeur, F.

    2007-09-01

    Spectrum unfolding can be implemented when the angular distribution of the radiation fluence is known, e.g. when the source-detector geometry is fixed. In the case of the system developed by Institut National des Radio-Elements (IRE) for monitoring radioactivity in aquatic systems, the source is an infinite homogenous medium surrounding the monitor, with constant density. Its response function for gamma rays is calculated with MCNP4.C2. The simulation model is validated with reference measurements of standard sources diluted in a drum. Results of unfolding with UMG 3.3 are presented for this situation, and for a measurement in sea water.

  1. 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.

  2. In Vessel Exposure Distributions Evaluated with MCNP5 for Atucha II

    NASA Astrophysics Data System (ADS)

    Longhino, Juan Manuel; Blaumann, Herman; Zamonsky, Gabriel

    2009-08-01

    Preliminary assessment of the flux and neutron-induced damage was obtained for all peripheral structures in Atucha II NPP. Maximum exposure zones were identified, and four group fluxes and DPA rates were obtained for the Moderator Tank, downcomer, inner RPV, 1/4 depth in RPV and external air. MCNP5 was used for this purpose, after developing a suitable model for the transport from core to out-of-vessel positions. This model allows also further evaluation of fluxes and detector responses in ex-core positions.

  3. 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.

  4. Editors-in-Chief of Medical Journals: Are They Experts, Authorities, Both, or Neither?

    ERIC Educational Resources Information Center

    Zsindely, Sandor; Schubert, Andras

    1989-01-01

    Uses citation analysis to study the professional status and influence of the editors-in-chief of 769 medical journals. Finds that these editors-in-chief are, at least in their own specialties, not necessarily experts but authorities. (SR)

  5. 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.

  6. Neutrons Flux Distributions of the Pu-Be Source and its Simulation by the MCNP-4B Code

    NASA Astrophysics Data System (ADS)

    Faghihi, F.; Mehdizadeh, S.; Hadad, K.

    Neutron Fluence rate of a low intense Pu-Be source is measured by Neutron Activation Analysis (NAA) of 197Au foils. Also, the neutron fluence rate distribution versus energy is calculated using the MCNP-4B code based on ENDF/B-V library. Theoretical simulation as well as our experimental performance are a new experience for Iranians to make reliability with the code for further researches. In our theoretical investigation, an isotropic Pu-Be source with cylindrical volume distribution is simulated and relative neutron fluence rate versus energy is calculated using MCNP-4B code. Variation of the fast and also thermal neutrons fluence rate, which are measured by NAA method and MCNP code, are compared.

  7. 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

  8. 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.

  9. 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

    2016-03-01

    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. PACS number(s): 87.56.bg.

  10. 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

    2016-03-08

    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.

  11. 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.

  12. 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.

  13. 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…

  14. Preparing Students To Work on Newspaper Copy Desks: Are Educators Meeting Editors' Expectations?

    ERIC Educational Resources Information Center

    Auman, Ann E.; Cook, Betsy B.

    A study surveyed two groups in the fall of 1994, journalism educators and newspaper editors. Educators completed a survey regarding the course content and skill areas emphasized in beginning level copy editing courses, while editors were asked to respond to questions regarding the skills they expect entry-level copy editors to have. Respondents…

  15. 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.

  16. 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.

  17. 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.

  18. Conversion coefficients for determination of dispersed photon dose during radiotherapy: NRUrad input code for MCNP

    PubMed Central

    Krstic, D.; Nikezic, D.

    2017-01-01

    Radiotherapy is a common cancer treatment module, where a certain amount of dose will be delivered to the targeted organ. This is achieved usually by photons generated by linear accelerator units. However, radiation scattering within the patient’s body and the surrounding environment will lead to dose dispersion to healthy tissues which are not targets of the primary radiation. Determination of the dispersed dose would be important for assessing the risk and biological consequences in different organs or tissues. In the present work, the concept of conversion coefficient (F) of the dispersed dose was developed, in which F = (Dd/Dt), where Dd was the dispersed dose in a non-targeted tissue and Dt is the absorbed dose in the targeted tissue. To quantify Dd and Dt, a comprehensive model was developed using the Monte Carlo N-Particle (MCNP) package to simulate the linear accelerator head, the human phantom, the treatment couch and the radiotherapy treatment room. The present work also demonstrated the feasibility and power of parallel computing through the use of the Message Passing Interface (MPI) version of MCNP5. PMID:28362837

  19. Comparison between EGSnrc, Geant4, MCNP5 and Penelope for mono-energetic electron beams.

    PubMed

    Archambault, John Paul; Mainegra-Hing, Ernesto

    2015-07-07

    A simple geometry is chosen to highlight similarities and differences of current electron transport algorithms implemented in four Monte Carlo codes commonly used in radiation physics. Energy deposited in a water-filled sphere by mono-energetic electron beams was calculated using EGSnrc, Geant4, MCNP5 and Penelope as the radius of the sphere varied from 0.25 cm to 4.5 cm for beam energies of 0.5 MeV, 1.0 MeV and 5.0 MeV. The calculations were performed in single-scattering mode (where applicable) and in condensed history mode. A good agreement is found for the single-scattering calculations except for the in-air case at 0.5 MeV where differences increase with decreasing radius up to 5% between EGSnrc and Penelope. Differences between results calculated with the default user settings when compared to their own single-scattering modes are under 5% for all codes when the sphere is surrounded by vacuum, however, large differences occur for Geant4, MCNP5 and Penelope when air is introduced around the sphere. Finally, the parameters associated with the multiple scattering algorithms were tuned reducing these differences below 10% for these codes at the expense of increased computation time.

  20. Use of MCNP for characterization of reactor vessel internals waste from decommissioned nuclear reactors

    SciTech Connect

    Love, E.F.; Pauley, K.A.; Reid, B.D.

    1995-09-01

    This study describes the use of the Monte Carlo Neutron-Photon (MCNP) code for determining activation levels of irradiated reactor vessel internals hardware. The purpose of the analysis is to produce data for the Department of Energy`s Greater-Than-Class C Low-Level Radioactive Waste Program. An MCNP model was developed to analyze the Yankee Rowe reactor facility. The model incorporates reactor geometry, material compositions, and operating history data acquired from Yankee Atomic Electric Company. In addition to the base activation analysis, parametric studies were performed to determine the sensitivity of activation to specific parameters. A component sampling plan was also developed to validate the model results, although the plan was not implemented. The calculations for the Yankee Rowe reactor predict that only the core baffle and the core support plates will be activated to levels above the Class C limits. The parametric calculations show, however, that the large uncertainties in the material compositions could cause errors in the estimates that could also increase the estimated activation level of the core barrel to above the Class C limits. Extrapolation of the results to other reactor facilities indicates that in addition to the baffle and support plates, core barrels may also be activated to above Class C limits; however the classification will depend on the specific operating conditions of the reactor and the specific material compositions of the metal, as well as the use of allowable concentration averaging practices in packaging and classifying the waste.

  1. 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.

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

    DOE PAGES

    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

  3. Conversion coefficients for determination of dispersed photon dose during radiotherapy: NRUrad input code for MCNP.

    PubMed

    Shahmohammadi Beni, Mehrdad; Ng, C Y P; Krstic, D; Nikezic, D; Yu, K N

    2017-01-01

    Radiotherapy is a common cancer treatment module, where a certain amount of dose will be delivered to the targeted organ. This is achieved usually by photons generated by linear accelerator units. However, radiation scattering within the patient's body and the surrounding environment will lead to dose dispersion to healthy tissues which are not targets of the primary radiation. Determination of the dispersed dose would be important for assessing the risk and biological consequences in different organs or tissues. In the present work, the concept of conversion coefficient (F) of the dispersed dose was developed, in which F = (Dd/Dt), where Dd was the dispersed dose in a non-targeted tissue and Dt is the absorbed dose in the targeted tissue. To quantify Dd and Dt, a comprehensive model was developed using the Monte Carlo N-Particle (MCNP) package to simulate the linear accelerator head, the human phantom, the treatment couch and the radiotherapy treatment room. The present work also demonstrated the feasibility and power of parallel computing through the use of the Message Passing Interface (MPI) version of MCNP5.

  4. Benchmarking of MCNP for calculating dose rates at an interim storage facility for nuclear waste.

    PubMed

    Heuel-Fabianek, Burkhard; Hille, Ralf

    2005-01-01

    During the operation of research facilities at Research Centre Jülich, Germany, nuclear waste is stored in drums and other vessels in an interim storage building on-site, which has a concrete shielding at the side walls. Owing to the lack of a well-defined source, measured gamma spectra were unfolded to determine the photon flux on the surface of the containers. The dose rate simulation, including the effects of skyshine, using the Monte Carlo transport code MCNP is compared with the measured dosimetric data at some locations in the vicinity of the interim storage building. The MCNP data for direct radiation confirm the data calculated using a point-kernel method. However, a comparison of the modelled dose rates for direct radiation and skyshine with the measured data demonstrate the need for a more precise definition of the source. Both the measured and the modelled dose rates verified the fact that the legal limits (<1 mSv a(-1)) are met in the area outside the perimeter fence of the storage building to which members of the public have access. Using container surface data (gamma spectra) to define the source may be a useful tool for practical calculations and additionally for benchmarking of computer codes if the discussed critical aspects with respect to the source can be addressed adequately.

  5. 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

  6. 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.

  7. 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.

  8. William E. Edmonston, Jr.: Editor, 1968-1976.

    PubMed

    Kihlstrom, John F; Frischholz, Edward J

    2010-10-01

    This article is part of an occasional series profiling editors of the American Journal of Clinical Hypnosis (AJCH). William E. Edmonston was the second editor, succeeding Milton H. Erickson. His research focused on the use of conditioning paradigms and psychophysiological measures to explore a wide variety of hypnotic phenomena, leading to a "neo-Pavlovian" theory of neutral hypnosis as physiological relaxation (anesis). A longtime professor of psychology at Colgate University, he created an interdisciplinary undergraduate major in neuroscience, and was named New York State College Professor of the Year in 1988. He gave the Journal a new look, and a greater balance of clinical and experimental papers. The article also provides background on George Barton Cutten, George H. Estabrooks, and Frank A. Pattie, pioneers of hypnosis who were linked to Edmonston.

  9. 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.

  10. Incremental Expression Parsing for Syntax-Directed Editors

    DTIC Science & Technology

    1982-10-27

    Cretsna*refr a+b+cde ftth I / \\ ,:I \\ I’\\ / , I \\ b- ’ I I € d Figure 4-3: Correct syntax tree for"a + (b + c" d" e) ftgth" The tokens between, the...Schwartz. The Design of a Language-Directed Editor for Block-Structured Languages. In Proceedings of the ACM SIGPLAN SIGOA Symposium on Text Manipulation

  11. Reference Accuracy: Authors', Reviewers', Editors', and Publishers' Contributions

    PubMed Central

    2014-01-01

    Scientific authors are responsible for the accuracy of their writings and references to others' works. However, relying on authors is not enough when it comes to processing their manuscripts. Joint efforts of authors, peer reviewers, editors, and publishers throughout the publishing process may prevent most reference errors. This article analyzes essential aspects of bibliographic management and focuses on the importance of validating references by all stakeholders of scholarly publishing. PMID:25469055

  12. JGR-Solid Earth and Planets GP editor appointed

    NASA Astrophysics Data System (ADS)

    Ken Hoffman (Physics Department, California Polytechnic State University, San Luis Obispo) has been appointed GP editor for papers submitted to the Journal of Geophysical Research—Solid Earth and Planets. His tenure will be from January 1987 to December 1988. Hoffman holds a Ph.D. in geophysics from the University of California, Berkeley, and has published extensively in the areas of rock magnetism, paleomagnetism, lunar paleointensity, and most recently, geomagnetic dipole field reversal modeling.

  13. 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.

  14. 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.

  15. 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.

  16. 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

  17. 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.

  18. 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

  19. 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.

  20. 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.

  1. 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.

  2. Determination of Weighting Functions and Neutron Sensitivity for C6D6 Detectors by MCNP

    NASA Astrophysics Data System (ADS)

    Borella, A.; Aerts, G.; Gunsing, F.; Moens, A.; Wynants, R.; Schillebeeckx, P.

    2005-05-01

    To determine capture cross sections using C6D6 detectors, the total energy detection principle in combination with the Pulse Height Weighting Technique (PHWT) is very often applied. The quality of the data deduced from such measurements depends strongly on the response of the detection system used for the calculation of the weighting function. In addition, for nuclei with small capture-to-scattering ratios, i.e., light and neutron magic nuclei, the proper determination of the capture cross section also depends on the correction for the neutron sensitivity of the capture detector. We used the MCNP code to simulate both the gamma and neutron transport of the detection system and deduce the weighting functions and neutron sensitivity.

  3. MCNP analysis of a multilayer phoswich detector for β-particle dosimetry and spectroscopy

    NASA Astrophysics Data System (ADS)

    Farsoni, A. T.; Hamby, D. M.

    2005-12-01

    To measure and study energy deposition of β-particles at different depths, a triple-layer phoswich detector has been designed. The phoswich detector consists of BC-400/CaF2:Eu/BC-444 with decay time constants of 2.4, 940 and 264 ns, respectively, all with thicknesses corresponding to that necessary to completely stop 0.1 MeV electrons in the first layer, 1.0 MeV electrons in the second layer and 2.5 MeV electrons in the third layer. Monte Carlo N-Particle (MCNP) version 4B was used to simulate energy deposition in each layer from monoenergetic β-particles. The simulations and measurements revealed that the traditional rise time measurement technique is not able to provide appropriate and accurate pulse shape discrimination for this type of detector.

  4. 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.

  5. Comparison of a laboratory spectrum of Eu-152 with results of simulation using the MCNP code

    NASA Astrophysics Data System (ADS)

    Ródenas, J.; Gallardo, S.; Ortiz, J.

    2007-09-01

    Detectors used for gamma spectrometry must be calibrated for each geometry considered in environmental radioactivity laboratories. This calibration is performed using a standard solution containing gamma emitter sources. Nevertheless, the efficiency curves obtained are periodically checked using a source such as 152Eu emitting many gamma rays that cover a wide energy range (20-1500 keV). 152Eu presents a problem because it has a lot of peaks affected by True Coincidence Summing (TCS). Two experimental measures have been performed placing the source (a Marinelli beaker) at 0 and 10 cm from the detector. Both spectra are simulated by the MCNP 4C code, where the TCS is not reproduced. Therefore, the comparison between experimental and simulated peak net areas permits one to choose the most convenient peaks to check the efficiency curves of the detector.

  6. 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.

  7. 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.

  8. 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)

  9. 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.

  10. EBR-II Static Neutronic Calculations by PHISICS / MCNP6 codes

    SciTech Connect

    Paolo Balestra; Carlo Parisi; Andrea Alfonsi

    2016-02-01

    The International Atomic Energy Agency (IAEA) launched a Coordinated Research Project (CRP) on the Shutdown Heat Removal Tests (SHRT) performed in the '80s at the Experimental fast Breeder Reactor EBR-II, USA. The scope of the CRP is to improve and validate the simulation tools for the study and the design of the liquid metal cooled fast reactors. Moreover, training of the next generation of fast reactor analysts is being also considered the other scope of the CRP. In this framework, a static neutronic model was developed, using state-of-the art neutron transport codes like SCALE/PHISICS (deterministic solution) and MCNP6 (stochastic solution). Comparison between both solutions is briefly illustrated in this summary.

  11. 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.

  12. 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

  13. Thorium-based mixed oxide fuel in a pressurized water reactor: A feasibility analysis with MCNP

    NASA Astrophysics Data System (ADS)

    Tucker, Lucas Powelson

    This dissertation investigates techniques for spent fuel monitoring, and assesses the feasibility of using a thorium-based mixed oxide fuel in a conventional pressurized water reactor for plutonium disposition. Both non-paralyzing and paralyzing dead-time calculations were performed for the Portable Spectroscopic Fast Neutron Probe (N-Probe), which can be used for spent fuel interrogation. Also, a Canberra 3He neutron detector's dead-time was estimated using a combination of subcritical assembly measurements and MCNP simulations. Next, a multitude of fission products were identified as candidates for burnup and spent fuel analysis of irradiated mixed oxide fuel. The best isotopes for these applications were identified by investigating half-life, photon energy, fission yield, branching ratios, production modes, thermal neutron absorption cross section and fuel matrix diffusivity. 132I and 97Nb were identified as good candidates for MOX fuel on-line burnup analysis. In the second, and most important, part of this work, the feasibility of utilizing ThMOX fuel in a pressurized water reactor (PWR) was first examined under steady-state, beginning of life conditions. Using a three-dimensional MCNP model of a Westinghouse-type 17x17 PWR, several fuel compositions and configurations of a one-third ThMOX core were compared to a 100% UO2 core. A blanket-type arrangement of 5.5 wt% PuO2 was determined to be the best candidate for further analysis. Next, the safety of the ThMOX configuration was evaluated through three cycles of burnup at several using the following metrics: axial and radial nuclear hot channel factors, moderator and fuel temperature coefficients, delayed neutron fraction, and shutdown margin. Additionally, the performance of the ThMOX configuration was assessed by tracking cycle length, plutonium destroyed, and fission product poison concentration.

  14. 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

  15. Problems faced by editors of peer reviewed medical journals.

    PubMed

    Jawaid, Shaukat A

    2004-01-01

    Forty-six medical and dental journals are published from Pakistan of which only 29 are currently recognized by the Pakistan Medical and Dental Council. Only a few are peer reviewed. Six are indexed in Medline while EMBASE Excerpta Medica and World Health Organization Index Medicus for Eastern Mediterranean Region cover others. Editors of the peer reviewed medical journals are faced with numerous problems, which relate to the authors. Some of these are: shortage of quality of manuscripts, poor quality of reviewers, problems with indexation in international indexing services particularly Medline, duplicate submission and authorship and lastly, financial problems. Patronage from the Pharma industry is the major source of revenue which itself has serious implications. Editing a medical journal is a very stressful job and the editors have to work under too many pressures. A lot of useful data is presented at medical conferences, but a vast majority of it remains unpublished for various reasons, which adversely affects the citation rate from scientists from the developing third world countries in the world of medical literature. A few lectures on medical writing and research methodology to final year medical students will expose them to the art of medical writing. Specialty organizations can be persuaded to have a session on medical writing at their conferences, which will be extremely helpful not only to the potential new authors but also others, thereby improving the quality of their manuscripts. In addition to regular seminars, workshops for authors, reviewers and training courses for editors, subscribing to local medical journals by healthcare professionals and libraries are some of the measures that will help improve the situation to a great extent.

  16. 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

  17. 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

  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, 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...

  20. 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...

  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, 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...

  3. An editor for the generation and customization of geometry restraints

    PubMed Central

    Moriarty, Nigel W.; Adams, Paul D.

    2017-01-01

    Chemical restraints for use in macromolecular structure refinement are produced by a variety of methods, including a number of programs that use chemical information to generate the required bond, angle, dihedral, chiral and planar restraints. These programs help to automate the process and therefore minimize the errors that could otherwise occur if it were performed manually. Furthermore, restraint-dictionary generation programs can incorporate chemical and other prior knowledge to provide reasonable choices of types and values. However, the use of restraints to define the geometry of a molecule is an approximation introduced with efficiency in mind. The representation of a bond as a parabolic function is a convenience and does not reflect the true variability in even the simplest of molecules. Another complicating factor is the interplay of the molecule with other parts of the macromolecular model. Finally, difficult situations arise from molecules with rare or unusual moieties that may not have their conformational space fully explored. These factors give rise to the need for an interactive editor for WYSIWYG interactions with the restraints and molecule. Restraints Editor, Especially Ligands (REEL) is a graphical user interface for simple and error-free editing along with additional features to provide greater control of the restraint dictionaries in macromolecular refinement. PMID:28177308

  4. 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.

  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. Questions of modeling the non-stationary thermal neutron transport in two-zone systems with Plexiglas by means of the MCNP code

    NASA Astrophysics Data System (ADS)

    Wiącek, U.; Krynicka, E.; Drozdowicz, K.; Gabańska, B.

    2007-09-01

    The pulsed thermal neutron experiments have been modeled in two-zone spherical and cylindrical systems. The outer zone of Plexiglas has surrounded either hydrogenous or non-hydrogenous inner zone. The MCNP code has been used in the numerical simulations. The standard poly.01t MCNP library and its modification by the authors have been used for Plexiglas. A considerable improvement of the agreement with experimental results is observed while using the proposed modification.

  7. 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 ...

  8. Visual Impairment

    MedlinePlus

    ... Loss Surgery? A Week of Healthy Breakfasts Shyness Visual Impairment KidsHealth > For Teens > Visual Impairment Print A ... with the brain, making vision impossible. What Is Visual Impairment? Many people have some type of visual ...

  9. Uncertainty analysis in the simulation of X-ray spectra in the diagnostic range using the MCNP5 code.

    PubMed

    Gallardo, S; Querol, A; Ródenas, J; Verdú, G

    2011-01-01

    An accurate knowledge of the photonic spectra emitted by X-ray tubes in radiodiagnostics is essential to better estimate the imparted dose to patients and to improve the image quality obtained with these devices. In this work, several X-ray spectra have been simulated using the MCNP5 code to simulate X-ray production in a commercial device. To validate the Monte Carlo results, simulated spectra have been compared to those extracted from the IPEM 78 database. The uncertainty associated to some geometrical features of the tube and its effect on the simulated spectra has been analyzed using the Noether-Wilks formula. This analysis has been focused on the thickness of collimators, filters, shielding and barrel shutter. Furthermore, results show that the uncertainty due to geometrical parameters (0.98% in terms of Root Mean Squared) is higher than the statistical uncertainty associated to the MCNP5 calculations.

  10. 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.

  11. ENDF/B-VI Release 3 Cross Section Library for Use with the MCNP Monte Carlo Code.

    SciTech Connect

    MASSIMO,; PESCARINI,

    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 with 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.

  12. ENDF/B-V and ENDF/B-VI results for UO{sub 2} lattice benchmark problems using MCNP

    SciTech Connect

    Mosteller, R.D.

    1998-12-31

    Calculations for the ANS UO{sub 2} lattice benchmark have been performed with the MCNP Monte Carlo code and its ENDF/B-V and ENDF/B-VI continuous-energy libraries. The ENDF/B-V library produces significantly better agreement with the benchmark value for k{sub eff} than do the ENDF/B-VI libraries. However, the pin power distributions are essentially the same irrespective of the library.

  13. 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.

  14. 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

  15. A benchmarked MCNP model of the in vivo detection of gadolinium by prompt gamma neutron activation analysis

    NASA Astrophysics Data System (ADS)

    Gräfe, J. L.; McNeill, F. E.; Byun, S. H.; Chettle, D. R.; Noseworthy, M. D.

    2010-08-01

    Gadolinium (Gd)-based contrast agents are a valuable diagnostic aid for magnetic resonance imaging (MRI). The amount of free Gd deposited in tissues following contrast enhanced MRI is of toxicological concern. The McMaster University in vivo prompt gamma neutron activation analysis facility has been adapted for the detection of Gd in the kidney, liver, and the leg muscle. A simple model of the HPGe detector used for detection of the prompt γ-rays following Gd neutron capture has been created using Monte Carlo simulation. A separate simulation describing the neutron collimation and shielding apparatus has been modified to determine the neutron capture rate in the Gd phantoms. The MCNP simulation results have been confirmed by experimental measurement. The deviations between MCNP and the experiment were between 1% and 18%, with an average deviation of 3.8 ± 6.7%. The validated MCNP model is to be used to improve the Gd in vivo measurement sensitivity by determining the best neutron moderator/reflector arrangement.

  16. MCNP Super Lattice Method for VHTR ORIGEN2.2 Nuclear Library Improvement Based on ENDF/B-VII

    SciTech Connect

    G. S. Chang; J. R. Parry

    2010-10-01

    The advanced Very High Temperature gas-cooled Reactor (VHTR) achieves simplification of safety through reliance on innovative features and passive systems. One of the VHTRs innovative features is the reliance on ceramic-coated fuel particles to retain the fission products under extreme accident conditions. The effect of the random fuel kernel distribution in the fuel prismatic block creates a double-heterogeneous lattice, which needs to be addressed through the use of the newly developed prismatic super Kernel-by-Kernel Fuel (KbKF) lattice model method. Based on the new ENDF/B-VII nuclear cross section evaluated data, the developed KbKF super lattice model was then used with MCNP to calculate the material isotopes neutron reaction rates, such as, (n,?); (n,n’); (n,2n’); (n,f); (n,p); (n,?). Then, the MCNP-calculated results are rearranged to generate a set of new libraries “VHTRXS.lib,” for the ORIGEN2.2 isotopes depletion and build-up analysis code. The libraries contain one group cross section data for the structural light elements, actinides, and fission products that can be applied in the VHTR related fuel burnup and material transmutation analysis codes. The efficiency and ease of use of the MCNP method to generate and update the ORIGEN2.2 one-group spectrum weighed cross section library for VHTR was demonstrated.

  17. Visual Perception versus Visual Function.

    ERIC Educational Resources Information Center

    Lieberman, Laurence M.

    1984-01-01

    Disfunctions are drawn between visual perception and visual function, and four optometrists respond with further analysis of the visual perception-visual function controversy and its implications for children with learning problems. (CL)

  18. 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.

  19. 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.

  20. Upcoming IJTMB Initiatives from the Interim Executive Editor

    PubMed Central

    Kennedy, Ann Blair

    2016-01-01

    It is an honor and a privilege to be appointed the Interim Executive Editor for the IJTMB; I am lucky to have some initiatives that were already in development by the previous editorial team that I hope to bring to fruition over the next few months. First, I hope to increase the Journal’s Internet presence through social media to expand readership and encourage new submitters. The second initiative is a mentoring program to assist writers with their submissions to the Journal. Finally, I, and the rest of the editorial staff, will continue to evaluate the process, procedures, and forms used in peer review. I hope to move these initiatives forward and by doing so, bring in new readers, submitters, and reviewers to the Journal. PMID:27974945

  1. 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.

  2. Andreae is New Editor of Global Biogeochemical Cycles

    NASA Astrophysics Data System (ADS)

    Andreae, Meinrat O.

    2004-10-01

    As the incoming editor of Global Biogeochemical Cycles, I would like to introduce myself and my ideas for the journal to Eos readers and to current and potential GBC authors. I've had a somewhat ``roaming'' scientific evolution, coming from ``straight'' chemistry through hard-rock geochemistry to chemical oceanography, the field in which I did my Ph.D. I taught marine chemistry at Florida State University for a number of years, and developed an interest in ocean/atmosphere interactions and atmospheric chemistry. In 1987 I took on my present job at the Max Planck Institute for Chemistry, in Mainz, Germany, and, after leaving the seacoast, my interests shifted to interactions between the terrestrial biosphere and atmosphere, including the role of vegetation fires. My present focus is on the role of biogenic aerosols and biomass smoke in regulating cloud properties and influencing climate.

  3. 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.

  4. Agile High-Fidelity Mcnp Model Development Techniques for Rapid Mechanical Design Iteration

    NASA Astrophysics Data System (ADS)

    Kulesza, Joel A.

    2009-08-01

    In order to finalize mechanical design details and perform the associated radiological analyses for the AP1000 pressurized water reactor integrated head package (IHP) in time to meet industrial obligations, a process was developed that allowed a radiological analyst to rapidly respond to changing design criteria. This process used several tools together, most of which were freely available, that enabled the analyst to rapidly re-model both geometrical and radiological details, perform a three-dimensional dose field analysis with MCNP5, examine the results, and present the results in an informative and easily understandable manner to other technical working groups. Thus far the author has used this process to study the radiological impacts of different sources due to various incore instrumentation thimble assembly (IITA) materials, different IITA shield alloys and geometrical configurations, different MP shroud thicknesses, and parameterized air duct wall thicknesses and complementary shielding. Model processing before execution will be discussed in detail. Techniques will also be described which allow for rapid spatial redistribution based on the modified source term. Post processing tools and methods will also be described that yield both qualitative and quantitative results.

  5. MCNP modeling of a neutron generator and its shielding at Missouri University of Science and Technology

    NASA Astrophysics Data System (ADS)

    Sharma, Manish K.; Alajo, Ayodeji Babatunde; Liu, Xin

    2014-12-01

    The shielding of a neutron generator producing fast neutrons should be sufficient to limit the dose rates to the prescribed values. A deuterium-deuterium neutron generator has been installed in the Nuclear Engineering Department at Missouri University of Science and Technology (Missouri S&T). The generator produces fast neutrons with an approximate energy of 2.5 MeV. The generator is currently shielded with different materials like lead, high-density polyethylene, and borated polyethylene. An MCNP transport simulation has been performed to estimate the dose rates at various places in and around the facility. The simulations incorporated the geometric and composition information of these shielding materials to determine neutron and photon dose rates at three central planes passing through the neutron source. Neutron and photon dose rate contour plots at these planes were provided using a MATLAB program. Furthermore, the maximum dose rates in the vicinity of the facility were used to estimate the annual limit for the generator's hours of operation. A successful operation of this generator will provide a convenient neutron source for basic and applied research at the Nuclear Engineering Department of Missouri S&T.

  6. Utilization of MCNP for the development of spectral stripping algorithms for orthovoltage radiation therapy systems

    NASA Astrophysics Data System (ADS)

    Brown, Steven; Detwiler, Rebecca S.; Lu, Bo; Gopal, Arun; Samant, Sangiv; Baciak, James E.

    2011-10-01

    We are developing a Monte-Carlo based method for spectral stripping of a low-voltage X-ray detector spectrum for calibrating and performing quality assurance with orthovoltage (X-ray) radiation therapy systems. The technique involves a tungsten-based X-ray generator with limited energy spectral information of at the most two half value layers of shielding available from the manufacturer. The goal is to generate a complete energy spectrum of the source from a measured detector spectrum, by correcting for radiation losses and misplaced counts due to Compton scattering and the photoelectric effect. In this work, energy spectra were measured at generator voltages of 150-300 kVp with HPGe and Si detectors, with several optional shielding configurations. The source to detector geometry were modeled in MCNP, and the reaction rates and spatial locations of Compton scattering and photoelectric events in the detectors have been investigated as a function of source energy to gain information on where interactions occur for the given beam collimation and geometry. Photon leakage and energy flux out of the detector were also simulated, and initial spectral stripping has been performed on the HPGe and Si detector spectra.

  7. An improved MCNP version of the NORMAN voxel phantom for dosimetry studies

    NASA Astrophysics Data System (ADS)

    Ferrari, P.; Gualdrini, G.

    2005-09-01

    In recent years voxel phantoms have been developed on the basis of tomographic data of real individuals allowing new sets of conversion coefficients to be calculated for effective dose. Progress in radiation studies brought ICRP to revise its recommendations and a new report, already circulated in draft form, is expected to change the actual effective dose evaluation method. In the present paper the voxel phantom NORMAN developed at HPA, formerly NRPB, was employed with MCNP Monte Carlo code. A modified version of the phantom, NORMAN-05, was developed to take into account the new set of tissues and weighting factors proposed in the cited ICRP draft. Air kerma to organ equivalent dose and effective dose conversion coefficients for antero-posterior and postero-anterior parallel photon beam irradiations, from 20 keV to 10 MeV, have been calculated and compared with data obtained in other laboratories using different numerical phantoms. Obtained results are in good agreement with published data with some differences for the effective dose calculated employing the proposed new tissue weighting factors set in comparison with previous evaluations based on the ICRP 60 report.

  8. MCNP simulation of absorbed energy and dose by iodinated contrast agent

    NASA Astrophysics Data System (ADS)

    He, Wenjun; Mah, Eugene; Huda, Walter; Yao, Hai

    2012-03-01

    The purpose of this study is to investigate the absorbed dose and energy by iodinated contrast medium in diagnostic radiology. A simulation geometry in which an inner sphere (d = 0.2cm, 1cm, 5cm) filled with iodinated contrast medium (or water) is located at the center of a 20cm diameter water sphere was used in simulations performed with MCNP5 codes. Monoenergetic x-rays with energies ranging from 40 to 80keV from a cone beam source were utilized and contrast medium concentration ranged from 100 to 1mg/ml. Absorbed dose ratio (RD) to inner sphere and total absorbed energies ratio (RE) to the whole phantom with and without iodinated contrast medium were investigated. The maximum RD was ~13 for the 0.2cm diameter sphere with 100mg/ml contrast medium. The maximum RE was ~1.05 for the 5cm diameter contrast sphere at 80keV with 100mg/ml contrast medium. Under the same incident photon energy, increasing the inner sphere size from 0.2cm to 5cm caused a ~63% increase in the RD on average. Decreasing the contrast medium concentration from 100 to 10 mg/ml caused a decrease of RD of ~ 76%. A conclusion was reached that although local absorbed dose increase caused by iodinated contrast agent could be high; the increase in total absorbed energy is negligible.

  9. Verification of the Monte Carlo differential operator technique for MCNP{trademark}

    SciTech Connect

    McKinney, G.W.; Iverson, J.L.

    1996-02-01

    The differential operator perturbation technique has been incorporated into the Monte Carlo N-Particle transport code MCNP and will become a standard feature of future releases. This feature includes first and second order terms of the Taylor series expansion for response perturbations related to cross-section data (i.e., density, composition, etc.). Perturbation and sensitivity analyses can benefit from this technique in that predicted changes in one or more tally responses may be obtained for multiple perturbations in a single run. The user interface is intuitive, yet flexible enough to allow for changes in a specific microscopic cross section over a specified energy range. With this technique, a precise estimate of a small change in response is easily obtained, even when the standard deviation of the unperturbed tally is greater than the change. Furthermore, results presented in this report demonstrate that first and second order terms can offer acceptable accuracy, to within a few percent, for up to 20-30% changes in a response.

  10. Performance of the MTR core with MOX fuel using the MCNP4C2 code.

    PubMed

    Shaaban, Ismail; Albarhoum, Mohamad

    2016-08-01

    The MCNP4C2 code was used to simulate the MTR-22 MW research reactor and perform the neutronic analysis for a new fuel namely: a MOX (U3O8&PuO2) fuel dispersed in an Al matrix for One Neutronic Trap (ONT) and Three Neutronic Traps (TNTs) in its core. Its new characteristics were compared to its original characteristics based on the U3O8-Al fuel. Experimental data for the neutronic parameters including criticality relative to the MTR-22 MW reactor for the original U3O8-Al fuel at nominal power were used to validate the calculated values and were found acceptable. The achieved results seem to confirm that the use of MOX fuel in the MTR-22 MW will not degrade the safe operational conditions of the reactor. In addition, the use of MOX fuel in the MTR-22 MW core leads to reduce the uranium fuel enrichment with (235)U and the amount of loaded (235)U in the core by about 34.84% and 15.21% for the ONT and TNTs cases, respectively.

  11. Implementation of On-the-Fly Doppler Broadening in MCNP5 for Multiphysics Simulation of Nuclear Reactors

    SciTech Connect

    William Martin

    2012-11-16

    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. Previous work had established the scientific feasibility of obtaining Doppler-broadened cross sections "on-the-fly" (OTF) during the random walk of the neutron. Thus, when a neutron of energy E enters a material region that is at some temperature T, the cross sections for that material at the exact temperature T are immediately obtained 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. A standalone Fortran code has been developed that generates the OTF library for any isotope that can be processed by NJOY. 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., 250K - 3200K. 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 using OTF cross sections greatly reduces the complexity of the input for MCNP, especially for full-core temperature feedback calculations with many temperature regions. This results in an order of magnitude decrease in the number of input lines for full-core configurations, thus simplifying input preparation and reducing the potential for input errors. Finally, for full-core problems with multiphysics

  12. Benchmarking ENDF/B-VII.1, JENDL-4.0 and JEFF-3.1.1 with MCNP6

    NASA Astrophysics Data System (ADS)

    van der Marck, Steven C.

    2012-12-01

    Recent releases of three major world nuclear reaction data libraries, ENDF/B-VII.1, JENDL-4.0, and JEFF-3.1.1, have been tested extensively using benchmark calculations. The calculations were performed with the latest release of the continuous energy Monte Carlo neutronics code MCNP, i.e. MCNP6. Three types of benchmarks were used, viz. criticality safety benchmarks, (fusion) shielding benchmarks, and reference systems for which the effective delayed neutron fraction is reported. For criticality safety, more than 2000 benchmarks from the International Handbook of Criticality Safety Benchmark Experiments were used. Benchmarks from all categories were used, ranging from low-enriched uranium, compound fuel, thermal spectrum ones (LEU-COMP-THERM), to mixed uranium-plutonium, metallic fuel, fast spectrum ones (MIX-MET-FAST). For fusion shielding many benchmarks were based on IAEA specifications for the Oktavian experiments (for Al, Co, Cr, Cu, LiF, Mn, Mo, Si, Ti, W, Zr), Fusion Neutronics Source in Japan (for Be, C, N, O, Fe, Pb), and Pulsed Sphere experiments at Lawrence Livermore National Laboratory (for 6Li, 7Li, Be, C, N, O, Mg, Al, Ti, Fe, Pb, D2O, H2O, concrete, polyethylene and teflon). The new functionality in MCNP6 to calculate the effective delayed neutron fraction was tested by comparison with more than thirty measurements in widely varying systems. Among these were measurements in the Tank Critical Assembly (TCA in Japan) and IPEN/MB-01 (Brazil), both with a thermal spectrum, two cores in Masurca (France) and three cores in the Fast Critical Assembly (FCA, Japan), all with fast spectra. The performance of the three libraries, in combination with MCNP6, is shown to be good. The results for the LEU-COMP-THERM category are on average very close to the benchmark value. Also for most other categories the results are satisfactory. Deviations from the benchmark values do occur in certain benchmark series, or in isolated cases within benchmark series. Such

  13. The Editor and Publisher as Public Official: The Ultimate Conflict of Interest.

    ERIC Educational Resources Information Center

    Sneed, Don

    A fifteen-item Likert scale and indepth personal interviews were used to collect data in a study that examined whether five individuals who held both the role of editor and public official were perceived as able to perform in a socially responsible manner as editors of their community newspapers in their estimation and in the estimation of a…

  14. A Coorientational Study of Food Public Relations Practitioners, Editors and Readers.

    ERIC Educational Resources Information Center

    Knodell, Joyce Elaine

    Survey data on newspaper food editors and newspaper readers were collected through a title-rating technique. Analysis of responses to 40 food titles and leads indicated three newspaper food-editor types: transitional, traditional, and "new guard." Food-page readers fell into two types: information oriented (nutritionists) and cooking…

  15. 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…

  16. 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…

  17. 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

  18. 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...)(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)...

  19. 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...)(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)...

  20. 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...)(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)...

  1. Editorial Page Editors and Endorsements: Chain-owned vs. Independent Newspapers.

    ERIC Educational Resources Information Center

    St. Dizier, Byron

    Questionnaires were sent to 114 of the 228 editorial page editors at newspapers in the United States with daily circulations greater than 50,000 for a study that compared (1) the editor-publisher relationship existing at chains to that found at independent papers, and (2) the 1984 presidential endorsements made by chains to those by independent…

  2. "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…

  3. 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...

  4. 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…

  5. Dr. Bruce Squires witnessed vast changes during tenure as CMAJ editor

    PubMed Central

    Sullivan, Patrick

    1996-01-01

    Dr. Bruce Squires retired in September after spending 10 years as editor of CMAJ. During his tenure the editor's responsibilities expanded greatly because of the CMA's foray into the publishing of medical books and additional journals and other publications. In this article, people who have worked with Squires reflect on his term with CMAJ. Imagesp570-a

  6. 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.

  7. Validation of MCNP6 Version 1.0 with the ENDF/B-VII.1 Cross Section Library for Uranium Metal, Oxide, and Solution Systems on the High Performance Computing Platform Moonlight

    SciTech Connect

    Chapman, Bryan Scott; MacQuigg, Michael Robert; Wysong, Andrew Russell

    2016-04-21

    In this document, the code MCNP is validated with ENDF/B-VII.1 cross section data under the purview of ANSI/ANS-8.24-2007, for use with uranium systems. MCNP is a computer code based on Monte Carlo transport methods. While MCNP has wide reading capability in nuclear transport simulation, this validation is limited to the functionality related to neutron transport and calculation of criticality parameters such as keff.

  8. SU-E-T-212: Comparison of TG-43 Dosimetric Parameters of Low and High Energy Brachytherapy Sources Obtained by MCNP Code Versions of 4C, X and 5

    SciTech Connect

    Zehtabian, M; Zaker, N; Sina, S; Meigooni, A Soleimani

    2015-06-15

    Purpose: Different versions of MCNP code are widely used for dosimetry purposes. The purpose of this study is to compare different versions of the MCNP codes in dosimetric evaluation of different brachytherapy sources. Methods: The TG-43 parameters such as dose rate constant, radial dose function, and anisotropy function of different brachytherapy sources, i.e. Pd-103, I-125, Ir-192, and Cs-137 were calculated in water phantom. The results obtained by three versions of Monte Carlo codes (MCNP4C, MCNPX, MCNP5) were compared for low and high energy brachytherapy sources. Then the cross section library of MCNP4C code was changed to ENDF/B-VI release 8 which is used in MCNP5 and MCNPX codes. Finally, the TG-43 parameters obtained using the MCNP4C-revised code, were compared with other codes. Results: The results of these investigations indicate that for high energy sources, the differences in TG-43 parameters between the codes are less than 1% for Ir-192 and less than 0.5% for Cs-137. However for low energy sources like I-125 and Pd-103, large discrepancies are observed in the g(r) values obtained by MCNP4C and the two other codes. The differences between g(r) values calculated using MCNP4C and MCNP5 at the distance of 6cm were found to be about 17% and 28% for I-125 and Pd-103 respectively. The results obtained with MCNP4C-revised and MCNPX were similar. However, the maximum difference between the results obtained with the MCNP5 and MCNP4C-revised codes was 2% at 6cm. Conclusion: The results indicate that using MCNP4C code for dosimetry of low energy brachytherapy sources can cause large errors in the results. Therefore it is recommended not to use this code for low energy sources, unless its cross section library is changed. Since the results obtained with MCNP4C-revised and MCNPX were similar, it is concluded that the difference between MCNP4C and MCNPX is their cross section libraries.

  9. 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

  10. A voxel-based mouse for internal dose calculations using Monte Carlo simulations (MCNP)

    NASA Astrophysics Data System (ADS)

    Bitar, A.; Lisbona, A.; Thedrez, P.; Sai Maurel, C.; LeForestier, D.; Barbet, J.; Bardies, M.

    2007-02-01

    Murine models are useful for targeted radiotherapy pre-clinical experiments. These models can help to assess the potential interest of new radiopharmaceuticals. In this study, we developed a voxel-based mouse for dosimetric estimates. A female nude mouse (30 g) was frozen and cut into slices. High-resolution digital photographs were taken directly on the frozen block after each section. Images were segmented manually. Monoenergetic photon or electron sources were simulated using the MCNP4c2 Monte Carlo code for each source organ, in order to give tables of S-factors (in Gy Bq-1 s-1) for all target organs. Results obtained from monoenergetic particles were then used to generate S-factors for several radionuclides of potential interest in targeted radiotherapy. Thirteen source and 25 target regions were considered in this study. For each source region, 16 photon and 16 electron energies were simulated. Absorbed fractions, specific absorbed fractions and S-factors were calculated for 16 radionuclides of interest for targeted radiotherapy. The results obtained generally agree well with data published previously. For electron energies ranging from 0.1 to 2.5 MeV, the self-absorbed fraction varies from 0.98 to 0.376 for the liver, and from 0.89 to 0.04 for the thyroid. Electrons cannot be considered as 'non-penetrating' radiation for energies above 0.5 MeV for mouse organs. This observation can be generalized to radionuclides: for example, the beta self-absorbed fraction for the thyroid was 0.616 for I-131; absorbed fractions for Y-90 for left kidney-to-left kidney and for left kidney-to-spleen were 0.486 and 0.058, respectively. Our voxel-based mouse allowed us to generate a dosimetric database for use in preclinical targeted radiotherapy experiments.

  11. MCNP Neutron Simulations: The Effectiveness of the University of Kentucky Accelerator Laboratory Pit

    NASA Astrophysics Data System (ADS)

    Jackson, Daniel; Nguyen, Thien An; Hicks, S. F.; Rice, Ben; Vanhoy, J. R.

    2015-10-01

    The design of the Van de Graaff Particle Accelerator complex at the University of Kentucky is marked by the unique addition of a pit in the main neutron scattering room underneath the neutron source and detection shielding assembly. This pit was constructed as a neutron trap in order to decrease the amount of neutron flux within the laboratory. Such a decrease of background neutron flux effectively reduces as much noise as possible in detection of neutrons scattering off of desired samples to be studied. This project uses the Monte-Carlo N-Particle Transport Code (MCNP) to model the structure of the accelerator complex, gas cell, and the detector's collimator and shielding apparatus to calculate the neutron flux in various sections of the laboratory. Simulations were completed with baseline runs of 107 neutrons of energies 4 MeV and 17 MeV, produced respectively by 3H(p,n)3He and 3H(d,n)4He source reactions. In addition, a comparison model of the complex with simply a floor and no pit was designed, and the respective neutron fluxes of both models were calculated and compared. The results of the simulations seem to affirm the validity of the pit design in significantly reducing the overall neutron flux throughout the accelerator complex, which could be used in future designs to increase the precision and reliability of data. This project was supported in part by the DOE NEUP Grant NU-12-KY-UK-0201-05 and the Donald A. Cowan Physics Institute at the University of Dallas.

  12. Testing actinide fission yield treatment in CINDER90 for use in MCNP6 burnup calculations

    SciTech Connect

    Fensin, Michael Lorne; Umbel, Marissa

    2015-09-18

    Most of the development of the MCNPX/6 burnup capability focused on features that were applied to the Boltzman transport or used to prepare coefficients for use in CINDER90, with little change to CINDER90 or the CINDER90 data. Though a scheme exists for best solving the coupled Boltzman and Bateman equations, the most significant approximation is that the employed nuclear data are correct and complete. Thus, the CINDER90 library file contains 60 different actinide fission yields encompassing 36 fissionable actinides (thermal, fast, high energy and spontaneous fission). Fission reaction data exists for more than 60 actinides and as a result, fission yield data must be approximated for actinides that do not possess fission yield information. Several types of approximations are used for estimating fission yields for actinides which do not possess explicit fission yield data. The objective of this study is to test whether or not certain approximations of fission yield selection have any impact on predictability of major actinides and fission products. Further we assess which other fission products, available in MCNP6 Tier 3, result in the largest difference in production. Because the CINDER90 library file is in ASCII format and therefore easily amendable, we assess reasons for choosing, as well as compare actinide and major fission product prediction for the H. B. Robinson benchmark for, three separate fission yield selection methods: (1) the current CINDER90 library file method (Base); (2) the element method (Element); and (3) the isobar method (Isobar). Results show that the three methods tested result in similar prediction of major actinides, Tc-99 and Cs-137; however, certain fission products resulted in significantly different production depending on the method of choice.

  13. Testing actinide fission yield treatment in CINDER90 for use in MCNP6 burnup calculations

    DOE PAGES

    Fensin, Michael Lorne; Umbel, Marissa

    2015-09-18

    Most of the development of the MCNPX/6 burnup capability focused on features that were applied to the Boltzman transport or used to prepare coefficients for use in CINDER90, with little change to CINDER90 or the CINDER90 data. Though a scheme exists for best solving the coupled Boltzman and Bateman equations, the most significant approximation is that the employed nuclear data are correct and complete. Thus, the CINDER90 library file contains 60 different actinide fission yields encompassing 36 fissionable actinides (thermal, fast, high energy and spontaneous fission). Fission reaction data exists for more than 60 actinides and as a result, fissionmore » yield data must be approximated for actinides that do not possess fission yield information. Several types of approximations are used for estimating fission yields for actinides which do not possess explicit fission yield data. The objective of this study is to test whether or not certain approximations of fission yield selection have any impact on predictability of major actinides and fission products. Further we assess which other fission products, available in MCNP6 Tier 3, result in the largest difference in production. Because the CINDER90 library file is in ASCII format and therefore easily amendable, we assess reasons for choosing, as well as compare actinide and major fission product prediction for the H. B. Robinson benchmark for, three separate fission yield selection methods: (1) the current CINDER90 library file method (Base); (2) the element method (Element); and (3) the isobar method (Isobar). Results show that the three methods tested result in similar prediction of major actinides, Tc-99 and Cs-137; however, certain fission products resulted in significantly different production depending on the method of choice.« less

  14. A calibration method for realistic neutron dosimetry in radiobiological experiments assisted by MCNP simulation

    PubMed Central

    Shahmohammadi Beni, Mehrdad; Krstic, Dragana; Nikezic, Dragoslav; Yu, Kwan Ngok

    2016-01-01

    Many studies on biological effects of neutrons involve dose responses of neutrons, which rely on accurately determined absorbed doses in the irradiated cells or living organisms. Absorbed doses are difficult to measure, and are commonly surrogated with doses measured using separate detectors. The present work describes the determination of doses absorbed in the cell layer underneath a medium column (DA) and the doses absorbed in an ionization chamber (DE) from neutrons through computer simulations using the MCNP-5 code, and the subsequent determination of the conversion coefficients R (= DA/DE). It was found that R in general decreased with increase in the medium thickness, which was due to elastic and inelastic scattering. For 2-MeV neutrons, conspicuous bulges in R values were observed at medium thicknesses of about 500, 1500, 2500 and 4000 μm, and these were attributed to carbon, oxygen and nitrogen nuclei, and were reflections of spikes in neutron interaction cross sections with these nuclei. For 0.1-MeV neutrons, no conspicuous bulges in R were observed (except one at ~2000 μm that was due to photon interactions), which was explained by the absence of prominent spikes in the interaction cross-sections with these nuclei for neutron energies <0.1 MeV. The ratio R could be increased by ~50% for small medium thickness if the incident neutron energy was reduced from 2 MeV to 0.1 MeV. As such, the absorbed doses in cells (DA) would vary with the incident neutron energies, even when the absorbed doses shown on the detector were the same. PMID:27380801

  15. 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

  16. 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)

  17. Thermal neutron self-shielding correction factors for large sample instrumental neutron activation analysis using the MCNP code

    NASA Astrophysics Data System (ADS)

    Tzika, F.; Stamatelatos, I. E.

    2004-01-01

    Thermal neutron self-shielding within large samples was studied using the Monte Carlo neutron transport code MCNP. The code enabled a three-dimensional modeling of the actual source and geometry configuration including reactor core, graphite pile and sample. Neutron flux self-shielding correction factors derived for a set of materials of interest for large sample neutron activation analysis are presented and evaluated. Simulations were experimentally verified by measurements performed using activation foils. The results of this study can be applied in order to determine neutron self-shielding factors of unknown samples from the thermal neutron fluxes measured at the surface of the sample.

  18. Tally modifying of MCNP and post processing of pile-up simulation with time convolution method in PGNAA

    NASA Astrophysics Data System (ADS)

    Asghar Mowlavi, Ali; Koohi-Fayegh, Rahim

    2005-11-01

    Time convolution method has been employed for pile-up simulation in prompt gamma neutron activation analysis with an Am-Be neutron source and a 137Cs gamma source. A TALLYX subroutine has been written to design a new tally in the MCNP code. This tally records gamma particle information for the detector cell into an output file to be processed later. The times at which the particles are emitted by the source have been randomly generated following an exponential decay time distribution. A time convolution program was written to process the data produced and simulate more realistic pile-up. This method can be applied in optimization studies.

  19. MCNP calculations for criticality-safety benchmarks with ENDF/B-V and ENDF/B-VI libraries

    SciTech Connect

    Iverson, J.L.; Mosteller, R.D.

    1995-07-01

    The MCNP Monte Carlo code, in conjunction with its continuous-energy ENDF/B-V and ENDF/B-VI cross-section libraries, has been benchmarked against results from 27 different critical experiments. The predicted values of k{sub eff} are in excellent agreement with the benchmarks, except for the ENDF/B-V results for solutions of plutonium nitrate and, to a lesser degree, for the ENDF/B-V and ENDF/B-VI results for a bare sphere of {sup 233}U.

  20. A comparison of results from LANCER02 and MCNP on a series of two-dimensional multiple BWR bundle configurations

    SciTech Connect

    Knott, D.; Wehlage, E.; Sawada, A.; Zino, J.

    2006-07-01

    This paper discusses recent extensions to the LANCER02 lattice physics code that allow for the analysis of multiple bundles lying along a two-dimensional plane of a reactor core. The paper presents results from LANCER02 on a study consisting of analyses on single assemblies, 2 x 2 arrays of bundles, and 4 x 4 arrays of bundles at different operating conditions. LANCER02 eigenvalues and rod-by-rod fission rates are compared against results from corresponding MCNP analyses. Results indicate that the LANCER02 multi-bundle modelling option is equivalent in accuracy to its single-assembly capability. (authors)

  1. Calculation of thermal neutron self-shielding correction factors for aqueous bulk sample prompt gamma neutron activation analysis using the MCNP code

    NASA Astrophysics Data System (ADS)

    Nasrabadi, M. N.; Jalali, M.; Mohammadi, A.

    2007-10-01

    In this work thermal neutron self-shielding in aqueous bulk samples containing neutron absorbing materials is studied using bulk sample prompt gamma neutron activation analysis (BSPGNAA) with the MCNP code. The code was used to perform three dimensional simulations of a neutron source, neutron detector and sample of various material compositions. The MCNP model was validated against experimental measurements of the neutron flux performed using a BF 3 detector. Simulations were performed to predict thermal neutron self-shielding in aqueous bulk samples containing neutron absorbing solutes. In practice, the MCNP calculations are combined with experimental measurements of the relative thermal neutron flux over the sample's surface, with respect to a reference water sample, to derive the thermal neutron self-shielding within the sample. The proposed methodology can be used for the determination of the elemental concentration of unknown aqueous samples by BSPGNAA where knowledge of the average thermal neutron flux within the sample volume is required.

  2. Element analysis and calculation of the attenuation coefficients for gold, bronze and water matrixes using MCNP, WinXCom and experimental data

    NASA Astrophysics Data System (ADS)

    Esfandiari, M.; Shirmardi, S. P.; Medhat, M. E.

    2014-06-01

    In this study, element analysis and the mass attenuation coefficient for matrixes of gold, bronze and water with various impurities and the concentrations of heavy metals (Cu, Mn, Pb and Zn) are evaluated and calculated by the MCNP simulation code for photons emitted from Barium-133, Americium-241 and sources with energies between 1 and 100 keV. The MCNP data are compared with the experimental data and WinXCom code simulated results by Medhat. The results showed that the obtained results of bronze and gold matrix are in good agreement with the other methods for energies above 40 and 60 keV, respectively. However for water matrixes with various impurities, there is a good agreement between the three methods MCNP, WinXCom and the experimental one in low and high energies.

  3. 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.

  4. 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.

  5. Writing Science Effectively: Biology and English Students in an Author-Editor Relationship.

    ERIC Educational Resources Information Center

    Kokkala, Irene; Gessell, Donna A.

    2003-01-01

    Reports on the design of a collaborative learning community linking students in biology and English courses in author-editor relationships. Delineates the steps of the project and provides sample evaluations for both groups. (Contains 19 references.) (DDR)

  6. Issues in Communication Education: An Interview with Joe Ayers (Editor 1999-2002).

    ERIC Educational Resources Information Center

    Crandall, Heather; Hazel, Michael

    2002-01-01

    Presents an interview with Joe Ayres, editor of this journal from 1999 to 2002. Addresses issues such as curriculum content, competencies for undergraduate students, graduate students, student retention, and the role of mentoring in higher education. (SG)

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

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... editor and chief engineer. The 13(b)(9) exemption, as was made clear during the debate on the amendment... television stations. It is known at the time of such debate that these stations employ only a small number...

  8. Comparison of ENDF/B-VII.1 and ENDF/B-VII.0 Results for the Expanded Criticality Validation Suite for MCNP and for Selected Additional Criticality Benchmarks

    NASA Astrophysics Data System (ADS)

    Mosteller, R.

    2014-04-01

    Results obtained with the MCNP5 Monte Carlo code and the ENDF/B-VII.1 and ENDF/B-VII.0 nuclear data libraries have been compared for the 119 benchmarks in the expanded criticality validation suite for MCNP and for 23 additional benchmarks. ENDF/B-VII.1 was found to produce improvements relative to ENDF/B-VII.0 for benchmarks that contain significant amounts of tungsten, zirconium, cadmium, or beryllium, although the results for the benchmarks with beryllium suggest that further improvement still may be needed. In addition, a number of deficiencies previously identified for ENDF/B-VII.0 still remain in ENDF/B-VII.1.

  9. Special Article: Ronald D. Miller: tribute to a past editor-in-chief.

    PubMed

    Tuman, Kenneth J

    2012-12-01

    For anesthesiologists around the world who have practiced or trained in the past 4 decades, the name Ronald Miller, MD, has been synonymous with a commitment to excellence that has been evident in all aspects of his remarkable career as a distinguished clinician-scientist, editor, writer, and educator. Dr. Miller's contributions as Editor-in-Chief of Anesthesia & Analgesia (1991-2006) have stimulated this salutation of his career and of his influence on transforming the Journal.

  10. Exploring why and how journal editors retract articles: findings from a qualitative study.

    PubMed

    Williams, Peter; Wager, Elizabeth

    2013-03-01

    Editors have a responsibility to retract seriously flawed articles from their journals. However, there appears to be little consistency in journals' policies or procedures for this. In a qualitative study, we therefore interviewed editors of science journals using semi-structured interviews to investigate their experience of retracting articles. We identified potential barriers to retraction, difficulties in the process and also sources of support and encouragement. Our findings have been used as the basis for guidelines developed by the Committee on Publication Ethics.

  11. 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

  12. Organ dose conversion coefficients based on a voxel mouse model and MCNP code for external photon irradiation.

    PubMed

    Zhang, Xiaomin; Xie, Xiangdong; Cheng, Jie; Ning, Jing; Yuan, Yong; Pan, Jie; Yang, Guoshan

    2012-01-01

    A set of conversion coefficients from kerma free-in-air to the organ absorbed dose for external photon beams from 10 keV to 10 MeV are presented based on a newly developed voxel mouse model, for the purpose of radiation effect evaluation. The voxel mouse model was developed from colour images of successive cryosections of a normal nude male mouse, in which 14 organs or tissues were segmented manually and filled with different colours, while each colour was tagged by a specific ID number for implementation of mouse model in Monte Carlo N-particle code (MCNP). Monte Carlo simulation with MCNP was carried out to obtain organ dose conversion coefficients for 22 external monoenergetic photon beams between 10 keV and 10 MeV under five different irradiation geometries conditions (left lateral, right lateral, dorsal-ventral, ventral-dorsal, and isotropic). Organ dose conversion coefficients were presented in tables and compared with the published data based on a rat model to investigate the effect of body size and weight on the organ dose. The calculated and comparison results show that the organ dose conversion coefficients varying the photon energy exhibits similar trend for most organs except for the bone and skin, and the organ dose is sensitive to body size and weight at a photon energy approximately <0.1 MeV.

  13. SMITHERS: An object-oriented modular mapping methodology for MCNP-based neutronic–thermal hydraulic multiphysics

    SciTech Connect

    Richard, Joshua; Galloway, Jack; Fensin, Michael; Trellue, Holly

    2015-04-04

    A novel object-oriented modular mapping methodology for externally coupled neutronics–thermal hydraulics multiphysics simulations was developed. The Simulator using MCNP with Integrated Thermal-Hydraulics for Exploratory Reactor Studies (SMITHERS) code performs on-the-fly mapping of material-wise power distribution tallies implemented by MCNP-based neutron transport/depletion solvers for use in estimating coolant temperature and density distributions with a separate thermal-hydraulic solver. The key development of SMITHERS is that it reconstructs the hierarchical geometry structure of the material-wise power generation tallies from the depletion solver automatically, with only a modicum of additional information required from the user. In addition, it performs the basis mapping from the combinatorial geometry of the depletion solver to the required geometry of the thermal-hydraulic solver in a generalizable manner, such that it can transparently accommodate varying levels of thermal-hydraulic solver geometric fidelity, from the nodal geometry of multi-channel analysis solvers to the pin-cell level of discretization for sub-channel analysis solvers.

  14. SMITHERS: An object-oriented modular mapping methodology for MCNP-based neutronic–thermal hydraulic multiphysics

    DOE PAGES

    Richard, Joshua; Galloway, Jack; Fensin, Michael; ...

    2015-04-04

    A novel object-oriented modular mapping methodology for externally coupled neutronics–thermal hydraulics multiphysics simulations was developed. The Simulator using MCNP with Integrated Thermal-Hydraulics for Exploratory Reactor Studies (SMITHERS) code performs on-the-fly mapping of material-wise power distribution tallies implemented by MCNP-based neutron transport/depletion solvers for use in estimating coolant temperature and density distributions with a separate thermal-hydraulic solver. The key development of SMITHERS is that it reconstructs the hierarchical geometry structure of the material-wise power generation tallies from the depletion solver automatically, with only a modicum of additional information required from the user. In addition, it performs the basis mapping from themore » combinatorial geometry of the depletion solver to the required geometry of the thermal-hydraulic solver in a generalizable manner, such that it can transparently accommodate varying levels of thermal-hydraulic solver geometric fidelity, from the nodal geometry of multi-channel analysis solvers to the pin-cell level of discretization for sub-channel analysis solvers.« less

  15. Varian 2100C/D Clinac 18 MV photon phase space file characterization and modeling by using MCNP Code

    NASA Astrophysics Data System (ADS)

    Ezzati, Ahad Ollah

    2015-07-01

    Multiple points and a spatial mesh based surface source model (MPSMBSS) was generated for 18MV Varian 2100 C/D Clinac phase space file (PSF) and implemented in MCNP code. The generated source model (SM) was benchmarked against PSF and measurements. PDDs and profiles were calculated using the SM and original PSF for different field sizes from 5 × 5 to 20 × 20 cm2. Agreement was within 2% of the maximum dose at 100cm SSD for beam profiles at the depths of 4cm and 15cm with respect to the original PSF. Differences between measured and calculated points were less than 2% of the maximum dose or 2mm distance to agreement (DTA) at 100 cm SSD. Thus it can be concluded that the modified MCNP code can be used for radiotherapy calculations including multiple source model (MSM) and using the source biasing capability of MPSMBSS can increase the simulation speed up to 3600 for field sizes smaller than 5 × 5 cm2.

  16. A MCNP-based calibration method and a voxel phantom for in vivo monitoring of 241Am in skull

    NASA Astrophysics Data System (ADS)

    Moraleda, M.; Gómez-Ros, J. M.; López, M. A.; Navarro, T.; Navarro, J. F.

    2004-07-01

    Whole body counter (WBC) facilities are currently used for assessment of internal radionuclide body burdens by directly measuring the radiation emitted from the body. Previous calibration of the detection devices requires the use of specific anthropomorphic phantoms. This paper describes the MCNP-based Monte Carlo technique developed for calibration of the germanium detectors (Canberra LE Ge) used in the CIEMAT WBC for in vivo measurements of 241Am in skull. The proposed method can also be applied for in vivo counting of different radionuclides distributed in other anatomical regions as well as for other detectors. A computer software was developed to automatically generate the input files for the MCNP code starting from any segmented human anatomy data. A specific model of a human head for the assessment of 241Am was built based on the tomographic phantom VOXELMAN of Yale University. The germanium detectors were carefully modelled from data provided by the manufacturer. This numerical technique has been applied to investigate the best counting geometry and the uncertainty due to improper positioning of the detectors.

  17. [Tabular excel editor for analysis of aligned nucleotide sequences].

    PubMed

    Demkin, V V

    2010-01-01

    Excel platform was used for transition of results of multiple aligned nucleotide sequences obtained using the BLAST network service to the form appropriate for visual analysis and editing. Two macros operators for MS Excel 2007 were constructed. The array of aligned sequences transformed into Excel table and processed using macros operators is more appropriate for analysis than initial html data.

  18. 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

  19. 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

  20. 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

  1. SU-E-T-521: Investigation of the Uncertainties Involved in Secondary Neutron/gamma Production in Geant4/MCNP6 Monte Carlo Codes for Proton Therapy Application

    SciTech Connect

    Mirzakhanian, L; Enger, S; Giusti, V

    2015-06-15

    Purpose: A major concern in proton therapy is the production of secondary neutrons causing secondary cancers, especially in young adults and children. Most utilized Monte Carlo codes in proton therapy are Geant4 and MCNP. However, the default versions of Geant4 and MCNP6 do not have suitable cross sections or physical models to properly handle secondary particle production in proton energy ranges used for therapy. In this study, default versions of Geant4 and MCNP6 were modified to better handle production of secondaries by adding the TENDL-2012 cross-section library. Methods: In-water proton depth-dose was measured at the “The Svedberg Laboratory” in Uppsala (Sweden). The proton beam was mono-energetic with mean energy of 178.25±0.2 MeV. The measurement set-up was simulated by Geant4 version 10.00 (default and modified version) and MCNP6. Proton depth-dose, primary and secondary particle fluence and neutron equivalent dose were calculated. In case of Geant4, the secondary particle fluence was filtered by all the physics processes to identify the main process responsible for the difference between the default and modified version. Results: The proton depth-dose curves and primary proton fluence show a good agreement between both Geant4 versions and MCNP6. With respect to the modified version, default Geant4 underestimates the production of secondary neutrons while overestimates that of gammas. The “ProtonInElastic” process was identified as the main responsible process for the difference between the two versions. MCNP6 shows higher neutron production and lower gamma production than both Geant4 versions. Conclusion: Despite the good agreement on the proton depth dose curve and primary proton fluence, there is a significant discrepancy on secondary neutron production between MCNP6 and both versions of Geant4. Further studies are thus in order to find the possible cause of this discrepancy or more accurate cross-sections/models to handle the nuclear

  2. Visual signatures in video visualization.

    PubMed

    Chen, Min; Botchen, Ralf P; Hashim, Rudy R; Weiskopf, Daniel; Ertl, Thomas; Thornton, Ian M

    2006-01-01

    Video visualization is a computation process that extracts meaningful information from original video data sets and conveys the extracted information to users in appropriate visual representations. This paper presents a broad treatment of the subject, following a typical research pipeline involving concept formulation, system development, a path-finding user study, and a field trial with real application data. In particular, we have conducted a fundamental study on the visualization of motion events in videos. We have, for the first time, deployed flow visualization techniques in video visualization. We have compared the effectiveness of different abstract visual representations of videos. We have conducted a user study to examine whether users are able to learn to recognize visual signatures of motions, and to assist in the evaluation of different visualization techniques. We have applied our understanding and the developed techniques to a set of application video clips. Our study has demonstrated that video visualization is both technically feasible and cost-effective. It has provided the first set of evidence confirming that ordinary users can be accustomed to the visual features depicted in video visualizations, and can learn to recognize visual signatures of a variety of motion events.

  3. 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…

  4. G. K. Batchelor. Founding editor of the Journal of Fluid Mechanics

    NASA Astrophysics Data System (ADS)

    Crighton, D. G.

    1999-05-01

    Although developments in fluid mechanics continue at a heady pace, and are reported in JFM at about 800 pages per month, things in the editorial management of JFM change only slowly. There is a continuity among the JFM Editorial Team and among the policies they espouse and implement that appears to be appreciated by the fluid mechanics community. A major change has, however, occurred from January 1999, in that George Batchelor has, after 43 years as Editor, stepped down from the day-to-day handling of papers and from the formulation of policies and practices, and allowed himself to be named on our masthead as Founding Editor. I say ‘allowed’ because George's initial wish was not to be so named, feeling that this might be seen as an immodest and presumptuous title. But Founding Editor is exactly what George was and is. He launched JFM in May 1956, having persuaded Taylor & Francis to be the publisher and printer, and having enlisted the help of G. F. Carrier, W. C. Griffith and M. J. Lighthill as Associate Editors, and T. Brooke Benjamin and I. Proudman as Assistant Editors. Then, as now, all members of the JFM Editorial Team were to work autonomously in the handling of papers, with complete delegated authority and similar workloads, but all following similar procedures and with similar philosophies, and all under the watchful eye of G. K. B.

  5. [The relevance of the International Committee of Medical Journal Editors (ICMJE) for medical publishing and research].

    PubMed

    Reyes, Humberto B

    2014-01-01

    The International Committee of Medical Journal Editors is a leading independent institution providing guidance for the report of biomedical research and health related topics in medical journals. Established in 1978, it is currently constituted by editors of fourteen general medical journals from different countries, plus one representative for the US National Library of Medicine and one representative for the World Association of Biomedical Journal Editors. Since 1978 the Committee provides a document, originally named "Uniform Requirements…", "to help authors, editors, and others involved in peer review and biomedical publishing create and distribute accurate, clear, unbiased medical journal articles". This document has been updated several times and the last version was released in August 2013, now renamed "Recommendations for the Conduct, Reporting, Editing, and Publication of Scholarly Work in Medical Journals", available in www.icmje.org and citable as "ICMJE Recommendations". A vast proportion of medical journals, worldwide, have adopted these recommendations as rules. The ICMJE discusses and provides guidance on several relevant aspects including criteria on authorship, peer review, scientific misconduct, conflicts of interest, clinical trials registration, good editorial practices, the relations between editors and journal owners, the protection of individuals subject to medical research, the solvency of electronic publications, among others. The 2013 ICMJE Annual Meeting took place in Santiago, Chile, in November 4 and 5. The photograph shows attendants to the final session.

  6. 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

  7. Monte Carlo Simulation of Electron Beams for Radiotherapy - EGS4, MCNP4b and GEANT3 Intercomparison

    NASA Astrophysics Data System (ADS)

    Trindade, A.; Rodrigues, P.; Alves, C.; Chaves, A.; Lopes, M. C.; Oliveira, C.; Peralta, L.

    In medical radiation physics, an increasing number of Monte Carlo codes are being used, which requires intercomparison between them to evaluated the accuracy of the simulated results against benchmark experiments. The Monte Carlo code EGS4, commonly used to simulate electron beams from medical linear accelerators, was compared with GEANT3 and MCNP4b. Intercomparison of electron energy spectra, angular and spatial distribution were carried out for the Siemens KD2 linear accelerator, at beam energies of 10 and 15 MeV for a field size of 10x10 cm2. Indirect validation was performed against electron depth doses curves and beam profiles measured in a MP3-PTW water phantom using a Markus planar chamber. Monte Carlo isodose lines were reconstructed and compared to those from commercial treatment planning systems (TPS's) and with experimental data.

  8. Benchmark of Atucha-2 PHWR RELAP5-3D control rod model by Monte Carlo MCNP5 core calculation

    SciTech Connect

    Pecchia, M.; D'Auria, F.; Mazzantini, O.

    2012-07-01

    Atucha-2 is a Siemens-designed PHWR reactor under construction in the Republic of Argentina. Its geometrical complexity and peculiarities require the adoption of advanced Monte Carlo codes for performing realistic neutronic simulations. Therefore core models of Atucha-2 PHWR were developed using MCNP5. In this work a methodology was set up to collect the flux in the hexagonal mesh by which the Atucha-2 core is represented. The scope of this activity is to evaluate the effect of obliquely inserted control rod on neutron flux in order to validate the RELAP5-3D{sup C}/NESTLE three dimensional neutron kinetic coupled thermal-hydraulic model, applied by GRNSPG/UNIPI for performing selected transients of Chapter 15 FSAR of Atucha-2. (authors)

  9. Evaluation of a 50-MV Photon Therapy Beam from a Racetrack Microtron Using MCNP4B Monte Carlo Code

    NASA Astrophysics Data System (ADS)

    Gudowska, I.; Sorcini, B.; Svensson, R.

    High energy photon therapy beam from the 50 MV racetrack microtron has been evaluated using the Monte Carlo code MCNP4B. The spatial and energy distribution of photons, radial and depth dose distributions in the phantom are calculated for the stationary and scanned photon beams from different targets. The calculated dose distributions are compared to the experimental data using a silicon diode detector. Measured and calculated depth-dose distributions are in fairly good agreement, within 2-3% for the positions in the range 2-30 cm in the phantom, whereas the larger discrepancies up to 10% are observed in the dose build-up region. For the stationary beams the differences in the calculated and measured radial dose distributions axe about 2-10%.

  10. MCNP modelling of vaginal and uterine applicators used in intracavitary brachytherapy and comparison with radiochromic film measurements

    NASA Astrophysics Data System (ADS)

    Ceccolini, E.; Gerardy, I.; Ródenas, J.; van Dycke, M.; Gallardo, S.; Mostacci, D.

    Brachytherapy is an advanced cancer treatment that is minimally invasive, minimising radiation exposure to the surrounding healthy tissues. Microselectron© Nucletron devices with 192Ir source can be used for gynaecological brachytherapy, in patients with vaginal or uterine cancer. Measurements of isodose curves have been performed in a PMMA phantom and compared with Monte Carlo calculations and TPS (Plato software of Nucletron BPS 14.2) evaluation. The isodose measurements have been performed with radiochromic films (Gafchromic EBT©). The dose matrix has been obtained after digitalisation and use of a dose calibration curve obtained with a 6 MV photon beam provided by a medical linear accelerator. A comparison between the calculated and the measured matrix has been performed. The calculated dose matrix is obtained with a simulation using the MCNP5 Monte Carlo code (F4MESH tally).

  11. Photon attenuation coefficients of Heavy-Metal Oxide glasses by MCNP code, XCOM program and experimental data: A comparison study

    NASA Astrophysics Data System (ADS)

    El-Khayatt, A. M.; Ali, A. M.; Singh, Vishwanath P.

    2014-01-01

    The mass attenuation coefficients, μ/ρ, total interaction cross-section, σt, and mean free path (MFP) of some Heavy Metal Oxides (HMO) glasses, with potential applications as gamma ray shielding materials, have been investigated using the MCNP-4C code. Appreciable variations are noted for all parameters by changing the photon energy and the chemical composition of HMO glasses. The numerical simulations parameters are compared with experimental data wherever possible. Comparisons are also made with predictions from the XCOM program in the energy region from 1 keV to 100 MeV. Good agreement noticed indicates that the chosen Monte Carlo method may be employed to make additional calculations on the photon attenuation characteristics of different glass systems, a capability particularly useful in cases where no analogous experimental data exist.

  12. Calibration with MCNP of NaI detector for the determination of natural radioactivity levels in the field.

    PubMed

    Cinelli, Giorgia; Tositti, Laura; Mostacci, Domiziano; Baré, Jonathan

    2016-05-01

    In view of assessing natural radioactivity with on-site quantitative gamma spectrometry, efficiency calibration of NaI(Tl) detectors is investigated. A calibration based on Monte Carlo simulation of detector response is proposed, to render reliable quantitative analysis practicable in field campaigns. The method is developed with reference to contact geometry, in which measurements are taken placing the NaI(Tl) probe directly against the solid source to be analyzed. The Monte Carlo code used for the simulations was MCNP. Experimental verification of the calibration goodness is obtained by comparison with appropriate standards, as reported. On-site measurements yield a quick quantitative assessment of natural radioactivity levels present ((40)K, (238)U and (232)Th). On-site gamma spectrometry can prove particularly useful insofar as it provides information on materials from which samples cannot be taken.

  13. 3D element imaging using NSECT for the detection of renal cancer: a simulation study in MCNP

    NASA Astrophysics Data System (ADS)

    Viana, R. S.; Agasthya, G. A.; Yoriyaz, H.; Kapadia, A. J.

    2013-09-01

    This work describes a simulation study investigating the application of neutron stimulated emission computed tomography (NSECT) for noninvasive 3D imaging of renal cancer in vivo. Using MCNP5 simulations, we describe a method of diagnosing renal cancer in the body by mapping the 3D distribution of elements present in tumors using the NSECT technique. A human phantom containing the kidneys and other major organs was modeled in MCNP5. The element composition of each organ was based on values reported in literature. The two kidneys were modeled to contain elements reported in renal cell carcinoma (RCC) and healthy kidney tissue. Simulated NSECT scans were executed to determine the 3D element distribution of the phantom body. Elements specific to RCC and healthy kidney tissue were then analyzed to identify the locations of the diseased and healthy kidneys and generate tomographic images of the tumor. The extent of the RCC lesion inside the kidney was determined using 3D volume rendering. A similar procedure was used to generate images of each individual organ in the body. Six isotopes were studied in this work—32S, 12C, 23Na, 14N, 31P and 39K. The results demonstrated that through a single NSECT scan performed in vivo, it is possible to identify the location of the kidneys and other organs within the body, determine the extent of the tumor within the organ, and to quantify the differences between cancer and healthy tissue-related isotopes with p ≤ 0.05. All of the images demonstrated appropriate concentration changes between the organs, with some discrepancy observed in 31P, 39K and 23Na. The discrepancies were likely due to the low concentration of the elements in the tissue that were below the current detection sensitivity of the NSECT technique.

  14. High-fidelity MCNP modeling of a D-T neutron generator for active interrogation of special nuclear material

    NASA Astrophysics Data System (ADS)

    Katalenich, Jeff; Flaska, Marek; Pozzi, Sara A.; Hartman, Michael R.

    2011-10-01

    Fast and robust methods for interrogation of special nuclear material (SNM) are of interest to many agencies and institutions in the United States. It is well known that passive interrogation methods are typically sufficient for plutonium identification because of a relatively high neutron production rate from 240Pu [1]. On the other hand, identification of shielded uranium requires active methods using neutron or photon sources [2]. Deuterium-deuterium (2.45 MeV) and deuterium-tritium (14.1 MeV) neutron-generator sources have been previously tested and proven to be relatively reliable instruments for active interrogation of nuclear materials [3,4]. In addition, the newest generators of this type are small enough for applications requiring portable interrogation systems. Active interrogation techniques using high-energy neutrons are being investigated as a method to detect hidden SNM in shielded containers [4,5]. Due to the thickness of some containers, penetrating radiation such as high-energy neutrons can provide a potential means of probing shielded SNM. In an effort to develop the capability to assess the signal seen from various forms of shielded nuclear materials, the University of Michigan Neutron Science Laboratory's D-T neutron generator and its shielding were accurately modeled in MCNP. The generator, while operating at nominal power, produces approximately 1×10 10 neutrons/s, a source intensity which requires a large amount of shielding to minimize the dose rates around the generator. For this reason, the existing shielding completely encompasses the generator and does not include beam ports. Therefore, several MCNP simulations were performed to estimate the yield of uncollided 14.1-MeV neutrons from the generator for active interrogation experiments. Beam port diameters of 5, 10, 15, 20, and 25 cm were modeled to assess the resulting neutron fluxes. The neutron flux outside the beam ports was estimated to be approximately 2×10 4 n/cm 2 s.

  15. 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.

  16. 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.

  17. A Java chemical structure editor supporting the Modular Chemical Descriptor Language (MCDL).

    PubMed

    Trepalin, Sergei V; Yarkov, Alexander V; Pletnev, Igor V; Gakh, Andrei A

    2006-03-29

    A compact Modular Chemical Descriptor Language (MCDL) chemical structure editor (Java applet) is described. The small size (approximately 200 KB) of the applet allows its use to display and edit chemical structures in various Internet applications. The editor supports the MCDL format, in which structures are presented in compact canonical form and is capable of restoring bond orders as well as of managing atom and bond drawing overlap. A small database of cage and large cyclic fragment is used for optimal representation of difficult-to-draw molecules. The improved algorithm of the structure diagram generation can be used for other chemical notations that lack atomic coordinates (SMILES, InChI).

  18. 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.

  19. Magazine or journal--what is the difference? The role of the monitoring editor.

    PubMed

    Bretscher, Anthony

    2013-04-01

    Scientific communication, career advancement, and funding decisions are all dependent on research publications. The way manuscripts are handled by high-visibility, professionally edited magazines differs from the way academic journals evaluate manuscripts, using active scientists as monitoring editors. In this essay, I discuss the benefits that come with the involvement of active scientists. I enumerate the decisions a monitoring editor has to make, and how he or she goes about making them. Finally, I indicate ways in which authors can help to make the process a smoother and more positive experience.

  20. 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…

  1. Visual Knowledge.

    ERIC Educational Resources Information Center

    Chipman, Susan F.

    Visual knowledge is an enormously important part of our total knowledge. The psychological study of learning and knowledge has focused almost exclusively on verbal materials. Today, the advance of technology is making the use of visual communication increasingly feasible and popular. However, this enthusiasm involves the illusion that visual…

  2. Visual Theorems.

    ERIC Educational Resources Information Center

    Davis, Philip J.

    1993-01-01

    Argues for a mathematics education that interprets the word "theorem" in a sense that is wide enough to include the visual aspects of mathematical intuition and reasoning. Defines the term "visual theorems" and illustrates the concept using the Marigold of Theodorus. (Author/MDH)

  3. 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…

  4. 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

  5. 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

  6. 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…

  7. 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,…

  8. 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.

  9. Parting messages from current and former editors of the Journal of Andrology.

    PubMed

    Bartke, Andrzej; Orgebin-Crist, Marie-Claire; Desjardins, Claude; Lewis, Ron; Tindall, Don; Hamilton, David W; Pryor, Jon L; Schlegel, Peter N; Hardy, Matthew P; Burnett, Arthur L Bud; Darney, Sally P; Sandlow, Jay

    2012-01-01

    The proposal to produce this final commemorative issue for the Journal of Andrology arose during our regular discussions as current editors soon after it was announced that the Journal would complete its own life course and merge into a new publication (to be named Andrology) with the International Journal of Andrology. We considered the momentous occasion to be one that should be celebrated with an enduring tribute in recognition of the Journal's exceptional 33-year existence. Among the various contributions sought for inclusion in this issue, we envisioned an article assembling collected short essays from all living former editors drawing on notable events and highlights, if not less well-known challenges and successes arising during their editorship eras. We thought that any such production of musings, viewpoints, and most of all words of wisdom from those who have had major roles in the direction and accomplishments of the Journal would offer an illuminating read for the society's members and friends and provide all readers another venue to share in and enjoy the Journal's great history. We are enthralled to have gathered these collections, all personal compositions of the former editors-in-chief, and for their effort that has helped us complete this special endeavor we express to them our tremendous gratitude. Serving as the Journal's last editors, we are also grateful to contribute our essay at the very end as part of this joyous chronicle.

  10. Book Selection Criteria of Children's Book Editors and Elementary Classroom Teachers.

    ERIC Educational Resources Information Center

    McKeon, Helen M.

    This paper describes a study of the criteria children's book editors and elementary classroom teachers use to select fiction books for children in grades four, five, and six. A questionnaire was sent to all members of the Children's Book Council and to elementary classroom teachers of grades four, five, and six in each elementary school in…

  11. 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.

  12. 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…

  13. 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...

  14. 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,…

  15. 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…

  16. Interview with the editor: David L. Turpin by Robert P. Scholz.

    PubMed

    Turpin, David L

    2010-04-01

    David L. Turpin has worked on dental journals for over 30 years--from his early days on the Pacific Coast Society of Orthodontists Bulletin, to the Angle Orthodontist, and to the American Journal of Orthodontics and Dentofacial Orthopedics. He will retire as editor-in-chief of the American Journal of Orthodontics and Dentofacial Orthopedics at the end of 2010.

  17. Advancing the Profession through Journals: The Editor-Author-Profession Partnership [in HRD].

    ERIC Educational Resources Information Center

    1995

    These three papers are from a symposium on professional journals that was facilitated by Wim J. Nijhoff at the 1995 Academy of Human Resource Development (HRD) conference. "Advancing the Profession through Journals: The Editor-Author-Profession Partnership" (Gary N. McLean) describes the purpose and operation of the "Human Resource…

  18. 29 CFR 793.11 - Combination announcer, news editor and chief engineer.

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... television stations. It is known at the time of such debate that these stations employ only a small number of employees and that, at times, an employee of such a station may perform a variety of duties in connection... editor and chief engineer. The 13(b)(9) exemption, as was made clear during the debate on the...

  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. Evaluation using m.c.n.p. code of the bremsstrahlung energy spectrum produced by interactions between structural materials and accelerated electrons

    NASA Astrophysics Data System (ADS)

    Calderaro, Elio

    2004-09-01

    In order to design the biological shield of industrial accelerator plants, it is needed to have a good knowledge of the bremsstrahlung energy spectrum and the intensity of the bremsstrahlung produced by electron interactions with both products (usually water equivalent) and structural materials such as concrete, iron, aluminium. Using the MCNP code, a normalized bremsstrahlung energy spectrum was obtained for materials with average atomic number lower than or equal to 13 and irradiated with 5 and 10 Mev electrons, respectively; multiplying the spectrum by suitable coefficients, it was possible to obtain the real spectrum for materials such as water, concrete, aluminium and iron. The MCNP results have been obtained with relative error less than 2%.

  1. Guidelines, editors, pharma and the biological paradigm shift.

    PubMed

    Singh, Ajai R; Singh, Shakuntala A

    2007-01-01

    relatively recent survey of 2002, it was found that about 60% of 192 authors of clinical practice guidelines reported they had financial connections with the companies whose drugs were under consideration. There is a strong case for making CPGs based not just on effectivity but cost effectivity. The various ramifications of this need to be spelt out. Work of bodies like the Appraisal of Guidelines Research and Evaluation (AGREE) Collaboration and Guidelines Advisory Committee (GAC) are also worth a close look.Even the actions of Foundations that work for disease amelioration have come under scrutiny. The process of setting up 'Best Practices' Guidelines for interactions between the pharmaceutical industry and clinicians has already begun and can have important consequences for patient care. Similarly, Good Publication Practice (GPP) for pharmaceutical companies have also been set up aimed at improving the behaviour of drug companies while reporting drug trialsThe rapidly increasing trend toward influence and control by industry has become a concern for many. It is of such importance that the Association of American Medical Colleges has issued two relatively new documents - one, in 2001, on how to deal with individual conflicts of interest; and the other, in 2002, on how to deal with institutional conflicts of interest in the conduct of clinical research. Academic Medical Centers (AMCs), as also medical education and research institutions at other places, have to adopt means that minimize their conflicts of interest.Both medical associations and research journal editors are getting concerned with individual and institutional conflicts of interest in the conduct of clinical research and documents are now available which address these issues. The 2001 ICMJE revision calls for full disclosure of the sponsor's role in research, as well as assurance that the investigators are independent of the sponsor, are fully accountable for the design and conduct of the trial, have

  2. Verification and Validation of Monte Carlo n-Particle Code 6 (MCNP6) with Neutron Protection Factor Measurements of an Iron Box

    DTIC Science & Technology

    2014-03-27

    of the vacuum-filled aluminum cylinder which forms a part of the DD108 accelerator head. The isotropic source is centered therein. The scintillator...radiation transport codes, as the excerpt below explains. 26 The shield chosen for the study was an iron box with liners of various thicknesses of...Model Design Within MCNP6, the scintillator crystal was modeled as a 4x4 mm 2 right circular cylinder (RCC) suspended in vacuum inside a 14x16 mm 2

  3. Comparison of the 3-D Deterministic Neutron Transport Code Attila® To Measure Data, MCNP And MCNPX For The Advanced Test Reactor

    SciTech Connect

    D. Scott Lucas; D. S. Lucas

    2005-09-01

    An LDRD (Laboratory Directed Research and Development) project is underway at the Idaho National Laboratory (INL) to apply the three-dimensional multi-group deterministic neutron transport code (Attila®) to criticality, flux and depletion calculations of the Advanced Test Reactor (ATR). This paper discusses the development of Attila models for ATR, capabilities of Attila, the generation and use of different cross-section libraries, and comparisons to ATR data, MCNP, MCNPX and future applications.

  4. Production of energetic light fragments in extensions of the CEM and LAQGSM event generators of the Monte Carlo transport code MCNP6

    NASA Astrophysics Data System (ADS)

    Mashnik, Stepan G.; Kerby, Leslie M.; Gudima, Konstantin K.; Sierk, Arnold J.; Bull, Jeffrey S.; James, Michael R.

    2017-03-01

    We extend the cascade-exciton model (CEM), and the Los Alamos version of the quark-gluon string model (LAQGSM), event generators of the Monte Carlo N -particle transport code version 6 (MCNP6), to describe production of energetic light fragments (LF) heavier than 4He from various nuclear reactions induced by particles and nuclei at energies up to about 1 TeV/nucleon. In these models, energetic LF can be produced via Fermi breakup, preequilibrium emission, and coalescence of cascade particles. Initially, we study several variations of the Fermi breakup model and choose the best option for these models. Then, we extend the modified exciton model (MEM) used by these codes to account for a possibility of multiple emission of up to 66 types of particles and LF (up to 28Mg) at the preequilibrium stage of reactions. Then, we expand the coalescence model to allow coalescence of LF from nucleons emitted at the intranuclear cascade stage of reactions and from lighter clusters, up to fragments with mass numbers A ≤7 , in the case of CEM, and A ≤12 , in the case of LAQGSM. Next, we modify MCNP6 to allow calculating and outputting spectra of LF and heavier products with arbitrary mass and charge numbers. The improved version of CEM is implemented into MCNP6. Finally, we test the improved versions of CEM, LAQGSM, and MCNP6 on a variety of measured nuclear reactions. The modified codes give an improved description of energetic LF from particle- and nucleus-induced reactions; showing a good agreement with a variety of available experimental data. They have an improved predictive power compared to the previous versions and can be used as reliable tools in simulating applications involving such types of reactions.

  5. Visual Impairment

    MedlinePlus

    ... or head with a baseball or having an automobile or motorcycle accident. Some babies have congenital blindness , ... how well he or she sees at various distances. Visual field test. Ophthalmologists use this test to ...

  6. 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.

  7. Validation of MCNP6.1 for Criticality Safety of Pu-Metal, -Solution, and -Oxide Systems

    SciTech Connect

    Kiedrowski, Brian C.; Conlin, Jeremy Lloyd; Favorite, Jeffrey A.; Kahler, III, Albert C.; Kersting, Alyssa R.; Parsons, Donald K.; Walker, Jessie L.

    2014-05-13

    Guidance is offered to the Los Alamos National Laboratory Nuclear Criticality Safety division towards developing an Upper Subcritical Limit (USL) for MCNP6.1 calculations with ENDF/B-VII.1 nuclear data for three classes of problems: Pu-metal, -solution, and -oxide systems. A benchmark suite containing 1,086 benchmarks is prepared, and a sensitivity/uncertainty (S/U) method with a generalized linear least squares (GLLS) data adjustment is used to reject outliers, bringing the total to 959 usable benchmarks. For each class of problem, S/U methods are used to select relevant experimental benchmarks, and the calculational margin is computed using extreme value theory. A portion of the margin of sub criticality is defined considering both a detection limit for errors in codes and data and uncertainty/variability in the nuclear data library. The latter employs S/U methods with a GLLS data adjustment to find representative nuclear data covariances constrained by integral experiments, which are then used to compute uncertainties in keff from nuclear data. The USLs for the classes of problems are as follows: Pu metal, 0.980; Pu solutions, 0.973; dry Pu oxides, 0.978; dilute Pu oxide-water mixes, 0.970; and intermediate-spectrum Pu oxide-water mixes, 0.953.

  8. Calculation of the Fast Flux Test Facility fuel pin tests with the WIMS-E and MCNP codes

    SciTech Connect

    Schwinkendorf, K.N.; Wittekind, W.D.; Toffer, H.

    1991-10-01

    The Fuel Assembly Area (FAA) at the Fast Flux Test Facility site on the Hanford Site at Richland, Washington currently is being prepared to fabricate mixed oxide fuel (U, Pu) for the FFTF. Calculational tools are required to perform criticality safety analyses for various process locations and to establish safe limits for fissile material handling at the FAA. These codes require validation against experimental data appropriate for the compositions that will be handled. Critical array experiments performed by Bierman provide such data for mixed oxide fuel in the range Pu/(U+Pu) = 22 wt %, and with Pu-240 contents equal to 12 wt %. Both the Monte Carlo Neutron Photon (MCNP) and the Winfrith Improved Multigroup Scheme (WIMS-E) computer codes were used to calculate the neutron multiplication factor for explicit models of the various critical arrays. The W-CACTUS modules within the WIMS-E code system was used to calculate k{infinity} for the explicit array configuration, as well as few-group cross sections that were then used in a three-dimensional diffusion theory code for the calculation of k{sub eff} for the finite array. 10 refs., 15 figs., 7 tabs.

  9. Optimization of Neutron Spectrum in Northwest Beam Tube of Tehran Research Reactor for BNCT, by MCNP Code

    SciTech Connect

    Zamani, M.; Kasesaz, Y.; Khalafi, H.; Shayesteh, M.

    2015-07-01

    In order to gain the neutron spectrum with proper components specification for BNCT, it is necessary to design a Beam Shape Assembling (BSA), include of moderator, collimator, reflector, gamma filter and thermal neutrons filter, in front of the initial radiation beam from the source. According to the result of MCNP4C simulation, the Northwest beam tube has the most optimized neuron flux between three north beam tubes of Tehran Research Reactor (TRR). So, it has been chosen for this purpose. Simulation of the BSA has been done in four above mentioned phases. In each stage, ten best configurations of materials with different length and width were selected as the candidates for the next stage. The last BSA configuration includes of: 78 centimeters of air as an empty space, 40 centimeters of Iron plus 52 centimeters of heavy-water as moderator, 30 centimeters of water or 90 centimeters of Aluminum-Oxide as a reflector, 1 millimeters of lithium (Li) as thermal neutrons filter and finally 3 millimeters of Bismuth (Bi) as a filter of gamma radiation. The result of Calculations shows that if we use this BSA configuration for TRR Northwest beam tube, then the best neutron flux and spectrum will be achieved for BNCT. (authors)

  10. Validation of MCNP NPP Activation Simulations for Decommissioning Studies by Analysis of NPP Neutron Activation Foil Measurement Campaigns

    NASA Astrophysics Data System (ADS)

    Volmert, Ben; Pantelias, Manuel; Mutnuru, R. K.; Neukaeter, Erwin; Bitterli, Beat

    2016-02-01

    In this paper, an overview of the Swiss Nuclear Power Plant (NPP) activation methodology is presented and the work towards its validation by in-situ NPP foil irradiation campaigns is outlined. Nuclear Research and consultancy Group (NRG) in The Netherlands has been given the task of performing the corresponding neutron metrology. For this purpose, small Aluminium boxes containing a set of circular-shaped neutron activation foils have been prepared. After being irradiated for one complete reactor cycle, the sets have been successfully retrieved, followed by gamma-spectrometric measurements of the individual foils at NRG. Along with the individual activities of the foils, the reaction rates and thermal, intermediate and fast neutron fluence rates at the foil locations have been determined. These determinations include appropriate corrections for gamma self-absorption and neutron self-shielding as well as corresponding measurement uncertainties. The comparison of the NPP Monte Carlo calculations with the results of the foil measurements is done by using an individual generic MCNP model functioning as an interface and allowing the simulation of individual foil activation by predetermined neutron spectra. To summarize, the comparison between calculation and measurement serve as a sound validation of the Swiss NPP activation methodology by demonstrating a satisfying agreement between measurement and calculation. Finally, the validation offers a chance for further improvements of the existing NPP models by ensuing calibration and/or modelling optimizations for key components and structures.

  11. ENDF/B-V and ENDF/B-VI results for UO-2 lattice benchmark problems using MCNP

    SciTech Connect

    Mosteller, R.D.

    1998-08-01

    Calculations for the ANS UO{sub 2} lattice benchmark have been performed with the MCNP Monte Carlo code and its ENDF/B-V and EnDF/B-VI continuous-energy libraries. Similar calculations were performed previously for the experiments upon which these benchmarks are based, using continuous-energy libraries derived from EnDF/B-V and from Release 2 of EnDF/B-VI (ENDF/B-VI.2). This study extends those calculations to the infinite-lattice configurations given in the benchmark specifications and also includes results from Release 3 of EnDF/B-VI (ENDF/B-VI.3) for both the core and infinite-lattice configurations. For this set of benchmarks, the only significant difference between the ENDF/B-VI.2 and EnDF/B-VI.3 libraries is the cross-section behavior of {sup 235}U. EnDF/B-VI.3 contains revised cross sections for {sup 235}U below 900 eV, although those changes principally affect the range below 110 eV. In particular, relative to EnDF/B-VI.2, EnDF/B-VI.3 increases the epithermal capture-to-fission ratio for {sup 235}U and slightly increases its thermal fission cross section.

  12. Visual Prosthesis

    PubMed Central

    Schiller, Peter H.; Tehovnik, Edward J.

    2009-01-01

    There are more than 40 million blind individuals in the world whose plight would be greatly ameliorated by creating a visual prosthetic. We begin by outlining the basic operational characteristics of the visual system as this knowledge is essential for producing a prosthetic device based on electrical stimulation through arrays of implanted electrodes. We then list a series of tenets that we believe need to be followed in this effort. Central among these is our belief that the initial research in this area, which is in its infancy, should first be carried out in animals. We suggest that implantation of area V1 holds high promise as the area is of a large volume and can therefore accommodate extensive electrode arrays. We then proceed to consider coding operations that can effectively convert visual images viewed by a camera to stimulate electrode arrays to yield visual impressions that can provide shape, motion and depth information. We advocate experimental work that mimics electrical stimulation effects non-invasively in sighted human subjects using a camera from which visual images are converted into displays on a monitor akin to those created by electrical stimulation. PMID:19065857

  13. [Co-editors and editors with Jewish origins of the first German journals for anaesthesia. Their fate under National Socialism and an attempt at a biographical appreciation].

    PubMed

    Goerig, M; Goetz, A E

    2010-09-01

    The decision to publish the journals Der Schmerz and Narkose und Anaesthesie in 1928 was an important step towards the professionalization of anaesthesiology in Germany. The appearance of both journals, which for economic reasons merged into Schmerz - Narkose - Anaesthesie 1 year later, was initiated and vehemently supported by Jewish physicians. As editors and co-editors they were deeply involved with the editorial tasks of the journals for years from the early beginnings. When the National Socialistic Party took over the government in Germany many of the Jewish colleagues were forced to quit their editorial tasks, were eliminated and replaced by "Arians", they were persecuted and often arrested, forced to emigrate or decided to commit suicide due to inhumane personal circumstances. It is our intention to recall the biography and the terrible fate of the nearly unknown Jewish members of the editorial board of the first German anaesthesia journals. Moreover the biographic sketches promote a continuous discussion about the victims of an inhumane and barbarous ideology.

  14. Visual cognition

    SciTech Connect

    Pinker, S.

    1985-01-01

    This collection of research papers on visual cognition first appeared as a special issue of Cognition: International Journal of Cognitive Science. The study of visual cognition has seen enormous progress in the past decade, bringing important advances in our understanding of shape perception, visual imagery, and mental maps. Many of these discoveries are the result of converging investigations in different areas, such as cognitive and perceptual psychology, artificial intelligence, and neuropsychology. This volume is intended to highlight a sample of work at the cutting edge of this research area for the benefit of students and researchers in a variety of disciplines. The tutorial introduction that begins the volume is designed to help the nonspecialist reader bridge the gap between the contemporary research reported here and earlier textbook introductions or literature reviews.

  15. Influencing health debates through letters to the editor: the case of male circumcision.

    PubMed

    Carpenter, Laura M

    2009-04-01

    In this article I use the case of male circumcision (MC) to examine how grassroots activists, medical professionals, other stakeholders, and ordinary people employ letters to the editor (LTEs) to influence public health debates. I also show how journalistic practices affect the use of LTEs. Seventy LTEs about MC from U.S. newspapers between 1985 and 2006 are analyzed using qualitative methods. Pro-MC, anti-MC, and neutral LTE writers supported their stances on similar grounds, described adversaries as biased, and stressed medical and scientific authority. Yet only MC advocates and neutralists trivialized MC and declined to justify their stances, suggesting distinctive dynamics for LTEs about widely accepted practices. The prevalence of debated practices and activists' efforts to piggyback on related issues also affect LTE content. Editors chose LTEs to address readers' critiques, enact news values like balance and controversy, and showcase writers with strong claims to legitimacy, thereby mediating public health debates.

  16. PriorsEditor: a tool for the creation and use of positional priors in motif discovery

    PubMed Central

    Klepper, Kjetil; Drabløs, Finn

    2010-01-01

    Summary: Computational methods designed to discover transcription factor binding sites in DNA sequences often have a tendency to make a lot of false predictions. One way to improve accuracy in motif discovery is to rely on positional priors to focus the search to parts of a sequence that are considered more likely to contain functional binding sites. We present here a program called PriorsEditor that can be used to create such positional priors tracks based on a combination of several features, including phylogenetic conservation, nucleosome occupancy, histone modifications, physical properties of the DNA helix and many more. Availability: PriorsEditor is available as a web start application and downloadable archive from http://tare.medisin.ntnu.no/priorseditor (requires Java 1.6). The web site also provides tutorials, screenshots and example protocol scripts. Contact: kjetil.klepper@ntnu.no PMID:20628076

  17. Editor's perspective on the ECSS dedicated issue on green tides in the Yellow Sea

    NASA Astrophysics Data System (ADS)

    Valiela, Ivan

    2015-09-01

    Most of us learned about the extraordinary macroalgal bloom in the Yellow Sea through press reports previous to the 2008 Olympic competition in China. I was made aware of the extensive research efforts on this remarkable case of human-prompted, large-scale environmental change by discussions with Dr. Dongyan Liu during the 2012 ECSA conference in Venice. It soon became evident that it would be of great interest to the international audience to bring together results from the many different research projects on different aspects of this topic, taking place in different institutions and agencies. I therefore suggested that a committee of guest editors for the Issue be organized. The guest editors were charged with inviting the many researchers involved in work on the different aspects of the "green tide" phenomenon to contribute articles, request reviews of the submissions, and with helping me in editing the submissions.

  18. Writing a narrative biomedical review: considerations for authors, peer reviewers, and editors.

    PubMed

    Gasparyan, Armen Yuri; Ayvazyan, Lilit; Blackmore, Heather; Kitas, George D

    2011-11-01

    Review articles comprehensively covering a specific topic are crucial for successful research and academic projects. Most editors consider review articles for special and regular issues of journals. Writing a review requires deep knowledge and understanding of a field. The aim of this review is to analyze the main steps in writing a narrative biomedical review and to consider points that may increase the chances of success. We performed a comprehensive search through MEDLINE, EMBASE, Scopus, and Web of Science using the following keywords: review of the literature, narrative review, title, abstract, authorship, ethics, peer review, research methods, medical writing, scientific writing, and writing standards. Opinions expressed in the review are also based on personal experience as authors, peer reviewers, and editors.

  19. Red`s natural editor: A program designed to edit FORTRAN programs

    SciTech Connect

    Cullen, D.E.

    1993-09-01

    This program allows the user to edit files using a completely natural method. You don`t need a lot of time to learn how to use this program; it`s as simple as using a typewriter. Even while you are reading this report you can start editing files. Although it is as simple as using a typewriter, this is a full screen editor, so that you can overwrite (replace) anything, delete or insert characters or lines, copy or move lines, find or change anything. All of this can be done without using any complicated combinations of key strokes (as you are forced to memorize with other editors). This program is written in standard FORTRAN. Although it was designed and implemented on an IBM-PC, it can be easily adapted for use on virtually any graphics terminal.

  20. Ensuring the Quality, Fairness, and Integrity of Journal Peer Review: A Possible Role of Editors.

    PubMed

    Resnik, David B; Elmore, Susan A

    2016-02-01

    A growing body of literature has identified potential problems that can compromise the quality, fairness, and integrity of journal peer review, including inadequate review, inconsistent reviewer reports, reviewer biases, and ethical transgressions by reviewers. We examine the evidence concerning these problems and discuss proposed reforms, including double-blind and open review. Regardless of the outcome of additional research or attempts at reforming the system, it is clear that editors are the linchpin of peer review, since they make decisions that have a significant impact on the process and its outcome. We consider some of the steps editors should take to promote quality, fairness and integrity in different stages of the peer review process and make some recommendations for editorial conduct and decision-making.

  1. How the public responded to the Schiavo controversy: evidence from letters to editors.

    PubMed

    Racine, Eric; Karczewska, Marta; Seidler, Matthew; Amaram, Rakesh; Illes, Judy

    2010-09-01

    The history and genesis of major public clinical ethics controversies is intimately related to the publication of opinions and responses in media coverage. To provide a sample of public response in the media, this paper reports the results of a content analysis of letters to editors published in the four most prolific American newspapers for the Schiavo controversy. Opinions expressed in the letters sampled strongly supported the use of living wills and strongly condemned public attention to the case as well as political interventions. Letters tended to be against withdrawal of life support, proxy consent and associated procedures as well as against court decisions and legal procedures. In comparison with reports written by journalists, letters to editors contained fewer controversial claims about Schiavo''s neurological condition and behavioural repertoire but similar loaded language to describe withdrawal of life support. Distinct public discourses can be encountered in different stakeholders suggesting complex and extensive pluralism even within the media.

  2. [Hendrik Burger, editor-in-chief of the Dutch Journal of Medicine 1904- 1913].

    PubMed

    van't Hof, S E

    2007-07-28

    Hendrik Burger (1864-1957) became the sixth editor-in-chief of the Journal before gaining international fame as a professor of otorhinolaryngology. He was more a teacher than researcher, and his clinic in Amsterdam became an internationally renowned training centre. He advocated better public healthcare for children who were deaf/mute or had impaired hearing and founded schools for these children. A prolific writer, Burger contributed more than 400 papers to the Journal.

  3. [Stanisława Adamowiczowa--first editor in-chief of Journal "Przeglad Epidemiologiczny"].

    PubMed

    Gromulska, Marta

    2010-01-01

    First issue of Epidemiological Review was published in 1920. First editor in chief was Stanisława Adamowiczowa, PhD (1888-1965), who had worked in National Central Epidemiological Institute since 1919, and later, for period of 45 years, interrupted by breaks resulting from political situation, worked in National Institute of Hygiene. In this jubilee article, we present scientific resume of S. Adamowiczowa which focuses on her achievements in infectious diseases epidemiology, and particularly in analysis and evaluation of current epidemiological data distribution in Poland and worldwide in the period. She was the pioneer in systemic organization of registries of new cases of diseases in the highly populated Polish cities; she initiated use of statistical methods in this field. As editor in chief of Epidemiological Review, she started publishing Epidemiological Chronicle, which is continuously added as a supplement to every second issue, each year. Name of S. Adamowiczowa is associated with Ludwik Rajchman--director of Hygiene Section in League of Nations, with Witold Chodźko PhD--she led courses in National School of Hygiene in Warsaw, with prof. Marcin Kacprzak--as co-author and co-editor of books on hygiene and epidemiology. A brief list of scientific publications of S. Adamowiczowa is also presented.

  4. Conflicts of interest in biomedical publications: considerations for authors, peer reviewers, and editors.

    PubMed

    Gasparyan, Armen Yuri; Ayvazyan, Lilit; Akazhanov, Nurbek A; Kitas, George D

    2013-12-01

    This article overviews evidence on common instances of conflict of interest (COI) in research publications from general and specialized fields of biomedicine. Financial COIs are viewed as the most powerful source of bias, which may even distort citation outcomes of sponsored publications. The urge to boost journal citation indicators by stakeholders of science communication is viewed as a new secondary interest, which may compromize the interaction between authors, peer reviewers and editors. Comprehensive policies on disclosure of financial and non-financial COIs in scholarly journals are presented as proxies of their indexing in evidence-based databases, and examples of successful medical journals are discussed in detail. Reports on clinical trials, systematic reviews, meta-analyses and clinical practice guidelines may be unduly influenced by author-pharmaceutical industry relations, but these publications do not always contain explicit disclosures to allow the readers to judge the reliability of the published conclusions and practice-changing recommendations. The article emphasizes the importance of adhering to the guidance on COI from learned associations such as the International Committee of Medical Journal Editors (ICMJE). It also considers joint efforts of authors, peer reviewers and editors as a foundation for appropriately defining and disclosing potential COIs.

  5. How is research publishing going to progress in the next 20 years? Transcription of session for editors, associate editors, publishers and others with an interest in scientific publishing held at IADR meeting in Seattle on Wednesday, 20 March 2013.

    PubMed

    Eaton, K A; Holland, G R; Giannobile, W V; Hancocks, S; Robinson, P G; Lynch, C D

    2014-05-01

    On March 20th 2013, a one-hour session for Editors, Associate Editors, Publishers and others with an interest in scientific publishing was held at the IADR International Session in Seattle. Organised by Kenneth Eaton and Chris Lynch (Chair and Secretary, respectively, of the British Dental Editors Forum), the meeting sought to bring together leading international experts in dental publishing, as well as authors, reviewers and students engaged in research. The meeting was an overwhelming success, with more than 100 attendees. A panel involving four leading dental editors led a discussion on anticipated developments in publishing dental research with much involvement and contribution from audience members. This was the third such meeting held at the IADR for Editors, Associate Editors, Publishers and others with an interest in scientific publishing. A follow up session will take place in Cape Town on 25 June 2014 as part of the annual IADR meeting. The transcript of the meeting is reproduced in this article. Where possible speakers are identified by name. At the first time of mention their role/ position is also stated, thereafter only their name appears. We are grateful to Stephen Hancocks Ltd for their generous sponsorship of this event. For those who were not able to attend the authors hope this article gives a flavour of the discussions and will encourage colleagues to attend future events. Involvement is open to Editors, Associate Editors, Publishers and others with an interest in scientific publishing. It is a very open group and all those with an interest will be welcome to join in.

  6. How is research publishing going to progress in the next 20 years?: transcription of session for editors, associate editors, publishers and others with an interest in scientific publishing held at IADR meeting in Seattle on Wednesday, 20 March 2013.

    PubMed

    Eaton, Kenneth A; Rex Holland, G; Giannobile, William V; Hancocks, Stephen; Robinson, Peter G; Lynch, Christopher D

    2014-03-01

    On March 20th 2013, a one-hour session for Editors, Associate Editors, Publishers and others with an interest in scientific publishing was held at the IADR International Session in Seattle. Organised by Kenneth Eaton and Christopher Lynch (Chair and Secretary, respectively, of the British Dental Editors Forum), the meeting sought to bring together leading international experts in dental publishing, as well as authors, reviewers and students engaged in research. The meeting was an overwhelming success, with more than 100 attendees. A panel involving four leading dental editors led a discussion on anticipated developments in publishing dental research with much involvement and contribution from audience members. This was the third such meeting held at the IADR for Editors, Associate Editors, Publishers and others with an interest in scientific publishing. A follow-up session will take place in Cape Town on 25 June 2014 as part of the annual IADR meeting. The transcript of the Seattle meeting is reproduced in this article. Where possible speakers are identified by name. At the first time of mention their role/position is also stated, thereafter only their name appears. We are grateful to Stephen Hancocks Ltd. for their generous sponsorship of this event. For those who were not able to attend the authors hope this article gives a flavour of the discussions and will encourage colleagues to attend future events. Involvement is open to Editors, Associate Editors, Publishers and others with an interest in scientific publishing. It is a very open group and all those with an interest will be welcome to join in.

  7. Visualizing inequality

    NASA Astrophysics Data System (ADS)

    Eliazar, Iddo

    2016-07-01

    The study of socioeconomic inequality is of substantial importance, scientific and general alike. The graphic visualization of inequality is commonly conveyed by Lorenz curves. While Lorenz curves are a highly effective statistical tool for quantifying the distribution of wealth in human societies, they are less effective a tool for the visual depiction of socioeconomic inequality. This paper introduces an alternative to Lorenz curves-the hill curves. On the one hand, the hill curves are a potent scientific tool: they provide detailed scans of the rich-poor gaps in human societies under consideration, and are capable of accommodating infinitely many degrees of freedom. On the other hand, the hill curves are a powerful infographic tool: they visualize inequality in a most vivid and tangible way, with no quantitative skills that are required in order to grasp the visualization. The application of hill curves extends far beyond socioeconomic inequality. Indeed, the hill curves are highly effective 'hyperspectral' measures of statistical variability that are applicable in the context of size distributions at large. This paper establishes the notion of hill curves, analyzes them, and describes their application in the context of general size distributions.

  8. Comparison of KENO-VI and MCNP5 Criticality Analyses for a Lunar Regolith Clustered-Reactor System

    NASA Astrophysics Data System (ADS)

    Bess, John Darrell

    2008-01-01

    The Lunar Regolith Clustered-Reactor System design has been presented as an alternative method for providing surface power to a lunar facility using a fast-fission, heatpipe-cooled nuclear reactor. The reactor system is divided into subcritical units that can be safely launched into orbit without risk of inadvertent criticality in the event of a launch accident. The reactor subunits are emplaced into the lunar surface to form a clustered-reactor system, utilizing the regolith as both radiation shielding and neutron-reflector material. Coordinated placement of multiple subunits can provision a critical reactor system proportional to localized lunar surface power demand. Reactor units assembled using proven and tested materials in radiation environments such as UO2 fuel, stainless-steel cladding and support, and compatible liquid-metal heatpipes promote safety and reliability, with ease of manufacture and testing. Reactor power levels of approximately 100 kWth per subunit significantly reduces the negative effects of elevated temperature and radiation environments associated with single nuclear power reactors operated at higher power levels. The analysis of subunit criticality in various accident scenarios differs by up to 4% (~$6 in reactivity) between results generated using conventional criticality analysis codes, MCNP5 and KENO-VI. A demonstrated trend exists between results of the two criticality codes as accident conditions approach a multiplication factor of one. Code comparison of a tri-cluster system on the lunar surface provides comparable results with calculated system reactivity within 0.5%. Iron concentration is confirmed as the dominant element in the lunar regolith influencing system reactivity.

  9. A New On-the-Fly Sampling Method for Incoherent Inelastic Thermal Neutron Scattering Data in MCNP6

    SciTech Connect

    Pavlou, Andrew Theodore; Brown, Forrest B.; Ji, Wei

    2014-09-02

    At thermal energies, the scattering of neutrons in a system is complicated by the comparable velocities of the neutron and target, resulting in competing upscattering and downscattering events. The neutron wavelength is also similar in size to the target's interatomic spacing making the scattering process a quantum mechanical problem. Because of the complicated nature of scattering at low energies, the thermal data files in ACE format used in continuous-energy Monte Carlo codes are quite large { on the order of megabytes for a single temperature and material. In this paper, a new storage and sampling method is introduced that is orders of magnitude less in size and is used to sample scattering parameters at any temperature on-the-fly. In addition to the reduction in storage, the need to pre-generate thermal scattering data tables at fine temperatures has been eliminated. This is advantageous for multiphysics simulations which may involve temperatures not known in advance. A new module was written for MCNP6 that bypasses the current S(α,β) table lookup in favor of the new format. The new on-the-fly sampling method was tested for graphite for two benchmark problems at ten temperatures: 1) an eigenvalue test with a fuel compact of uranium oxycarbide fuel homogenized into a graphite matrix, 2) a surface current test with a \\broomstick" problem with a monoenergetic point source. The largest eigenvalue difference was 152pcm for T= 1200K. For the temperatures and incident energies chosen for the broomstick problem, the secondary neutron spectrum showed good agreement with the traditional S(α,β) sampling method. These preliminary results show that sampling thermal scattering data on-the-fly is a viable option to eliminate both the storage burden of keeping thermal data at discrete temperatures and the need to know temperatures before simulation runtime.

  10. Quantitative comparison between PGNAA measurements and MCNP calculations in view of the characterization of radioactive wastes in Germany and France

    NASA Astrophysics Data System (ADS)

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

    2013-04-01

    The Forschungszentrum Jülich GmbH (FZJ), together with the Aachen University Rheinisch-Westfaelische Technische Hochschule (RWTH) and the French Alternative Energies and Atomic Energy Commission (CEA Cadarache) 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) [1]. The French and German waste management agencies have indeed defined acceptability limits concerning these elements in view of their projected geological repositories. A first measurement campaign was performed in the new Prompt Gamma Neutron Activation Analysis (PGNAA) facility called MEDINA, at FZJ, to assess the capture gamma-ray signatures of some elements of interest in large samples up to waste drums with a volume of 200 liter. MEDINA is the acronym for Multi Element Detection based on Instrumental Neutron Activation. This paper presents MCNP calculations of the MEDINA facility and quantitative comparison between measurement and simulation. Passive gamma-ray spectra acquired with a high purity germanium detector and calibration sources are used to qualify the numerical model of the crystal. Active PGNAA spectra of a sodium chloride sample measured with MEDINA then allow for qualifying the global numerical model of the measurement cell. Chlorine indeed constitutes a usual reference with reliable capture gamma-ray production data. The goal is to characterize the entire simulation protocol (geometrical model, nuclear data, and postprocessing tools) which will be used for current measurement interpretation, extrapolation of the performances to other types of waste packages or other applications, as well as for the study of future PGNAA facilities.

  11. Quantitative comparison between PGNAA measurements and MCNP calculations in view of the characterization of radioactive wastes in Germany and France

    SciTech Connect

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

    2013-04-19

    The Forschungszentrum Juelich GmbH (FZJ), together with the Aachen University Rheinisch-Westfaelische Technische Hochschule (RWTH) and the French Alternative Energies and Atomic Energy Commission (CEA Cadarache) 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 French and German waste management agencies have indeed defined acceptability limits concerning these elements in view of their projected geological repositories. A first measurement campaign was performed in the new Prompt Gamma Neutron Activation Analysis (PGNAA) facility called MEDINA, at FZJ, to assess the capture gamma-ray signatures of some elements of interest in large samples up to waste drums with a volume of 200 liter. MEDINA is the acronym for Multi Element Detection based on Instrumental Neutron Activation. This paper presents MCNP calculations of the MEDINA facility and quantitative comparison between measurement and simulation. Passive gamma-ray spectra acquired with a high purity germanium detector and calibration sources are used to qualify the numerical model of the crystal. Active PGNAA spectra of a sodium chloride sample measured with MEDINA then allow for qualifying the global numerical model of the measurement cell. Chlorine indeed constitutes a usual reference with reliable capture gamma-ray production data. The goal is to characterize the entire simulation protocol (geometrical model, nuclear data, and postprocessing tools) which will be used for current measurement interpretation, extrapolation of the performances to other types of waste packages or other applications, as well as for the study of future PGNAA facilities.

  12. Sensitivity of MCNP5 calculations for a spherical numerical benchmark problem to the angular scattering distributions for deuterium

    SciTech Connect

    Kozier, K. S.

    2006-07-01

    This paper examines the sensitivity of MCNP5 k{sub eff} results to various deuterium data files for a simple benchmark problem consisting of an 8.4-cm radius sphere of uranium surrounded by an annulus of deuterium at the nuclide number density corresponding to heavy water. This study was performed to help clarify why {Delta}k{sub eff} values of about 10 mk are obtained when different ENDF/B deuterium data files are used in simulations of critical experiments involving solutions of high-enrichment uranyl fluoride in heavy water, while simulations of low-leakage, heterogeneous critical lattices of natural-uranium fuel rods in heavy water show differences of <1 mk. The benchmark calculations were performed as a function of deuterium reflector thickness for several uranium compositions using deuterium ACE files derived from ENDF/B-VII.b1 (release beta 1), ENDF/B-VI.4 and JENDL-3.3, which differ primarily in the energy/angle distributions for elastic scattering <3.2 MeV. Calculations were also performed using modified ACE files having equiprobable cosine bin values in the centre-of-mass reference frame in a progressive manner with increasing energy. It was found that the {Delta}k{sub eff} values increased with deuterium reflector thickness and uranium enrichment. The studies using modified ACE files indicate that most of the reactivity differences arise at energies <1 MeV; hence, this energy range should be given priority if new scattering distribution measurements are undertaken. (authors)

  13. Comparison of KENO-VI and MCNP5 Criticality Analyses for a Lunar Regolith Clustered-Reactor System

    SciTech Connect

    Bess, John Darrell

    2008-01-21

    The Lunar Regolith Clustered-Reactor System design has been presented as an alternative method for providing surface power to a lunar facility using a fast-fission, heatpipe-cooled nuclear reactor. The reactor system is divided into subcritical units that can be safely launched into orbit without risk of inadvertent criticality in the event of a launch accident. The reactor subunits are emplaced into the lunar surface to form a clustered-reactor system, utilizing the regolith as both radiation shielding and neutron-reflector material. Coordinated placement of multiple subunits can provision a critical reactor system proportional to localized lunar surface power demand. Reactor units assembled using proven and tested materials in radiation environments such as UO{sub 2} fuel, stainless-steel cladding and support, and compatible liquid-metal heatpipes promote safety and reliability, with ease of manufacture and testing. Reactor power levels of approximately 100 kWth per subunit significantly reduces the negative effects of elevated temperature and radiation environments associated with single nuclear power reactors operated at higher power levels. The analysis of subunit criticality in various accident scenarios differs by up to 4% ({approx}$6 in reactivity) between results generated using conventional criticality analysis codes, MCNP5 and KENO-VI. A demonstrated trend exists between results of the two criticality codes as accident conditions approach a multiplication factor of one. Code comparison of a tri-cluster system on the lunar surface provides comparable results with calculated system reactivity within 0.5%. Iron concentration is confirmed as the dominant element in the lunar regolith influencing system reactivity.

  14. Improvement of the MCNP simulated n-gamma spectrometer response function using the new ENDF/B-VI evaluations for thermal neutron capture

    NASA Astrophysics Data System (ADS)

    Cywicka-Jakiel, T.; Zorski, T.

    2007-09-01

    An impact of the improved nuclear data library for thermal neutron capture (ENDF/B-VI.8) on the numerically simulated response of the spectrometric n-gamma well logging (sNGL) probe, SO-5-90-SN type, has been investigated. For this aim the MCNP simulations have been done using two kinds of data libraries for radiative capture: the commonly used ENDF/B-VI.2 (ENDF60) and the new ENDF/B-VI. 8 (ACTIA). MCNP simulations concerned the n-gamma benchmark experiment which was performed at the Polish calibration station in Zielona Góra to investigate the influence of chlorine in borehole on the tool readings and thus on the accuracy of quantitative elemental analysis for the main rock elements: Si, Ca and Fe. High quality of the nuclear data for radiative capture in Cl and Al have been of special interest as the ENDF60 library contains an imperfect data for Cl and there is no delay gamma-ray line of energy 1.7791 MeV from thermal neutron capture in Al. The last element is the main construction material for the SO-5-90-SN spectrometer. The advantage of the new ACTIA library over the ENDF60 was shown through the better matching of the experimental and simulated gamma-ray spectra from thermal neutron capture. As a consequence the Si, Ca and Fe rock contents obtained from the MCNP modeling with the use of ACTIA data, fit well their reference values regarded as "true". The accuracies for the Si, Ca and Fe determination have been improved by about 63%, 35% and 51%, respectively.

  15. Editor's note

    NASA Astrophysics Data System (ADS)

    2014-08-01

    Progress in marine sciences often follows the development of new methods. The Invited Feature Article "New Insight into Particulate Mineral and Organic Matter in Coastal Ocean Waters through Optical Inversion" by Xiaodong Zhang, Robert Hans Stavn, Alexander U. Falster, Deric J. Gray, and Richard W. Gould demonstrates a new method that uses scattering and transmissometer data to differentiate between particle size distribution of suspended mineral and that of suspended organic matter. The method helps define the particular groups of phytoplankton that may be dominant, whether organic detritus may be more significant in suspended organic matter, add insight on the dominant size classes of mineral aggregates, and helps differentiate between organic detritus-dominated systems and biogenic-dominated systems.

  16. Editor's note

    NASA Astrophysics Data System (ADS)

    2005-11-01

    Nordita, the Nordic Institute for Theoretical Physics, was founded in 1957 by Niels Bohr and Torsten Gustafsson at Blegdamsvej in Copenhagen, joint to Bohr's legendary Institute. Today, memories of Bohr and his famous visitors -- Albert Einstein, Werner Heisenberg, Lev Landau and many others -- strongly contribute to Nordita's genius loci and inspire next generations of her visitors. Nordita awards ``Nordic Project'' grants to individual Nordic physicists to help conduct a world-class research in Nordic countries (Denmark, Finland, Island, Norway, and Sweden). Research reported here was generously supported by the Nordic Project "Quasi Periodic Oscillations in Black Hole and Neutron Star sources" awarded in 2005 to Marek Abramowicz. The Project supported the ``Nordita Workdays on QPO" (March 25 -- April 1, 2005) organized by Marek Abramowicz, Axel Brandenburg and Juri Poutanen with help of Hanne Bergen, Helle http://www.nordita.dk/positions/norproject.html

  17. Editor's note

    NASA Astrophysics Data System (ADS)

    2016-02-01

    In the Invited Feature Article in this issue of Estuarine, Coastal and Shelf Science, Ruben Kosyan and Violeta Velikova describe the disastrous anthropogenic impact on the Black Sea coast of Bulgaria, Georgia, Romania, Russian Federation, Turkey, and Ukraine over the last 100 years and its inverse correlation with economic development as exemplified by improving water quality during a downturn in the economy. This degradation is now accelerating from the renovation and construction of ports and terminals, the development of resorts, hazardous industrial development, oil and gas exploration, and unsustainable agricultural and fishing practices. There appears to be no enforcement of protected areas. In the absence of scientific research on these issues, coastal zone management appears to be based on 'learning after seeing disastrous effects'. Without recognition of the need for Integrated Coastal Zone Management, the Black Sea coast and the coastal waters will deteriorate, as was observed between the 1970s and the 1990s.

  18. Editor's Note.

    PubMed

    Alberts, Bruce

    2011-05-27

    The Research Article "A bacterium that can grow by using arsenic instead of phosphorus" by F. Wolfe-Simon et al., published online 2 December 2010, was the subject of extensive discussion and criticism following its online publication. Science received a wide range of correspondence that raised specific concerns about the Research Article's methods and interpretations. Eight Technical Comments that represent the main concerns, as well as a Technical Response by Wolfe-Simon et al., are published online in Science Express at the addresses listed in this note. They have been peer-reviewed and revised according to Science's standard procedure.

  19. Editors' note

    NASA Astrophysics Data System (ADS)

    2015-03-01

    The widespread eutrophication of coastal waters clearly involves increased nitrogen loads, in most cases with nitrogen derived from human activities on contributing watersheds. This has prompted regulators, managers, and other stakeholders to set standards for water quality that involve lowering nitrogen loads to estuaries and other coastal waters. To carry out the proscribed lowering of nitrogen loads there are a number of options. In many instances and sites with high human density and intense activity, advanced wastewater treatment plants are unavoidable, but such environmental engineering approaches are costly. There are many coastal zones with lower population densities where other, less costly alternative strategies might be less expensive and more attuned to "green" approaches.

  20. Editor's Introduction.

    ERIC Educational Resources Information Center

    Cozzens, Susan E.

    1986-01-01

    Offers perspectives and ideas on a range of issues related to policy-relevant research in science studies. Identifies and discusses major challenges and problems involved in science policy studies. Presents an overview of articles that address the theme of funding and knowledge growth. (ML)