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Sample records for users manual version

  1. IDSE Version 1 User's Manual

    Science.gov (United States)

    Mayer, Richard

    1988-01-01

    The integrated development support environment (IDSE) is a suite of integrated software tools that provide intelligent support for information modelling. These tools assist in function, information, and process modeling. Additional tools exist to assist in gathering and analyzing information to be modeled. This is a user's guide to application of the IDSE. Sections covering the requirements and design of each of the tools are presented. There are currently three integrated computer aided manufacturing definition (IDEF) modeling methodologies: IDEF0, IDEF1, and IDEF2. Also, four appendices exist to describe hardware and software requirements, installation procedures, and basic hardware usage.

  2. Sesame IO Library User Manual Version 8

    Energy Technology Data Exchange (ETDEWEB)

    Abhold, Hilary [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Young, Ginger Ann [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2017-05-15

    This document is a user manual for SES_IO, a low-level library for reading and writing sesame files. The purpose of the SES_IO library is to provide a simple user interface for accessing and creating sesame files that does not change across sesame format type (such as binary, ascii, and xml).

  3. UQTk version 2.0 user manual

    Energy Technology Data Exchange (ETDEWEB)

    Debusschere, Bert J. [Sandia National Lab. (SNL-CA), Livermore, CA (United States); Sargsyan, Khachik [Sandia National Lab. (SNL-CA), Livermore, CA (United States); Safta, Cosmin [Sandia National Lab. (SNL-CA), Livermore, CA (United States)

    2013-10-01

    The UQ Toolkit (UQTk) is a collection of libraries and tools for the quantification of uncertainty in numerical model predictions. Version 2.0 ffers intrusive and non-intrusive methods for propagating input uncertainties through computational models, tools for sensitivity analysis, methods for sparse surrogate construction, and Bayesian inference tools for inferring parameters from experimental data. This manual discusses the download and installation process for UQTk, provides pointers to the UQ methods used in the toolkit, and describes some of the examples provided with the toolkit.

  4. HECTR Version 1.5 user's manual

    International Nuclear Information System (INIS)

    Dingman, S.E.; Camp, A.L.; Wong, C.C.; King, D.B.; Gasser, R.D.

    1986-04-01

    This report describes the use and features of HECTR Version 1.5. HECTR is a relatively fast-running, lumped-volume containment analysis computer program that is most useful for performing parametric studies. The main purpose of HECTR is to analyze nuclear reactor accidents involving the transport and combustion of hydrogen, but HECTR can also function as an experiment analysis tool and can solve a limited set of other types of containment problems. New models added to HECTR Version 1.5 include fan coolers, containment leakage, continuous burning, and the capability to treat carbon monoxide and carbon dioxide. Models for the ice condenser, sumps, and Mark III suppression pool were upgraded. HECTR is designed for flexibility and provides for user control of many important parameters, particularly those related to hydrogen combustion. Built-in correlations and default values of key parameters are also provided

  5. SPARK Version 1.1 user manual

    International Nuclear Information System (INIS)

    Weissenburger, D.W.

    1988-01-01

    This manual describes the input required to use Version 1.1 of the SPARK computer code. SPARK 1.1 is a library of FORTRAN main programs and subprograms designed to calculate eddy currents on conducting surfaces where current flow is assumed zero in the direction normal to the surface. Surfaces are modeled with triangular and/or quadrilateral elements. Lorentz forces produced by the interaction of eddy currents with background magnetic fields can be output at element nodes in a form compatible with most structural analysis codes. In addition, magnetic fields due to eddy currents can be determined at points off the surface. Version 1.1 features eddy current streamline plotting with optional hidden-surface-removal graphics and topological enhancements that allow essentially any orientable surface to be modeled. SPARK also has extensive symmetry specification options. In order to make the manual as self-contained as possible, six appendices are included that present summaries of the symmetry options, topological options, coil options and code algorithms, with input and output examples. An edition of SPARK 1.1 is available on the Cray computers at the National Magnetic Fusion Energy Computer Center at Livermore, California. Another more generic edition is operational on the VAX computers at the Princeton Plasma Physics Laboratory and is available on magnetic tape by request. The generic edition requires either the GKS or PLOT10 graphics package and the IMSL or NAG mathematical package. Requests from outside the United States will be subject to applicable federal regulations regarding dissemination of computer programs. 22 refs

  6. SPARK Version 1. 1 user manual

    Energy Technology Data Exchange (ETDEWEB)

    Weissenburger, D.W.

    1988-01-01

    This manual describes the input required to use Version 1.1 of the SPARK computer code. SPARK 1.1 is a library of FORTRAN main programs and subprograms designed to calculate eddy currents on conducting surfaces where current flow is assumed zero in the direction normal to the surface. Surfaces are modeled with triangular and/or quadrilateral elements. Lorentz forces produced by the interaction of eddy currents with background magnetic fields can be output at element nodes in a form compatible with most structural analysis codes. In addition, magnetic fields due to eddy currents can be determined at points off the surface. Version 1.1 features eddy current streamline plotting with optional hidden-surface-removal graphics and topological enhancements that allow essentially any orientable surface to be modeled. SPARK also has extensive symmetry specification options. In order to make the manual as self-contained as possible, six appendices are included that present summaries of the symmetry options, topological options, coil options and code algorithms, with input and output examples. An edition of SPARK 1.1 is available on the Cray computers at the National Magnetic Fusion Energy Computer Center at Livermore, California. Another more generic edition is operational on the VAX computers at the Princeton Plasma Physics Laboratory and is available on magnetic tape by request. The generic edition requires either the GKS or PLOT10 graphics package and the IMSL or NAG mathematical package. Requests from outside the United States will be subject to applicable federal regulations regarding dissemination of computer programs. 22 refs.

  7. MULTIPLE PROJECTIONS SYSTEM (MPS) - USER'S MANUAL VERSION 1.0

    Science.gov (United States)

    The report is a user's manual for version 1.0 of the Multiple Projections Systems (MPS), a computer system that can perform "what if" scenario analysis and report the final results (i.e., Rate of Further Progress - ROP - inventories) to EPA (i.e., the Aerometric Information Retri...

  8. TOUGH2-GRS version 1. User manual

    Energy Technology Data Exchange (ETDEWEB)

    Navarro, Martin; Eckel, Jens

    2016-07-15

    TOUGH2 is a code for the simulation of multi-phase flow processes in porous media that has been developed by the Lawrence Berkeley National Laboratory, California, USA. Since 1991, GRS has been using the code for process analyses and safety assessments for deep geological repositories and has extended the code by several processes that are relevant for repository systems. The TOUGH2 source code that has been developed further by GRS is referred to as TOUGH2-GRS. The present report presents code version 1.1.g, which was developed in project UM13 A 03400 sponsored by the German Federal Ministry for the Environment, Nature Conservation, Building and Nuclear Safety (BMUB).

  9. National Radiobiology Archives Distributed Access User`s Manual, Version 1.1. Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    Smith, S.K.; Prather, J.C.; Ligotke, E.K.; Watson, C.R.

    1992-06-01

    This supplement to the NRA Distributed Access User`s manual (PNL-7877), November 1991, describes installation and use of Version 1.1 of the software package; this is not a replacement of the previous manual. Version 1.1 of the NRA Distributed Access Package is a maintenance release. It eliminates several bugs, and includes a few new features which are described in this manual. Although the appearance of some menu screens has changed, we are confident that the Version 1.0 User`s Manual will provide an adequate introduction to the system. Users who are unfamiliar with Version 1.0 may wish to experiment with that version before moving on to Version 1.1.

  10. User's Manual for LEWICE Version 3.2

    Science.gov (United States)

    Wright, William

    2008-01-01

    A research project is underway at NASA Glenn to produce a computer code which can accurately predict ice growth under a wide range of meteorological conditions for any aircraft surface. This report will present a description of the code inputs and outputs from version 3.2 of this software, which is called LEWICE. This version differs from release 2.0 due to the addition of advanced thermal analysis capabilities for de-icing and anti-icing applications using electrothermal heaters or bleed air applications, the addition of automated Navier-Stokes analysis, an empirical model for supercooled large droplets (SLD) and a pneumatic boot option. An extensive effort was also undertaken to compare the results against the database of electrothermal results which have been generated in the NASA Glenn Icing Research Tunnel (IRT) as was performed for the validation effort for version 2.0. This report will primarily describe the features of the software related to the use of the program. Appendix A has been included to list some of the inner workings of the software or the physical models used. This information is also available in the form of several unpublished documents internal to NASA. This report is intended as a replacement for all previous user manuals of LEWICE. In addition to describing the changes and improvements made for this version, information from previous manuals may be duplicated so that the user will not need to consult previous manuals to use this software.

  11. PC/FRAM, Version 3.2 User Manual

    International Nuclear Information System (INIS)

    Kelley, T.A.; Sampson, T.E.

    1999-01-01

    This manual describes the use of version 3.2 of the PC/FRAM plutonium isotopic analysis software developed in the Safeguards Science and Technology Group, NE-5, Nonproliferation and International Security Division Los Alamos National Laboratory. The software analyzes the gamma ray spectrum from plutonium-bearing items and determines the isotopic distribution of the plutonium 241Am content and concentration of other isotopes in the item. The software can also determine the isotopic distribution of uranium isotopes in items containing only uranium. The body of this manual descenies the generic version of the code. Special facility-specific enhancements, if they apply, will be described in the appendices. The information in this manual applies equally well to version 3.3, which has been licensed to ORTEC. The software can analyze data that is stored in a file on disk. It understands several storage formats including Canberra's S1OO format, ORTEC'S 'chn' and 'SPC' formats, and several ASCII text formats. The software can also control data acquisition using an MCA and then store the results in a file on disk for later analysis or analyze the spectrum directly after the acquisition. The software currently only supports the control of ORTEC MCB'S. Support for Canbema's Genie-2000 Spectroscopy Systems will be added in the future. Support for reading and writing CAM files will also be forthcoming. A versatile parameter fde database structure governs all facets of the data analysis. User editing of the parameter sets allows great flexibility in handling data with different isotopic distributions, interfering isotopes, and different acquisition parameters such as energy calibration, and detector type. This manual is intended for the system supervisor or the local user who is to be the resident expert. Excerpts from this manual may also be appropriate for the system operator who will routinely use the instrument

  12. AIMSsim Version 2.3.4 - User Manual

    National Research Council Canada - National Science Library

    Schoenborn, Oliver; Lachance, Patrick; Bahramifarid, Nima

    2008-01-01

    This user manual provides an overview of the software functionality developed to support the empirical investigation of a simulated user interface for an Advanced Integrated Multi-sensor Surveillance (AIMS) system...

  13. AIMSsim Version 2.2.1, User Manual

    National Research Council Canada - National Science Library

    Schoenborn, Oliver

    2007-01-01

    This user manual provides an overview of how to use the software developed to support the empirical investigation of a simulated user interface for an Advanced Integrated Multi sensor Surveillance (AIMS) system...

  14. Object Toolkit Version 4.3 User’s Manual

    Science.gov (United States)

    2016-12-31

    and with Nascap-2k. See the EPIC and Nascap-2k manuals for instructions. Most of the difficulties that users have encountered with Object Toolkit are...4/icond). 12.3 Importing Components From a NX I-DEAS TMG ASCII VUFF File Users of the NX I-DEAS TMG thermal analysis program can import the ASCII...2k user interface. The meaning of these properties is discussed in the Nascap-2k User’s Manual . Figure 36. Detector Properties Dialog Box. 15.5

  15. User's manual, version 1.00 for Monteburns, version 3.01

    International Nuclear Information System (INIS)

    Poston, D.I.; Trellue, H.R.

    1998-06-01

    Monteburns is a fully automated tool that links the Monte Carlo transport code MCNP with the radioactive decay and burnup code ORIGEN2. Monteburns produces a large number of criticality and burnup results based on various material feed/removal specifications, power(s), and time intervals. The program processes input from the user that specifies the system geometry, initial material compositions, feed/removal specifications, and other code-specific parameters. Various results from MCNP, ORIGEN2, and other calculations are then output successively as the code runs. The principle function of monteburns is to transfer one-group cross section and flux values from MCNP to ORIGEN2, and then transfer the resulting material compositions (after irradiation and/or decay) from ORIGEN2 back to MCNP in a repeated, cyclic fashion. The basic requirement of the code is that the user have a working MCNP input file and other input parameters; all interaction with ORIGEN2 and other calculations are performed by monteburns. This report serves as a user's manual for monteburns. It describes how the code functions, what input the user must provide, the calculations performed by the code, and it presents the format required for input files, as well as samples of these files. Monteburns is still in a developmental stage; thus, additions and/or changes may be made over time, and the user's manual will change as well. This is the first version of the user's manual (valid for monteburns version 3.01); users should contact the authors to inquire if a more recent version is available

  16. Code development and analysis program. RELAP4/MOD7 (Version 2): user's manual

    International Nuclear Information System (INIS)

    1978-08-01

    This manual describes RELAP4/MOD7 (Version 2), which is the latest version of the RELAP4 LPWR blowdown code. Version 2 is a precursor to the final version of RELAP4/MOD7, which will address LPWR LOCA analysis in integral fashion (i.e., blowdown, refill, and reflood in continuous fashion). This manual describes the new code models and provides application information required to utilize the code. It must be used in conjunction with the RELAP4/MOD5 User's Manual (ANCR-NUREG-1335, dated September 1976), and the RELAP4/MOD6 User's Manual

  17. ANOPP2 User's Manual: Version 1.2

    Science.gov (United States)

    Lopes, L. V.; Burley, C. L.

    2016-01-01

    This manual documents the Aircraft NOise Prediction Program 2 (ANOPP2). ANOPP2 is a toolkit that includes a framework, noise prediction methods, and peripheral software to aid a user in predicting and understanding aircraft noise. This manual includes an explanation of the overall design and structure of ANOPP2, including a brief introduction to aircraft noise prediction and the ANOPP2 background, philosophy, and architecture. The concept of nested acoustic data surfaces and its application to a mixed-fidelity noise prediction are presented. The structure and usage of ANOPP2, which includes the communication between the user, the ANOPP2 framework, and noise prediction methods, are presented for two scenarios: wind-tunnel and flight. These scenarios serve to provide the user with guidance and documentation references for performing a noise prediction using ANOPP2.

  18. M3 User's Manual. Version 3.0

    International Nuclear Information System (INIS)

    Laaksoharju, Marcus; Skaarman, Erik; Gomez, Javier B.

    2009-11-01

    This report describes the Multivariate Mixing and Mass balance calculations (M3). This new method and computer code is developed to trace the mixing and reaction processes in the groundwater. The aim of the M3 concept is to decode the often hidden and complex information gathered in the groundwater analytical data. The manual presents shortly the theory and practice behind the M3 method. The M3 computer code is also presented and emphasis is put on the reference manual. This includes detailed reference to the M3 program's abilities and limitations, installation procedures and all functions and operations that the program can perform. It also describes sample cases of how the program is used to analyse a test data set. This guide is part of the Help Files distributed together with M3. Two accompanying reports cover other aspects: - Concepts, Methods, and Mathematical Formulation, gives a complete description of the mathematical framework of M3 and introduces concepts and methods useful for the end user. - M3 version 3.0: Verification and Validation, gathers a collection of validation and verification exercises, designed to test each part of M3 code and to build confidence in its methodology. The M3 method has been tested and modified over several years. The development work has been supported by the Swedish Nuclear Fuel and Waste Management Company (SKB). The main test site for the model was the underground Aespoe Hard Rock Laboratory (HRL). The examples used in this manual are from a Aespoe international groundwater modelling co-operation project where one of the tools used was M3. The M3 concept has been applied on the data from SKB's site investigation programme and in data from Canada, Japan, Jordan, Gabon and Finland. The groundwater composition is a result of mixing processes and water-rock interaction. Standard groundwater models based on thermodynamic laws may not be applicable in a normal temperature groundwater system where equilibrium with many of the

  19. National Radiobiology Archives Distributed Access User's Manual, Version 1. 1

    Energy Technology Data Exchange (ETDEWEB)

    Smith, S.K.; Prather, J.C.; Ligotke, E.K.; Watson, C.R.

    1992-06-01

    This supplement to the NRA Distributed Access User's manual (PNL-7877), November 1991, describes installation and use of Version 1.1 of the software package; this is not a replacement of the previous manual. Version 1.1 of the NRA Distributed Access Package is a maintenance release. It eliminates several bugs, and includes a few new features which are described in this manual. Although the appearance of some menu screens has changed, we are confident that the Version 1.0 User's Manual will provide an adequate introduction to the system. Users who are unfamiliar with Version 1.0 may wish to experiment with that version before moving on to Version 1.1.

  20. UQTk Version 3.0.3 User Manual

    Energy Technology Data Exchange (ETDEWEB)

    Sargsyan, Khachik [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Safta, Cosmin [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Chowdhary, Kamaljit Singh [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Castorena, Sarah [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); De Bord, Sarah [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Debusschere, Bert [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2017-05-01

    The UQ Toolkit (UQTk) is a collection of libraries and tools for the quantification of uncertainty in numerical model predictions. Version 3.0.3 offers intrusive and non-intrusive methods for propagating input uncertainties through computational models, tools for sen- sitivity analysis, methods for sparse surrogate construction, and Bayesian inference tools for inferring parameters from experimental data. This manual discusses the download and installation process for UQTk, provides pointers to the UQ methods used in the toolkit, and describes some of the examples provided with the toolkit.

  1. User's manual for CBS3DS, version 1.0

    Science.gov (United States)

    Reddy, C. J.; Deshpande, M. D.

    1995-10-01

    CBS3DS is a computer code written in FORTRAN 77 to compute the backscattering radar cross section of cavity backed apertures in infinite ground plane and slots in thick infinite ground plane. CBS3DS implements the hybrid Finite Element Method (FEM) and Method of Moments (MoM) techniques. This code uses the tetrahedral elements, with vector edge basis functions for FEM in the volume of the cavity/slot and the triangular elements with the basis functions for MoM at the apertures. By virtue of FEM, this code can handle any arbitrarily shaped three-dimensional cavities filled with inhomogeneous lossy materials; due to MoM, the apertures can be of any arbitrary shape. The User's Manual is written to make the user acquainted with the operation of the code. The user is assumed to be familiar with the FORTRAN 77 language and the operating environment of the computer the code is intended to run.

  2. User's Manual for FEMOM3DS. Version 1.0

    Science.gov (United States)

    Reddy, C.J.; Deshpande, M. D.

    1997-01-01

    FEMOM3DS is a computer code written in FORTRAN 77 to compute electromagnetic(EM) scattering characteristics of a three dimensional object with complex materials using combined Finite Element Method (FEM)/Method of Moments (MoM) technique. This code uses the tetrahedral elements, with vector edge basis functions for FEM in the volume of the cavity and the triangular elements with the basis functions similar to that described for MoM at the outer boundary. By virtue of FEM, this code can handle any arbitrarily shaped three-dimensional cavities filled with inhomogeneous lossy materials. The User's Manual is written to make the user acquainted with the operation of the code. The user is assumed to be familiar with the FORTRAN 77 language and the operating environment of the computers on which the code is intended to run.

  3. User's Manual for FEMOM3DR. Version 1.0

    Science.gov (United States)

    Reddy, C. J.

    1998-01-01

    FEMoM3DR is a computer code written in FORTRAN 77 to compute radiation characteristics of antennas on 3D body using combined Finite Element Method (FEM)/Method of Moments (MoM) technique. The code is written to handle different feeding structures like coaxial line, rectangular waveguide, and circular waveguide. This code uses the tetrahedral elements, with vector edge basis functions for FEM and triangular elements with roof-top basis functions for MoM. By virtue of FEM, this code can handle any arbitrary shaped three dimensional bodies with inhomogeneous lossy materials; and due to MoM the computational domain can be terminated in any arbitrary shape. The User's Manual is written to make the user acquainted with the operation of the code. The user is assumed to be familiar with the FORTRAN 77 language and the operating environment of the computers on which the code is intended to run.

  4. Water Security Toolkit User Manual: Version 1.3 | Science ...

    Science.gov (United States)

    User manual: Data Product/Software The Water Security Toolkit (WST) is a suite of tools that help provide the information necessary to make good decisions resulting in the minimization of further human exposure to contaminants, and the maximization of the effectiveness of intervention strategies. WST assists in the evaluation of multiple response actions in order to select the most beneficial consequence management strategy. It includes hydraulic and water quality modeling software and optimization methodologies to identify: (1) sensor locations to detect contamination, (2) locations in the network in which the contamination was introduced, (3) hydrants to remove contaminated water from the distribution system, (4) locations in the network to inject decontamination agents to inactivate, remove or destroy contaminants, (5) locations in the network to take grab sample to confirm contamination or cleanup and (6) valves to close in order to isolate contaminated areas of the network.

  5. CDD CERN Drawings Directory User's manual Version 1.1

    CERN Document Server

    Delamare, Christophe; Jeannin, F; Petit, S

    1996-01-01

    CDD (CERN Drawings Directory) is a multi-platform utility which manages engineering drawings made in any division at CERN. The aim of CDD is not to store the graphical drawing itself, but to store a reference with some information related to the drawing. Access to this data is provided via a graphical user interface which is based upon ORACLE Forms and via WWW. Drawings following different numbering systems and different management rules can be handled by CDD. The only condition is that those particular functionalities are well defined. Several drawing systems have been identified in CERN and therefore considered when designing the application. The current version of CDD focuses on systems EST, LEP, ST-IE, SPS, ST-CE and the experiments ALICE, ATLAS, CMS and LHCb. Other CERN systems could be easily integrated upon demand.

  6. DECADES Tools. User's manual for version 1.0

    International Nuclear Information System (INIS)

    2000-01-01

    databases for analysis of costs and environmental burdens at the power plant, full energy chain and electric system levels, and a decision analysis tool. The DECADES Tools were developed jointly by the International Atomic Energy Agency (IAEA), Argonne National Laboratory (ANL) under contract with the IAEA funded by extrabudgetary contribution from the US Government to the IAEA, and external consultants, working under contract with the IAEA. The DECADES Tools User's Manual is published as part of a series of technical reports and documents prepared in the framework of the DECADES project. The Joint Steering Committee for the project hopes that these software tools will contribute to the process of strengthening and improving the capabilities for the design and implementation of sustainable strategies in the power sector, in particular in developing countries and countries in transition to market economies

  7. STATE ACID RAIN RESEARCH AND SCREENING SYSTEM - VERSION 1.0 USER'S MANUAL

    Science.gov (United States)

    The report is a user's manual that describes Version 1.0 of EPA's STate Acid Rain Research and Screening System (STARRSS), developed to assist utility regulatory commissions in reviewing utility acid rain compliance plans. It is a screening tool that is based on scenario analysis...

  8. Water Security Toolkit User Manual Version 1.2.

    Energy Technology Data Exchange (ETDEWEB)

    Klise, Katherine A.; Siirola, John Daniel; Hart, David; Hart, William Eugene; Phillips, Cynthia Ann; Haxton, Terranna; Murray, Regan; Janke, Robert; Taxon, Thomas; Laird, Carl; Seth, Arpan; Hackebeil, Gabriel; McGee, Shawn; Mann, Angelica

    2014-08-01

    The Water Security Toolkit (WST) is a suite of open source software tools that can be used by water utilities to create response strategies to reduce the impact of contamination in a water distribution network . WST includes hydraulic and water quality modeling software , optimizati on methodologies , and visualization tools to identify: (1) sensor locations to detect contamination, (2) locations in the network in which the contamination was introduced, (3) hydrants to remove contaminated water from the distribution system, (4) locations in the network to inject decontamination agents to inactivate, remove, or destroy contaminants, (5) locations in the network to take grab sample s to help identify the source of contamination and (6) valves to close in order to isolate contaminate d areas of the network. This user manual describes the different components of WST , along w ith examples and case studies. License Notice The Water Security Toolkit (WST) v.1.2 Copyright c 2012 Sandia Corporation. Under the terms of Contract DE-AC04-94AL85000, there is a non-exclusive license for use of this work by or on behalf of the U.S. government. This software is distributed under the Revised BSD License (see below). In addition, WST leverages a variety of third-party software packages, which have separate licensing policies: Acro Revised BSD License argparse Python Software Foundation License Boost Boost Software License Coopr Revised BSD License Coverage BSD License Distribute Python Software Foundation License / Zope Public License EPANET Public Domain EPANET-ERD Revised BSD License EPANET-MSX GNU Lesser General Public License (LGPL) v.3 gcovr Revised BSD License GRASP AT&T Commercial License for noncommercial use; includes randomsample and sideconstraints executable files LZMA SDK Public Domain nose GNU Lesser General Public License (LGPL) v.2.1 ordereddict MIT License pip MIT License PLY BSD License PyEPANET Revised BSD License Pyro MIT License PyUtilib Revised BSD License Py

  9. Babcock and Wilcox version of PDQ07: user's manual

    International Nuclear Information System (INIS)

    Hassan, H.H.; Wittkopf, W.A.; Mullan, W.H.

    1977-01-01

    The Babcock and Wilcox version of PDQ07 solves the neutron diffusion depletion problem in one, two, and three dimensions and in up to five lethargy groups. Adjoint and boundary value calculations may also be performed. Geometries available are rectangular, cylindrical, spherical, and hexagonal. Special capabilities of the code include thermal-hydraulic feedback with subcooled boiling effects, boron iteration, rod bank placement, automatic partial rod movement, and flux synthesis. Time-independent group diffusion equations are solved by Gaussian elimination in one dimension, single-line cyclic Chebyshev semi-iterative technique in two dimensions, and a modified block Gauss-Siedel in three dimensions. Diffusion coefficients, macroscopic data, and depletion use a modified HARMONY system. Thermal feedback effects use an iterative approach based on relative power density in the core. Flux synthesis uses two-dimensional trial functions to solve three-dimensional problems

  10. MOVIE.LASL version 1.0 user's manual

    International Nuclear Information System (INIS)

    Brown, B.E.

    1976-09-01

    MOVIE.LASL is an interactive Fortran program for display and animation both of finite-element models and of the results of their analysis. The program runs on the Los Alamos Scientific Laboratory's LTSS system. The user may manipulate the model (rotate, translate, zoom in, etc.), specify colors for the background and the different element groups, and select various display devices. Both line drawings and continuous-tone color images can be produced. Single frames or animated movie sequences are also available and can be displayed on any of the output devices

  11. System cost model user's manual, version 1.2

    International Nuclear Information System (INIS)

    Shropshire, D.

    1995-06-01

    The System Cost Model (SCM) was developed by Lockheed Martin Idaho Technologies in Idaho Falls, Idaho and MK-Environmental Services in San Francisco, California to support the Baseline Environmental Management Report sensitivity analysis for the U.S. Department of Energy (DOE). The SCM serves the needs of the entire DOE complex for treatment, storage, and disposal (TSD) of mixed low-level, low-level, and transuranic waste. The model can be used to evaluate total complex costs based on various configuration options or to evaluate site-specific options. The site-specific cost estimates are based on generic assumptions such as waste loads and densities, treatment processing schemes, existing facilities capacities and functions, storage and disposal requirements, schedules, and cost factors. The SCM allows customization of the data for detailed site-specific estimates. There are approximately forty TSD module designs that have been further customized to account for design differences for nonalpha, alpha, remote-handled, and transuranic wastes. The SCM generates cost profiles based on the model default parameters or customized user-defined input and also generates costs for transporting waste from generators to TSD sites

  12. Manufactured Home Energy Audit (MHEA)Users Manual (Version 7)

    Energy Technology Data Exchange (ETDEWEB)

    Gettings, M.B.

    2003-01-27

    The Manufactured Home Energy Audit (MHEA) is a software tool that predicts manufactured home energy consumption and recommends weatherization retrofit measures. It was developed to assist local weatherization agencies working with the U.S. Department of Energy (DOE) Weatherization Assistance Program. Whether new or experienced, employed within or outside the Weatherization Assistance Program, all users can benefit from incorporating MHEA into their manufactured home weatherization programs. DOE anticipates that the state weatherization assistance programs that incorporate MHEA into their programs will find significant growth in the energy and cost savings achieved from manufactured home weatherization. The easy-to-use MHEA uses a relatively standard Windows graphical interface for entering simple inputs and provides understandable, usable results. The user enters information about the manufactured home construction, heating equipment, cooling equipment appliances, and weather site. MHEA then calculates annual energy consumption using a simplified building energy analysis technique. Weatherization retrofit measures are evaluated based on the predicted energy savings after installation of the measure, the measure cost, and the measure life. Finally, MHEA recommends retrofit measures that are energy and cost effective for the particular home being evaluated. MHEA evaluates each manufactured home individually and takes into account local weather conditions, retrofit measure costs, and fuel costs. The recommended package of weatherization retrofit measures is tailored to the home being evaluated. More traditional techniques apply the same package of retrofit measures to all manufactured homes, often the same set of measures that are installed into site-built homes. Effective manufactured home weatherization can be achieved only by installing measures developed specifically for manufactured homes. The unique manufactured home construction characteristics require that

  13. In-vessel source term analysis code TRACER version 2.3. User's manual

    International Nuclear Information System (INIS)

    Toyohara, Daisuke; Ohno, Shuji; Hamada, Hirotsugu; Miyahara, Shinya

    2005-01-01

    A computer code TRACER (Transport Phenomena of Radionuclides for Accident Consequence Evaluation of Reactor) version 2.3 has been developed to evaluate species and quantities of fission products (FPs) released into cover gas during a fuel pin failure accident in an LMFBR. The TRACER version 2.3 includes new or modified models shown below. a) Both model: a new model for FPs release from fuel. b) Modified model for FPs transfer from fuel to bubbles or sodium coolant. c) Modified model for bubbles dynamics in coolant. Computational models, input data and output data of the TRACER version 2.3 are described in this user's manual. (author)

  14. User Manual for the NASA Glenn Ice Accretion Code LEWICE: Version 2.0

    Science.gov (United States)

    Wright, William B.

    1999-01-01

    A research project is underway at NASA Glenn to produce a computer code which can accurately predict ice growth under a wide range of meteorological conditions for any aircraft surface. This report will present a description of the code inputs and outputs from version 2.0 of this code, which is called LEWICE. This version differs from previous releases due to its robustness and its ability to reproduce results accurately for different spacing and time step criteria across computing platform. It also differs in the extensive effort undertaken to compare the results against the database of ice shapes which have been generated in the NASA Glenn Icing Research Tunnel (IRT) 1. This report will only describe the features of the code related to the use of the program. The report will not describe the inner working of the code or the physical models used. This information is available in the form of several unpublished documents which will be collectively referred to as a Programmers Manual for LEWICE 2 in this report. These reports are intended as an update/replacement for all previous user manuals of LEWICE. In addition to describing the changes and improvements made for this version, information from previous manuals may be duplicated so that the user will not need to consult previous manuals to use this code.

  15. User Manual for the NASA Glenn Ice Accretion Code LEWICE. Version 2.2.2

    Science.gov (United States)

    Wright, William B.

    2002-01-01

    A research project is underway at NASA Glenn to produce a computer code which can accurately predict ice growth under a wide range of meteorological conditions for any aircraft surface. This report will present a description of the code inputs and outputs from version 2.2.2 of this code, which is called LEWICE. This version differs from release 2.0 due to the addition of advanced thermal analysis capabilities for de-icing and anti-icing applications using electrothermal heaters or bleed air applications. An extensive effort was also undertaken to compare the results against the database of electrothermal results which have been generated in the NASA Glenn Icing Research Tunnel (IRT) as was performed for the validation effort for version 2.0. This report will primarily describe the features of the software related to the use of the program. Appendix A of this report has been included to list some of the inner workings of the software or the physical models used. This information is also available in the form of several unpublished documents internal to NASA. This report is intended as a replacement for all previous user manuals of LEWICE. In addition to describing the changes and improvements made for this version, information from previous manuals may be duplicated so that the user will not need to consult previous manuals to use this code.

  16. The Weatherization Assistant User's Manual (Version 8.9)

    Energy Technology Data Exchange (ETDEWEB)

    Gettings, Michael B. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Malhotra, Mini [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Ternes, Mark P. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

    2015-01-01

    The Weatherization Assistant is a Windows-based energy audit software tool that was developed by Oak Ridge National Laboratory (ORNL) to help states and their local weatherization agencies implement the U.S. Department of Energy (DOE) Weatherization Assistance Program. The Weatherization Assistant is an umbrella program for two individual energy audits or measure selection programs: the National Energy Audit Tool (NEAT) for site-built single-family homes and the Manufactured Home Energy Audit (MHEA) for mobile homes. The Weatherization Assistant User's Manual documents the operation of the user interface for Version 8.9 of the software. This includes how to install and setup the software, navigate through the program, and initiate an energy audit. All of the user interface forms associated with the software and the data fields on these forms are described in detail. The manual is intended to be a training manual for new users of the Weatherization Assistant and as a reference manual for experienced users.

  17. Simion 3D Version 6.0 User`s Manual

    Energy Technology Data Exchange (ETDEWEB)

    Dahl, D.A.

    1995-11-01

    The original SIMION was an electrostatic lens analysis and design program developed by D.C. McGilvery at Latrobe University, Bundoora Victoria, Australia, 1977. SIMION for the PC, developed at the Idaho National Engineering Laboratory, shares little more than its name with the original McGilvery version. INEL`s fifth major SIMION release, version 6.0, represents a quantum improvement over previous versions. This C based program can model complex problems using an ion optics workbench that can hold up to 200 2D and/or 3D electrostatic/magnetic potential arrays. Arrays can have up to 10,000,000 points. SIMION 3D`s 32 bit virtual Graphics User Interface provides a highly interactive advanced user environment. All potential arrays are visualized as 3D objects that the user can cut away to inspect ion trajectories and potential energy surfaces. User programs have been greatly extended in versatility and power. A new geometry file option supports the definition of highly complex array geometry. Extensive algorithm modifications have dramatically improved this version`s computational speed and accuracy.

  18. SERA: Simulation Environment for Radiotherapy Applications - Users Manual Version 1CO

    Energy Technology Data Exchange (ETDEWEB)

    Venhuizen, James Robert; Wessol, Daniel Edward; Wemple, Charles Alan; Wheeler, Floyd J; Harkin, G. J.; Frandsen, M. W.; Albright, C. L.; Cohen, M.T.; Rossmeier, M.; Cogliati, J.J.

    2002-06-01

    This document is the user manual for the Simulation Environment for Radiotherapy Applications (SERA) software program developed for boron-neutron capture therapy (BNCT) patient treatment planning by researchers at the Idaho National Engineering and Environmental Laboratory (INEEL) and students and faculty at Montana State University (MSU) Computer Science Department. This manual corresponds to the final release of the program, Version 1C0, developed to run under the RedHat Linux Operating System (version 7.2 or newer) or the Solaris™ Operating System (version 2.6 or newer). SERA is a suite of command line or interactively launched software modules, including graphical, geometric reconstruction, and execution interface modules for developing BNCT treatment plans. The program allows the user to develop geometric models of the patient as derived from Computed Tomography (CT) and Magnetic Resonance Imaging (MRI) images, perform dose computation for these geometric models, and display the computed doses on overlays of the original images as three dimensional representations. This manual provides a guide to the practical use of SERA, but is not an exhaustive treatment of each feature of the code.

  19. SERA: Simulation Environment for Radiotherapy Applications - Users Manual Version 1CO

    International Nuclear Information System (INIS)

    Venhuizen, James Robert; Wessol, Daniel Edward; Wemple, Charles Alan; Wheeler, Floyd J; Harkin, G. J.; Frandsen, M. W.; Albright, C. L.; Cohen, M.T.; Rossmeier, M.; Cogliati, J.J.

    2002-01-01

    This document is the user manual for the Simulation Environment for Radiotherapy Applications (SERA) software program developed for boron-neutron capture therapy (BNCT) patient treatment planning by researchers at the Idaho National Engineering and Environmental Laboratory (INEEL) and students and faculty at Montana State University (MSU) Computer Science Department. This manual corresponds to the final release of the program, Version 1C0, developed to run under the RedHat Linux Operating System (version 7.2 or newer) or the Solaris Operating System (version 2.6 or newer). SERA is a suite of command line or interactively launched software modules, including graphical, geometric reconstruction, and execution interface modules for developing BNCT treatment plans. The program allows the user to develop geometric models of the patient as derived from Computed Tomography (CT) and Magnetic Resonance Imaging (MRI) images, perform dose computation for these geometric models, and display the computed doses on overlays of the original images as three dimensional representations. This manual provides a guide to the practical use of SERA, but is not an exhaustive treatment of each feature of the code

  20. LLCEDATA and LLCECALC for Windows version 1.0, Volume 1: User`s manual

    Energy Technology Data Exchange (ETDEWEB)

    McFadden, J.G.

    1998-09-04

    LLCEDATA and LLCECALC for Windows are user-friendly computer software programs that work together to determine the proper waste designation, handling, and disposition requirements for Long Length Contaminated Equipment (LLCE). LLCEDATA reads from a variety of data bases to produce an equipment data file (EDF) that represents a snapshot of both the LLCE and the tank it originates from. LLCECALC reads the EDF and a gamma assay (AV2) file that is produced by the Flexible Receiver Gamma Energy Analysis System. LLCECALC performs corrections to the AV2 file as it is being read and characterizes the LLCE. Both programs produce a variety of reports, including a characterization report and a status report. The status report documents each action taken by the user, LLCEDATA, and LLCECALC. Documentation for LLCEDATA and LLCECALC for Windows is available in three volumes. Volume 1 is a user`s manual, which is intended as a quick reference for both LLCEDATA and LLCECALC. Volume 2 is a technical manual, and Volume 3 is a software verification and validation document.

  1. Apparel Research Network (ARN); Apparel Order Processing Module (AOPM): Field User Manual, Version 1

    Science.gov (United States)

    1997-09-30

    changes. Cancel Button Closes the Site Information Screen, abandoning changes. APPAREL ORDER PROCESSING MODULE FIELD USER MANUAL Ordering Official...on the Ordering Official Information Screen. APPAREL ORDER PROCESSING MODULE FIELD USER MANUAL Ordering Official Information Screen (Jjj

  2. Risk Analysis and Decision-Making Software Package (1997 Version) User Manual

    Energy Technology Data Exchange (ETDEWEB)

    Chung, F.T.H.

    1999-02-11

    This manual provides instructions for using the U.S. Department of Energy's (DOE) risk analysis and decision making software (1997 version) developed at BDM Petroleum Technologies by BDM-Oklahoma, Inc. for DOE, under contract No. DE-AC22-94PC91OO8. This software provides petroleum producers with a simple, handy tool for exploration and production risk analysis and decision-making. It collects useful risk analysis tools in one package so that users do not have to use several programs separately. The software is simple to use, but still provides many functions. The 1997 version of the software package includes the following tools: (1) Investment risk (Gambler's ruin) analysis; (2) Monte Carlo simulation; (3) Best fit for distribution functions; (4) Sample and rank correlation; (5) Enhanced oil recovery method screening; and (6) artificial neural network. This software package is subject to change. Suggestions and comments from users are welcome and will be considered for future modifications and enhancements of the software. Please check the opening screen of the software for the current contact information. In the future, more tools will be added to this software package. This manual includes instructions on how to use the software but does not attempt to fully explain the theory and algorithms used to create it.

  3. NetMOD Version 2.0 User?s Manual.

    Energy Technology Data Exchange (ETDEWEB)

    Merchant, Bion J. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2015-10-01

    NetMOD ( Net work M onitoring for O ptimal D etection) is a Java-based software package for conducting simulation of seismic, hydracoustic, and infrasonic networks. Specifically, NetMOD simulates the detection capabilities of monitoring networks. Network simulations have long been used to study network resilience to station outages and to determine where additional stations are needed to reduce monitoring thresholds. NetMOD makes use of geophysical models to determine the source characteristics, signal attenuation along the path between the source and station, and the performance and noise properties of the station. These geophysical models are combined to simulate the relative amplitudes of signal and noise that are observed at each of the stations. From these signal-to-noise ratios (SNR), the probability of detection can be computed given a detection threshold. This manual describes how to configure and operate NetMOD to perform detection simulations. In addition, NetMOD is distributed with simulation datasets for the Comprehensive Nuclear-Test-Ban Treaty Organization (CTBTO) International Monitoring System (IMS) seismic, hydroacoustic, and infrasonic networks for the purpose of demonstrating NetMOD's capabilities and providing user training. The tutorial sections of this manual use this dataset when describing how to perform the steps involved when running a simulation. ACKNOWLEDGEMENTS We would like to thank the reviewers of this document for their contributions.

  4. Radiological Safety Analysis Computer (RSAC) Program Version 7.0 Users Manual

    International Nuclear Information System (INIS)

    Schrader, Bradley J.

    2009-01-01

    The Radiological Safety Analysis Computer (RSAC) Program Version 7.0 (RSAC-7) is the newest version of the RSAC legacy code. It calculates the consequences of a release of radionuclides to the atmosphere. A user can generate a fission product inventory from either reactor operating history or a nuclear criticality event. RSAC-7 models the effects of high-efficiency particulate air filters or other cleanup systems and calculates the decay and ingrowth during transport through processes, facilities, and the environment. Doses are calculated for inhalation, air immersion, ground surface, ingestion, and cloud gamma pathways. RSAC-7 can be used as a tool to evaluate accident conditions in emergency response scenarios, radiological sabotage events and to evaluate safety basis accident consequences. This users manual contains the mathematical models and operating instructions for RSAC-7. Instructions, screens, and examples are provided to guide the user through the functions provided by RSAC-7. This program was designed for users who are familiar with radiological dose assessment methods

  5. Users' Manual for Research: Translating Head Start Findings Into Action (Expanded Notebook Version).

    Science.gov (United States)

    Grotberg, Edith H.; Fowler, Austine

    This users' manual, intended for use with a Project Head Start teacher training notebook, describes the purpose, development and field testing of the training materials and suggests procedures for using the notebook as a resource in teacher training sessions. The training notebook to which the users' manual refers is based on 11 questions in the…

  6. Tripoli-3: monte Carlo transport code for neutral particles - version 3.5 - users manual

    International Nuclear Information System (INIS)

    Vergnaud, Th.; Nimal, J.C.; Chiron, M.

    2001-01-01

    The TRIPOLI-3 code applies the Monte Carlo method to neutron, gamma-ray and coupled neutron and gamma-ray transport calculations in three-dimensional geometries, either in steady-state conditions or having a time dependence. It can be used to study problems where there is a high flux attenuation between the source zone and the result zone (studies of shielding configurations or source driven sub-critical systems, with fission being taken into account), as well as problems where there is a low flux attenuation (neutronic calculations -- in a fuel lattice cell, for example -- where fission is taken into account, usually with the calculation on the effective multiplication factor, fine structure studies, numerical experiments to investigate methods approximations, etc). TRIPOLI-3 has been operational since 1995 and is the version of the TRIPOLI code that follows on from TRIPOLI-2; it can be used on SUN, RISC600 and HP workstations and on PC using the Linux or Windows/NT operating systems. The code uses nuclear data libraries generated using the THEMIS/NJOY system. The current libraries were derived from ENDF/B6 and JEF2. There is also a response function library based on a number of evaluations, notably the dosimetry libraries IRDF/85, IRDF/90 and also evaluations from JEF2. The treatment of particle transport is the same in version 3.5 as in version 3.4 of the TRIPOLI code; but the version 3.5 is more convenient for preparing the input data and for reading the output. The french version of the user's manual exists. (authors)

  7. The bidimensional neutron transport code TWOTRAN-GG. Users manual and input data TWOTRAN-TRACA version

    International Nuclear Information System (INIS)

    Ahnert, C.; Aragones, J. M.

    1981-01-01

    This Is a users manual of the neutron transport code TWOTRAN-TRACA, which is a version of the original TWOTRAN-GG from the Los Alamos Laboratory, with some modifications made at JEN. A detailed input data description is given as well as the new modifications developed at JEN. (Author) 8 refs

  8. The bidimensional neutron transport code Twotran-GG. User's manual and input data. Twotran-Traca version

    International Nuclear Information System (INIS)

    Ahnert, C.; Aragones, J.M.

    1981-01-01

    A user's manual of the neutron transport code Twotran-Traca is presented; it is a version of the original Twotran-GG from the Los Alamos Laboratory, with some modifications made at J.E.N., Spain. A detailed input data description is given as well as the new modifications developped at J.E.N. (author) [es

  9. User's Manual for PCSMS (Parallel Complex Sparse Matrix Solver). Version 1.

    Science.gov (United States)

    Reddy, C. J.

    2000-01-01

    PCSMS (Parallel Complex Sparse Matrix Solver) is a computer code written to make use of the existing real sparse direct solvers to solve complex, sparse matrix linear equations. PCSMS converts complex matrices into real matrices and use real, sparse direct matrix solvers to factor and solve the real matrices. The solution vector is reconverted to complex numbers. Though, this utility is written for Silicon Graphics (SGI) real sparse matrix solution routines, it is general in nature and can be easily modified to work with any real sparse matrix solver. The User's Manual is written to make the user acquainted with the installation and operation of the code. Driver routines are given to aid the users to integrate PCSMS routines in their own codes.

  10. IMAGE User Manual

    Energy Technology Data Exchange (ETDEWEB)

    Stehfest, E; De Waal, L; Oostenrijk, R.

    2010-09-15

    This user manual contains the basic information for running the simulation model IMAGE ('Integrated Model to Assess the Global Environment') of PBL. The motivation for this report was a substantial restructuring of the source code for IMAGE version 2.5. The document gives concise content information about the submodels, tells the user how to install the program, describes the directory structure of the run environment, shows how scenarios have to be prepared and run, and gives insight in the restart functionality.

  11. LLCEDATA and LLCECALC for Windows version 1.0, Volume 1: User's manual

    International Nuclear Information System (INIS)

    McFadden, J.G.

    1998-01-01

    LLCEDATA and LLCECALC for Windows are user-friendly computer software programs that work together to determine the proper waste designation, handling, and disposition requirements for Long Length Contaminated Equipment (LLCE). LLCEDATA reads from a variety of data bases to produce an equipment data file (EDF) that represents a snapshot of both the LLCE and the tank it originates from. LLCECALC reads the EDF and a gamma assay (AV2) file that is produced by the Flexible Receiver Gamma Energy Analysis System. LLCECALC performs corrections to the AV2 file as it is being read and characterizes the LLCE. Both programs produce a variety of reports, including a characterization report and a status report. The status report documents each action taken by the user, LLCEDATA, and LLCECALC. Documentation for LLCEDATA and LLCECALC for Windows is available in three volumes. Volume 1 is a user's manual, which is intended as a quick reference for both LLCEDATA and LLCECALC. Volume 2 is a technical manual, and Volume 3 is a software verification and validation document

  12. Radiometer Calibration and Characterization (RCC) User's Manual: Windows Version 4.0

    Energy Technology Data Exchange (ETDEWEB)

    Andreas, Afshin M. [National Renewable Energy Lab. (NREL), Golden, CO (United States); Wilcox, Stephen M. [National Renewable Energy Lab. (NREL), Golden, CO (United States)

    2016-02-29

    The Radiometer Calibration and Characterization (RCC) software is a data acquisition and data archival system for performing Broadband Outdoor Radiometer Calibrations (BORCAL). RCC provides a unique method of calibrating broadband atmospheric longwave and solar shortwave radiometers using techniques that reduce measurement uncertainty and better characterize a radiometer's response profile. The RCC software automatically monitors and controls many of the components that contribute to uncertainty in an instrument's responsivity. This is a user's manual and guide to the RCC software.

  13. Core2D. A code for non-isothermal water flow and reactive solute transport. Users manual version 2

    International Nuclear Information System (INIS)

    Samper, J.; Juncosa, R.; Delgado, J.; Montenegro, L.

    2000-01-01

    Understanding natural groundwater quality patterns, quantifying groundwater pollution and assessing the effects of waste disposal, require modeling tools accounting for water flow, and transport of heat and dissolved species as well as their complex interactions with solid and gases phases. This report contains the users manual of CORE ''2D Version V.2.0, a COde for modeling water flow (saturated and unsaturated), heat transport and multicomponent Reactive solute transport under both local chemical equilibrium and kinetic conditions. it is an updated and improved version of CORE-LE-2D V0 (Samper et al., 1988) which in turns is an extended version of TRANQUI, a previous reactive transport code (ENRESA, 1995). All these codes were developed within the context of Research Projects funded by ENRESA and the European Commission. (Author)

  14. Core 2D. A code for non-isothermal water flow and reactive solute transport. Users manual version 2

    Energy Technology Data Exchange (ETDEWEB)

    Samper, J; Juncosa, R; Delgado, J; Montenegro, L [Universidad de A Coruna (Spain)

    2000-07-01

    Understanding natural groundwater quality patterns, quantifying groundwater pollution and assessing the effects of waste disposal, require modeling tools accounting for water flow, and transport of heat and dissolved species as well as their complex interactions with solid and gases phases. This report contains the users manual of CORE ''2D Version V.2.0, a COde for modeling water flow (saturated and unsaturated), heat transport and multicomponent Reactive solute transport under both local chemical equilibrium and kinetic conditions. it is an updated and improved version of CORE-LE-2D V0 (Samper et al., 1988) which in turns is an extended version of TRANQUI, a previous reactive transport code (ENRESA, 1995). All these codes were developed within the context of Research Projects funded by ENRESA and the European Commission. (Author)

  15. Core 2D. A code for non-isothermal water flow and reactive solute transport. Users manual version 2

    Energy Technology Data Exchange (ETDEWEB)

    Samper, J.; Juncosa, R.; Delgado, J.; Montenegro, L. [Universidad de A Coruna (Spain)

    2000-07-01

    Understanding natural groundwater quality patterns, quantifying groundwater pollution and assessing the effects of waste disposal, require modeling tools accounting for water flow, and transport of heat and dissolved species as well as their complex interactions with solid and gases phases. This report contains the users manual of CORE ''2D Version V.2.0, a COde for modeling water flow (saturated and unsaturated), heat transport and multicomponent Reactive solute transport under both local chemical equilibrium and kinetic conditions. it is an updated and improved version of CORE-LE-2D V0 (Samper et al., 1988) which in turns is an extended version of TRANQUI, a previous reactive transport code (ENRESA, 1995). All these codes were developed within the context of Research Projects funded by ENRESA and the European Commission. (Author)

  16. M3 User's Manual. Version 3.0

    Energy Technology Data Exchange (ETDEWEB)

    Laaksoharju, Marcus (Geopoint AB, Sollentuna (Sweden)); Skaarman, Erik (Abscondo Utveckling, Bromma (Sweden)); Gomez, Javier B. (Univ. of Zaragoza (Spain). Geochemical modelling Group); Gurban, Ioana (3D Terra (Canada))

    2006-07-15

    This report describes the Multivariate Mixing and Mass balance calculations (M3). This new method and computer code is developed to trace the mixing and reaction processes in the groundwater. The aim of the M3 concept is to decode the often hidden and complex information gathered in the groundwater analytical data. The manual presents shortly the theory and practice behind the M3 method. The M3 computer code is also presented and emphasis is put on the reference manual. This includes detailed reference to the M3 program's abilities and limitations, installation procedures and all functions and operations that the program can perform. It also describes sample cases of how the program is used to analyse a test data set. This guide is part of the Help Files distributed together with M3. Two accompanying reports cover other aspects: - Concepts, Methods, and Mathematical Formulation, gives a complete description of the mathematical framework of M3 and introduces concepts and methods useful for the end user. - M3 version 3.0: Verification and Validation, gathers a collection of validation and verification exercises, designed to test each part of M3 code and to build confidence in its methodology. The M3 method has been tested and modified over several years. The development work has been supported by the Swedish Nuclear Fuel and Waste Management Company (SKB). The main test site for the model was the underground Aespoe Hard Rock Laboratory (HRL). The examples used in this manual are from a Aespoe international groundwater modelling co-operation project where one of the tools used was M3. The M3 concept has been applied on the data from SKB's site investigation programme and in data from Canada, Japan, Jordan, Gabon and Finland. The groundwater composition is a result of mixing processes and water-rock interaction. Standard groundwater models based on thermodynamic laws may not be applicable in a normal temperature groundwater system where equilibrium with many

  17. User's Manual for RESRAD-OFFSITE Version 2.

    Energy Technology Data Exchange (ETDEWEB)

    Yu, C.; Gnanapragasam, E.; Biwer, B. M.; Kamboj, S.; Cheng, J. -J.; Klett, T.; LePoire, D.; Zielen, A. J.; Chen, S. Y.; Williams, W. A.; Wallo, A.; Domotor, S.; Mo, T.; Schwartzman, A.; Environmental Science Division; DOE; NRC

    2007-09-05

    The RESRAD-OFFSITE code is an extension of the RESRAD (onsite) code, which has been widely used for calculating doses and risks from exposure to radioactively contaminated soils. The development of RESRAD-OFFSITE started more than 10 years ago, but new models and methodologies have been developed, tested, and incorporated since then. Some of the new models have been benchmarked against other independently developed (international) models. The databases used have also expanded to include all the radionuclides (more than 830) contained in the International Commission on Radiological Protection (ICRP) 38 database. This manual provides detailed information on the design and application of the RESRAD-OFFSITE code. It describes in detail the new models used in the code, such as the three-dimensional dispersion groundwater flow and radionuclide transport model, the Gaussian plume model for atmospheric dispersion, and the deposition model used to estimate the accumulation of radionuclides in offsite locations and in foods. Potential exposure pathways and exposure scenarios that can be modeled by the RESRAD-OFFSITE code are also discussed. A user's guide is included in Appendix A of this manual. The default parameter values and parameter distributions are presented in Appendix B, along with a discussion on the statistical distributions for probabilistic analysis. A detailed discussion on how to reduce run time, especially when conducting probabilistic (uncertainty) analysis, is presented in Appendix C of this manual.

  18. Model for Analysis of the Energy Demand (MAED) users' manual for version MAED-1

    International Nuclear Information System (INIS)

    1986-09-01

    This manual is organized in two major parts. The first part includes eight main sections describing how to use the MAED-1 computer program and the second one consists of five appendices giving some additional information about the program. Concerning the main sections of the manual, Section 1 gives a summary description and some background information about the MAED-1 model. Section 2 extends the description of the MAED-1 model in more detail. Section 3 introduces some concepts, mainly related to the computer requirements imposed by the program, that are used throughout this document. Sections 4 to 7 describe how to execute each of the various programs (or modules) of the MAED-1 package. The description for each module shows the user how to prepare the control and data cards needed to execute the module and how to interpret the printed output produced. Section 8 recapitulates about the use of MAED-1 for carrying out energy and electricity planning studies, describes the several phases normally involved in this type of study and provides the user with practical hints about the most important aspects that need to be verified at each phase while executing the various MAED modules

  19. The bidimensional neutron transport code TWOTRAN-GG. Users manual and input data TWOTRAN-TRACA version; El codigo de transporte bidimensional TWOTRAN-GG. Manual de usuario y datos de entrada version TWOTRAN-TRACA

    Energy Technology Data Exchange (ETDEWEB)

    Ahnert, C; Aragones, J M

    1981-07-01

    This Is a users manual of the neutron transport code TWOTRAN-TRACA, which is a version of the original TWOTRAN-GG from the Los Alamos Laboratory, with some modifications made at JEN. A detailed input data description is given as well as the new modifications developed at JEN. (Author) 8 refs.

  20. Version I of the users manual for the Tuff Data Base Interface

    International Nuclear Information System (INIS)

    Langkopf, B.S.; Satter, B.J.; Welch, E.P.

    1985-04-01

    The Nevada Nuclear Waste Storage Investigations (NNWSI) project, managed by the Nevada Operations Office of the US Department of Energy, is investigating the feasibility of locating a repository at Yucca Mountain on and adjacent to the Nevada Test Site (NTS) in southern Nevada. A part of this investigation includes obtaining physical properties from laboratory tests on samples from Yucca Mountain and field tests of the in situ tuffs at Yucca Mountain. A computerized data base has been developed to store this data in a centralized location. The data base is stored on the Cyber 170/855 computer at Sandia using the System 2000 Data Base Management software. A user-friendly interface, the Tuff Data Base Interface, is being developed to allow NNWSI participants to retrieve information from the Tuff Data Base directly. The Interface gives NNWSI users a great deal of flexibility in retrieving portions of the Data Base. This report is an interim users manual for the Tuff Data Base Interface, as of August 1984. It gives basic instructions on accessing the Sandia computing system and explains the Interface on a question-by-question basis

  1. NetMOD version 1.0 user's manual

    Energy Technology Data Exchange (ETDEWEB)

    Merchant, Bion John [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2014-01-01

    NetMOD (Network Monitoring for Optimal Detection) is a Java-based software package for conducting simulation of seismic networks. Specifically, NetMOD simulates the detection capabilities of seismic monitoring networks. Network simulations have long been used to study network resilience to station outages and to determine where additional stations are needed to reduce monitoring thresholds. NetMOD makes use of geophysical models to determine the source characteristics, signal attenuation along the path between the source and station, and the performance and noise properties of the station. These geophysical models are combined to simulate the relative amplitudes of signal and noise that are observed at each of the stations. From these signal-to-noise ratios (SNR), the probability of detection can be computed given a detection threshold. This manual describes how to configure and operate NetMOD to perform seismic detection simulations. In addition, NetMOD is distributed with a simulation dataset for the Comprehensive Nuclear-Test-Ban Treaty Organization (CTBTO) International Monitoring System (IMS) seismic network for the purpose of demonstrating NetMOD's capabilities and providing user training. The tutorial sections of this manual use this dataset when describing how to perform the steps involved when running a simulation.

  2. FISPACT 97: user manual

    International Nuclear Information System (INIS)

    Forrest, R.A.; Sublet, J.-Ch.

    1997-05-01

    FISPACT is the inventory code included in the European Activation System (EASY). A new version of FISPACT: FISPACT-97 has been developed and this report is the User manual for the code. It explains the use of all the code words used in the input file to specify a FISPACT run and describes how all the data files are connected. A series of appendices cover the working of the code and the physical and mathematical details. Background information on the data files and extensive examples of input files suitable for various applications are included. (Author)

  3. Percept User Manual.

    Energy Technology Data Exchange (ETDEWEB)

    Carnes, Brian [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Kennon, Stephen Ray [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2017-05-01

    This document is the main user guide for the Sierra/Percept capabilities including the mesh_adapt and mesh_transfer tools. Basic capabilities for uniform mesh refinement (UMR) and mesh transfers are discussed. Examples are used to provide illustration. Future versions of this manual will include more advanced features such as geometry and mesh smoothing. Additionally, all the options for the mesh_adapt code will be described in detail. Capabilities for local adaptivity in the context of offline adaptivity will also be included. This page intentionally left blank.

  4. Neutron dosimetry system SAIPS: Manual for users and programmers (Version 87-02)

    International Nuclear Information System (INIS)

    Berzonis, M.A.; Bondars, Kh.Ya.; Niedritis, A.M.

    1988-07-01

    SAIPS is a system used for neutron dosimetry by foil activation, containing a package of programs and a data base of neutron activation cross-sections. A description is given of the SAIPS indexed procedures and users language, which are designed for producing input data for programs unfolding neutron spectra from reaction rate measurements, for carrying out calculations and processing and comparing the results obtained, for utilizing the additional capabilities of the system, and for setting up a working version of the system from the magnetic tapes used for distribution. A description is given of the logical structure of the data sets containing the libraries of neutron cross-section and a priori spectra and also the libraries of calculated spectra. The annexes give examples of SAIPS in use, of the contents of the a priori spectra and neutron cross-section libraries, and of the contents of the SAIPS distribution tapes. SAIPS contains programs in PL/1 (opt), FORTRAN IV(H) and ASSEMBLER. 25 refs

  5. Social values for ecosystem services (SolVES): Documentation and user manual, version 2.0

    Science.gov (United States)

    Sherrouse, Benson C.; Semmens, Darius J.

    2012-01-01

    In response to the need for incorporating quantified and spatially explicit measures of social values into ecosystem services assessments, the Rocky Mountain Geographic Science Center (RMGSC), in collaboration with Colorado State University, developed a geographic information system (GIS) application, Social Values for Ecosystem Services (SolVES). With version 2.0 (SolVES 2.0), RMGSC has improved and extended the functionality of SolVES, which was designed to assess, map, and quantify the perceived social values of ecosystem services. Social values such as aesthetics, biodiversity, and recreation can be evaluated for various stakeholder groups as distinguished by their attitudes and preferences regarding public uses, such as motorized recreation and logging. As with the previous version, SolVES 2.0 derives a quantitative, 10-point, social-values metric, the Value Index, from a combination of spatial and nonspatial responses to public attitude and preference surveys and calculates metrics characterizing the underlying environment, such as average distance to water and dominant landcover. Additionally, SolVES 2.0 integrates Maxent maximum entropy modeling software to generate more complete social value maps and to produce robust statistical models describing the relationship between the social values maps and explanatory environmental variables. The performance of these models can be evaluated for a primary study area, as well as for similar areas where primary survey data are not available but where social value mapping could potentially be completed using value-transfer methodology. SolVES 2.0 also introduces the flexibility for users to define their own social values and public uses, model any number and type of environmental variable, and modify the spatial resolution of analysis. With these enhancements, SolVES 2.0 provides an improved public domain tool for decisionmakers and researchers to evaluate the social values of ecosystem services and to facilitate

  6. Accelerator System Model (ASM) user manual with physics and engineering model documentation. ASM version 1.0

    International Nuclear Information System (INIS)

    1993-07-01

    The Accelerator System Model (ASM) is a computer program developed to model proton radiofrequency accelerators and to carry out system level trade studies. The ASM FORTRAN subroutines are incorporated into an intuitive graphical user interface which provides for the open-quotes constructionclose quotes of the accelerator in a window on the computer screen. The interface is based on the Shell for Particle Accelerator Related Codes (SPARC) software technology written for the Macintosh operating system in the C programming language. This User Manual describes the operation and use of the ASM application within the SPARC interface. The Appendix provides a detailed description of the physics and engineering models used in ASM. ASM Version 1.0 is joint project of G. H. Gillespie Associates, Inc. and the Accelerator Technology (AT) Division of the Los Alamos National Laboratory. Neither the ASM Version 1.0 software nor this ASM Documentation may be reproduced without the expressed written consent of both the Los Alamos National Laboratory and G. H. Gillespie Associates, Inc

  7. Accelerator System Model (ASM) user manual with physics and engineering model documentation. ASM version 1.0

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1993-07-01

    The Accelerator System Model (ASM) is a computer program developed to model proton radiofrequency accelerators and to carry out system level trade studies. The ASM FORTRAN subroutines are incorporated into an intuitive graphical user interface which provides for the {open_quotes}construction{close_quotes} of the accelerator in a window on the computer screen. The interface is based on the Shell for Particle Accelerator Related Codes (SPARC) software technology written for the Macintosh operating system in the C programming language. This User Manual describes the operation and use of the ASM application within the SPARC interface. The Appendix provides a detailed description of the physics and engineering models used in ASM. ASM Version 1.0 is joint project of G. H. Gillespie Associates, Inc. and the Accelerator Technology (AT) Division of the Los Alamos National Laboratory. Neither the ASM Version 1.0 software nor this ASM Documentation may be reproduced without the expressed written consent of both the Los Alamos National Laboratory and G. H. Gillespie Associates, Inc.

  8. User's Manual for the Naval Interactive Data Analysis System-Climatologies (NIDAS-C), Version 2.0

    Science.gov (United States)

    Abbott, Clifton

    1996-01-01

    This technical note provides the user's manual for the NIDAS-C system developed for the naval oceanographic office. NIDAS-C operates using numerous oceanographic data categories stored in an installed version of the Naval Environmental Operational Nowcast System (NEONS), a relational database management system (rdbms) which employs the ORACLE proprietary rdbms engine. Data management, configuration, and control functions for the supporting rdbms are performed externally. NIDAS-C stores and retrieves data to/from the rdbms but exercises no direct internal control over the rdbms or its configuration. Data is also ingested into the rdbms, for use by NIDAS-C, by external data acquisition processes. The data categories employed by NIDAS-C are as follows: Bathymetry - ocean depth at

  9. WIMS-CRNL: A user's manual for the Chalk River version of WIMS

    International Nuclear Information System (INIS)

    Donnelly, J.V.

    1986-01-01

    This report describes the preparation of the input for WIMS-CRNL, the Chalk River version of the WIMS lattice code. Also included are notes on the operation of the code, contents of the associated libraries, and the relation of WIMS-CRNL to other versions of the code

  10. ARDS User Manual

    Science.gov (United States)

    Fleming, David P.

    2001-01-01

    Personal computers (PCs) are now used extensively for engineering analysis. their capability exceeds that of mainframe computers of only a few years ago. Programs originally written for mainframes have been ported to PCs to make their use easier. One of these programs is ARDS (Analysis of Rotor Dynamic Systems) which was developed at Arizona State University (ASU) by Nelson et al. to quickly and accurately analyze rotor steady state and transient response using the method of component mode synthesis. The original ARDS program was ported to the PC in 1995. Several extensions were made at ASU to increase the capability of mainframe ARDS. These extensions have also been incorporated into the PC version of ARDS. Each mainframe extension had its own user manual generally covering only that extension. Thus to exploit the full capability of ARDS required a large set of user manuals. Moreover, necessary changes and enhancements for PC ARDS were undocumented. The present document is intended to remedy those problems by combining all pertinent information needed for the use of PC ARDS into one volume.

  11. Decommissioning economic risk advisor: DERAD Version 1.0 user's manual. Final report

    International Nuclear Information System (INIS)

    Gjerde, A.R.; Qian, M.; Govil, P.; Balson, W.E.

    1995-04-01

    DERAD - Decommissioning Economic and Risk ADvisor - is a decision support tool designed to help utility decision makers analyze economics and financial risk of decommissioning nuclear power plants. Your current copy of DERAD, Version 1.0, is customized for PWR configurated plants. DERAD has been developed by Decision Focus Incorporated under EPRI sponsorship. If you have ideas or recommendations for how we can improve and enhance future versions of DERAD, we would like to hear from you

  12. PVWatts Version 5 Manual

    Energy Technology Data Exchange (ETDEWEB)

    Dobos, A. P.

    2014-09-01

    The NREL PVWatts calculator is a web application developed by the National Renewable Energy Laboratory (NREL) that estimates the electricity production of a grid-connected photovoltaic system based on a few simple inputs. PVWatts combines a number of sub-models to predict overall system performance, and makes includes several built-in parameters that are hidden from the user. This technical reference describes the sub-models, documents assumptions and hidden parameters, and explains the sequence of calculations that yield the final system performance estimate. This reference is applicable to the significantly revised version of PVWatts released by NREL in 2014.

  13. MOST PROBABLE NUMBER (MPN) CALCULATOR Version 2.0 User and System Installation and Administration Manual

    Science.gov (United States)

    The new MPN Calculator is an easy-to-use stand alone Windows application built by Avineon, Inc. for the EPA. The calculator was built using Microsoft .NET (dot NET) version 3.5 SP1 (C#) and Windows Presentation Foundation technologies. The new calculator not only combines the mai...

  14. GRESS [Gradient Enhanced Software System] Version 0.0 user's manual

    International Nuclear Information System (INIS)

    Horwedel, J.E.; Worley, B.A.; Oblow, E.M.; Pin, F.G.; Wright, R.Q.

    1988-10-01

    The primary objective of this manual is to provide a description of the Gradient Enhanced Software System (GRESS) and to explain how to use GRESS to enhance FORTRAN 77 models for gradient calculation. The use of the Extended Arithmetic Processor (EXAP) as the precompiler for GRESS is presented. A complete description of how to enhance a source code for forward propagation of derivatives using the calculus chain rule is provided. On option, EXAP can be used to generate derivatives and store them on a direct access device for subsequent solution of the numerical adjoint equations. Programming information is also provided to aid in the installation and maintenance of the software

  15. User's Manual for BEST-Dairy: Benchmarking and Energy/water-Saving Tool (BEST) for the Dairy Processing Industry (Version 1.2)

    Energy Technology Data Exchange (ETDEWEB)

    Xu, T.; Ke, J.; Sathaye, J.

    2011-04-20

    This User's Manual summarizes the background information of the Benchmarking and Energy/water-Saving Tool (BEST) for the Dairy Processing Industry (Version 1.2, 2011), including'Read Me' portion of the tool, the sections of Introduction, and Instructions for the BEST-Dairy tool that is developed and distributed by Lawrence Berkeley National Laboratory (LBNL).

  16. MARFA version 3.2.2 user's manual: migration analysis of radionuclides in the far field

    International Nuclear Information System (INIS)

    Painter, Scott; Mancillas, James

    2009-12-01

    The computer code Migration Analysis of Radionuclides in the Far Field (MARFA) uses a particle-based Monte Carlo method to simulate the transport of radionuclides in a sparsely fractured geological medium. Transport in sparsely fractured rock is of interest because this medium may serve as a barrier to migration of radionuclides to the accessible environment. The physical processes represented in MARFA include advection, longitudinal dispersion, Fickian diffusion into an infinite or finite rock matrix, equilibrium sorption, decay, and in-growth. Multiple non-branching decay chains of arbitrary length are supported. This document describes the technical basis and input requirements for MARFA Version 3.2.2. MARFA Version 3.2 included new capabilities to accommodate transient flow velocities and sorption parameters, which are assumed to be piecewise constant in time. Version 3.2.1 was a minor change from Version 3.2 to allow a more convenient input format for sorption information. New capabilities in Version 3.2.2 include an option to specify a non-zero start time for the simulation, an optional input parameter that decreases the amount of retention within a single fracture because of flow channeling, and an alternative method for sampling the radionuclide source. MARFA uses the particle on random streamline segment algorithm /Painter et al. 2006/, a Monte Carlo algorithm combining time-domain random walk methods with pathway stochastic simulation. The algorithm uses non-interacting particles to represent packets of radionuclide mass. These particles are moved through the system according to rules that mimic the underlying physical transport and retention processes. The set of times required for particles to pass through the geological barrier are then used to reconstruct discharge rates (mass or activity basis). Because the algorithm uses non-interacting particles, the transport and retention processes are limited to those that depend linearly on radionuclide

  17. STAR (structural test and analysis database for reliable design) Version 7.1. User's manual

    International Nuclear Information System (INIS)

    Hosogai, Hiromi; Kawasaki, Nobuchika; Kasahara, Naoto

    1998-12-01

    The STAR is characterized by having two supporting functions for developing strength evaluation methods in addition to usual data base management system, an automatic damage calculation function with external programs and an analysis system on accuracy of prediction. This report describes the structure and user information for execution of STAR code. (K. Itami)

  18. Langley Stability and Transition Analysis Code (LASTRAC) Version 1.2 User Manual

    Science.gov (United States)

    Chang, Chau-Lyan

    2004-01-01

    LASTRAC is a general-purposed, physics-based transition prediction code released by NASA for Laminar Flow Control studies and transition research. The design and development of the LASTRAC code is aimed at providing an engineering tool that is easy to use and yet capable of dealing with a broad range of transition related issues. It was written from scratch based on the state-of-the-art numerical methods for stability analysis and modern software technologies. At low fidelity, it allows users to perform linear stability analysis and N-factor transition correlation for a broad range of flow regimes and configurations by using either the linear stability theory or linear parabolized stability equations method. At high fidelity, users may use nonlinear PSE to track finite-amplitude disturbances until the skin friction rise. This document describes the governing equations, numerical methods, code development, detailed description of input/output parameters, and case studies for the current release of LASTRAC.

  19. EnviroFish, Version 1.0: User’s Manual

    Science.gov (United States)

    2012-08-01

    to prepare input. Although the Enviro - Fish user may not become directly involved in the hydrologic modeling, a general awareness of the available...ERDC/EL TR-12-19 90 Appendix D: Hydrologic Plan A hydrologic plan is a prerequisite for a successful application of Enviro Fish. The planner of...certain amount of seepage may still emerge through the soil despite the action of the seepage well. Seepage wells may be sources of water for

  20. CSTEM User Manual

    Science.gov (United States)

    Hartle, M.; McKnight, R. L.

    2000-01-01

    This manual is a combination of a user manual, theory manual, and programmer manual. The reader is assumed to have some previous exposure to the finite element method. This manual is written with the idea that the CSTEM (Coupled Structural Thermal Electromagnetic-Computer Code) user needs to have a basic understanding of what the code is actually doing in order to properly use the code. For that reason, the underlying theory and methods used in the code are described to a basic level of detail. The manual gives an overview of the CSTEM code: how the code came into existence, a basic description of what the code does, and the order in which it happens (a flowchart). Appendices provide a listing and very brief description of every file used by the CSTEM code, including the type of file it is, what routine regularly accesses the file, and what routine opens the file, as well as special features included in CSTEM.

  1. SEVERO code - user's manual

    International Nuclear Information System (INIS)

    Sacramento, A.M. do.

    1989-01-01

    This user's manual contains all the necessary information concerning the use of SEVERO code. This computer code is related to the statistics of extremes = extreme winds, extreme precipitation and flooding hazard risk analysis. (A.C.A.S.)

  2. EMAP Users Manual.

    Science.gov (United States)

    Kotz, Arnold; Redondo, Rory

    Presented is the user's manual for the Educational Manpower Information Sources Project (EMAP), an information file containing approximately 325 document abstracts related to the field of educational planning. (The EMAP file is described in document SP 006 747.) (JB)

  3. Geographic Resources Analysis Support System (GRASS) Version 4.0 User’s Reference Manual

    Science.gov (United States)

    1992-06-01

    nmlulc.read, and places them into the user’s current mapset: 1. Land Use & Land Cover 2. Political Units 3. Census Units 4. Hydrologic Units 5. Federal...CIG format. Extracted data is placed into a file specified by argi . nmlulc.read should be used prior to using the GRASS program m.lulc.USGS...ALSO The AT least-cost search algorithm used by r.watershed is described in " Using the AT Search Algorithm to Develop Hydrologic Models from Digital

  4. GERTS GQ User's Manual.

    Science.gov (United States)

    Akiba, Y.; And Others

    This user's manual for the simulation program Graphical Evaluation and Review Technique (GERT) GQ contains sections on nodes, branches, program input description and format, and program output, as well as examples. Also included is a programmer's manual which contains information on scheduling, subroutine descriptions, COMMON Variables, and…

  5. Version II of the users manual for the Tuff Data Base Interface

    International Nuclear Information System (INIS)

    Welch, E.P.; Satter, B.J.; Langkopf, B.S.; Zeuch, D.H.

    1987-05-01

    The Nevada Nuclear Waste Storage Investigations (NNWSI) Project, managed by the Nevada Operations Office of the US Department of Energy, is investigating the feasibility of locating a repository at Yucca Mountain on and adjacent to the Nevada Test Site (NTS) in southern Nevada. A part of this investigation includes obtaining physical properties from laboratory tests on samples from Yucca Mountain and from field tests at Yucca Mountain. A computerized data base has been developed to store this data in a centralized location. The data base is stored on the Cyber 170/855 computer at Sandia using the System 2000 Data Base Management software. A user-friendly interface, the Tuff Data Base Interface (the Interface), allows NNWSI participants to retrieve data from the Tuff Data Base. The Interface gives users flexibility to retrieve portions of the Data Base related to their interests. This report gives basic instructions on accessing the Sandia computing system and explains how to use the Interface. 18 figs., 5 tabs

  6. Thermal Insulation System Analysis Tool (TISTool) User's Manual. Version 1.0.0

    Science.gov (United States)

    Johnson, Wesley; Fesmire, James; Leucht, Kurt; Demko, Jonathan

    2010-01-01

    The Thermal Insulation System Analysis Tool (TISTool) was developed starting in 2004 by Jonathan Demko and James Fesmire. The first edition was written in Excel and Visual BasIc as macros. It included the basic shapes such as a flat plate, cylinder, dished head, and sphere. The data was from several KSC tests that were already in the public literature realm as well as data from NIST and other highly respectable sources. More recently, the tool has been updated with more test data from the Cryogenics Test Laboratory and the tank shape was added. Additionally, the tool was converted to FORTRAN 95 to allow for easier distribution of the material and tool. This document reviews the user instructions for the operation of this system.

  7. Method of Characteristic (MOC) Nozzle Flowfield Solver - User’s Guide and Input Manual Version 2.0

    Science.gov (United States)

    2018-01-01

    TECHNICAL REPORT RDMR-SS-17-13 METHOD OF CHARACTERISTIC (MOC) NOZZLE FLOWFIELD SOLVER—USER’S GUIDE AND INPUT MANUAL VERSION 2.0 Kevin D. Kennedy...1 II. PROGRAM READS AND WRITES ...2 B. Program Reads .................................................................................................. 4 C. Program Writes

  8. SHARP User Manual

    Energy Technology Data Exchange (ETDEWEB)

    Yu, Y. Q. [Argonne National Lab. (ANL), Argonne, IL (United States); Shemon, E. R. [Argonne National Lab. (ANL), Argonne, IL (United States); Thomas, J. W. [Argonne National Lab. (ANL), Argonne, IL (United States); Mahadevan, Vijay S. [Argonne National Lab. (ANL), Argonne, IL (United States); Rahaman, Ronald O. [Argonne National Lab. (ANL), Argonne, IL (United States); Solberg, Jerome [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

    2016-03-31

    SHARP is an advanced modeling and simulation toolkit for the analysis of nuclear reactors. It is comprised of several components including physical modeling tools, tools to integrate the physics codes for multi-physics analyses, and a set of tools to couple the codes within the MOAB framework. Physics modules currently include the neutronics code PROTEUS, the thermal-hydraulics code Nek5000, and the structural mechanics code Diablo. This manual focuses on performing multi-physics calculations with the SHARP ToolKit. Manuals for the three individual physics modules are available with the SHARP distribution to help the user to either carry out the primary multi-physics calculation with basic knowledge or perform further advanced development with in-depth knowledge of these codes. This manual provides step-by-step instructions on employing SHARP, including how to download and install the code, how to build the drivers for a test case, how to perform a calculation and how to visualize the results. Since SHARP has some specific library and environment dependencies, it is highly recommended that the user read this manual prior to installing SHARP. Verification tests cases are included to check proper installation of each module. It is suggested that the new user should first follow the step-by-step instructions provided for a test problem in this manual to understand the basic procedure of using SHARP before using SHARP for his/her own analysis. Both reference output and scripts are provided along with the test cases in order to verify correct installation and execution of the SHARP package. At the end of this manual, detailed instructions are provided on how to create a new test case so that user can perform novel multi-physics calculations with SHARP. Frequently asked questions are listed at the end of this manual to help the user to troubleshoot issues.

  9. SHARP User Manual

    International Nuclear Information System (INIS)

    Yu, Y. Q.; Shemon, E. R.; Thomas, J. W.; Mahadevan, Vijay S.; Rahaman, Ronald O.; Solberg, Jerome

    2016-01-01

    SHARP is an advanced modeling and simulation toolkit for the analysis of nuclear reactors. It is comprised of several components including physical modeling tools, tools to integrate the physics codes for multi-physics analyses, and a set of tools to couple the codes within the MOAB framework. Physics modules currently include the neutronics code PROTEUS, the thermal-hydraulics code Nek5000, and the structural mechanics code Diablo. This manual focuses on performing multi-physics calculations with the SHARP ToolKit. Manuals for the three individual physics modules are available with the SHARP distribution to help the user to either carry out the primary multi-physics calculation with basic knowledge or perform further advanced development with in-depth knowledge of these codes. This manual provides step-by-step instructions on employing SHARP, including how to download and install the code, how to build the drivers for a test case, how to perform a calculation and how to visualize the results. Since SHARP has some specific library and environment dependencies, it is highly recommended that the user read this manual prior to installing SHARP. Verification tests cases are included to check proper installation of each module. It is suggested that the new user should first follow the step-by-step instructions provided for a test problem in this manual to understand the basic procedure of using SHARP before using SHARP for his/her own analysis. Both reference output and scripts are provided along with the test cases in order to verify correct installation and execution of the SHARP package. At the end of this manual, detailed instructions are provided on how to create a new test case so that user can perform novel multi-physics calculations with SHARP. Frequently asked questions are listed at the end of this manual to help the user to troubleshoot issues.

  10. MINTEQ user's manual

    International Nuclear Information System (INIS)

    Peterson, S.R.; Hostetler, C.J.; Deutsch, W.J.; Cowan, C.E.

    1987-02-01

    This manual will aid the user in applying the MINTEQ geochemical computer code to model aqueous solutions and the interactions of aqueous solutions with hypothesized assemblages of solid phases. The manual will provide a basic understanding of how the MINTEQ computer code operates and the important principles that are incorporated into the code and instruct a user of the MINTEQ code on how to create input files to simulate a variety of geochemical problems. Chapters 2 through 8 are for the user who has some experience with or wishes to review the principles important to geochemical computer codes. These chapters include information on the methodology MINTEQ uses to incorporate these principles into the code. Chapters 9 through 11 are for the user who wants to know how to create input data files to model various types of problems. 35 refs., 2 figs., 5 tabs

  11. CANAL user's manual

    International Nuclear Information System (INIS)

    Faya, A.; Wolf, L.; Todreas, N.

    1979-11-01

    CANAL is a subchannel computer program for the steady-state and transient thermal hydraulic analysis of BWR fuel rod bundles. The purpose of this manual is to introduce the user into the mechanism of running the code by providing information about the input data and options

  12. AELIB user's manual

    International Nuclear Information System (INIS)

    Evans, L.E.; Klawitter, G.L.

    1981-05-01

    This report is an updatable manual for users of AELIB, the AECL Library of FORTRAN-callable routines for the CRNL CDC 6600/CYBER 170 system. It provides general advice on the use of this library and detailed information on the selection and usage of particular library routines

  13. TRUBA User Manual

    Energy Technology Data Exchange (ETDEWEB)

    Tereshchenko, M. A.; Castejon, F.; Cappa, A.

    2008-04-25

    The TRUBA (pipeline in Russian) code is a computational tool for studying the propagation of Gaussian-shaped microwave beams in a prescribed equilibrium plasma. This manual covers the basic material handed to use the implementation of TRUBA (version 3,4) interfaced with the numerical library of the TJ-II stellarator. The manual provides a concise theoretical background of the problem, specifications for setting up the input files and interpreting the output of the code, and some information useful in modifying TRUBA. (Author) 13 refs.

  14. TRUBA User Manual

    International Nuclear Information System (INIS)

    Tereshchenko, M. A.; Castejon, F.; Cappa, A.

    2008-01-01

    The TRUBA (pipeline in Russian) code is a computational tool for studying the propagation of Gaussian-shaped microwave beams in a prescribed equilibrium plasma. This manual covers the basic material handed to use the implementation of TRUBA (version 3,4) interfaced with the numerical library of the TJ-II stellarator. The manual provides a concise theoretical background of the problem, specifications for setting up the input files and interpreting the output of the code, and some information useful in modifying TRUBA. (Author) 13 refs

  15. User Manual for Graphical User Interface Version 2.4 with Fire and Smoke Simulation Model (FSSIM) Version 1.2

    National Research Council Canada - National Science Library

    Haupt, Tomasz A; Henley, Greg; Sura, Bhargavi; Kirkland, Robert; Floyd, Jason; Scheffey, Joseph; Tatem, Patricia A; Williams, Frederick W

    2006-01-01

    The collaborative work of Hughes Associates, Inc., the Naval Research Laboratory, and a group at Mississippi State University resulted in development of a simulation system including a Graphical User Interface (GUI...

  16. OASIS User Manual

    CERN Document Server

    Bojtar, L

    2009-01-01

    The OASIS system has been operational for years now. After a long development the project has reached a state where the number of features it provides exceeds largely what most of its users knows about. The author felt it was time to write a user manual explaining all the functionality of the viewer application. This document is a user manual, concentrating on the functionality of the viewer from the user’s point of view. There are already documents available on the project’s web site about the technical aspects at http://project-oasis.web.cern.ch/project-oasis/presentations.htm . There was an attempt to produce a tutorial on the viewer, but it didn’t get much further than the table of contents, that however is well thought. The structure of this user manual follows the same principle, the basic and most often used features are grouped together. Advanced or less often used features are described in a separate chapter. There is a second organizational principle, features belong to different levels: chann...

  17. IAC user manual

    Science.gov (United States)

    Vos, R. G.; Beste, D. L.; Gregg, J.

    1984-01-01

    The User Manual for the Integrated Analysis Capability (IAC) Level 1 system is presented. The IAC system currently supports the thermal, structures, controls and system dynamics technologies, and its development is influenced by the requirements for design/analysis of large space systems. The system has many features which make it applicable to general problems in engineering, and to management of data and software. Information includes basic IAC operation, executive commands, modules, solution paths, data organization and storage, IAC utilities, and module implementation.

  18. Justine user`s manual

    Energy Technology Data Exchange (ETDEWEB)

    Lee, S.R.

    1995-10-01

    Justine is the graphical user interface to the Los Alamos Radiation Modeling Interactive Environment (LARAMIE). It provides LARAMIE customers with a powerful, robust, easy-to-use, WYSIWYG interface that facilitates geometry construction and problem specification. It is assumed that the reader is familiar with LARAMIE, and the transport codes available, i.e., MCNPTM and DANTSYSTM. No attempt is made in this manual to describe these codes in detail. Information about LARAMIE, DANTSYS, and MCNP are available elsewhere. It i also assumed that the reader is familiar with the Unix operating system and with Motif widgets and their look and feel. However, a brief description of Motif and how one interacts with it can be found in Appendix A.

  19. STAIRS User's Manual

    Energy Technology Data Exchange (ETDEWEB)

    Gadjokov, V; Dragulev, V; Gove, N; Schmid, H

    1976-10-15

    The STorage And Information Retrieval System (STAIRS) of IBM is described from the user's point of view. The description is based on the experimental use of STAIRS at the IAEA computer, with INIS and AGRIS data bases, from June 1975 to May 1976. Special attention is paid to what may be termed the hierarchical approach to retrieval in STAIRS. Such an approach allows for better use of the intrinsic data-base structure and, hence, contributes to higher recall and/or relevance ratios in retrieval. The functions carried out by STAIRS are explained and the communication language between the user and the system outlined. Details are given of the specific structure of the INIS and AGRIS data bases for STAIRS. The manual should enable an inexperienced user to start his first on-line dialogues by means of a CRT or teletype terminal. (author)

  20. STAIRS User's Manual

    International Nuclear Information System (INIS)

    Gadjokov, V.; Dragulev, V.; Gove, N.; Schmid, H.

    1976-10-01

    The STorage And Information Retrieval System (STAIRS) of IBM is described from the user's point of view. The description is based on the experimental use of STAIRS at the IAEA computer, with INIS and AGRIS data bases, from June 1975 to May 1976. Special attention is paid to what may be termed the hierarchical approach to retrieval in STAIRS. Such an approach allows for better use of the intrinsic data-base structure and, hence, contributes to higher recall and/or relevance ratios in retrieval. The functions carried out by STAIRS are explained and the communication language between the user and the system outlined. Details are given of the specific structure of the INIS and AGRIS data bases for STAIRS. The manual should enable an inexperienced user to start his first on-line dialogues by means of a CRT or teletype terminal. (author)

  1. GRSAC Users Manual

    International Nuclear Information System (INIS)

    Ball, S.J.; Nypaver, D.J.

    1999-01-01

    An interactive workstation-based simulation code (GRSAC) for studying postulated severe accidents in gas-cooled reactors has been developed to accommodate user-generated input with ''smart front-end'' checking. Code features includes on- and off-line plotting, on-line help and documentation, and an automated sensitivity study option. The code and its predecessors have been validated using comparisons with a variety of experimental data and similar codes. GRSAC model features include a three-dimensional representation of the core thermal hydraulics, and optional ATWS (anticipated transients without scram) capabilities. The user manual includes a detailed description of the code features, and includes four case studies which guide the user through four different examples of the major uses of GRSAC: an accident case; an initial conditions setup and run; a sensitivity study; and the setup of a new reactor model

  2. GRSAC Users Manual

    Energy Technology Data Exchange (ETDEWEB)

    Ball, S.J.; Nypaver, D.J.

    1999-02-01

    An interactive workstation-based simulation code (GRSAC) for studying postulated severe accidents in gas-cooled reactors has been developed to accommodate user-generated input with ''smart front-end'' checking. Code features includes on- and off-line plotting, on-line help and documentation, and an automated sensitivity study option. The code and its predecessors have been validated using comparisons with a variety of experimental data and similar codes. GRSAC model features include a three-dimensional representation of the core thermal hydraulics, and optional ATWS (anticipated transients without scram) capabilities. The user manual includes a detailed description of the code features, and includes four case studies which guide the user through four different examples of the major uses of GRSAC: an accident case; an initial conditions setup and run; a sensitivity study; and the setup of a new reactor model.

  3. Reliability of the Spanish version of the wheelchair skills test 4.2 for manual wheelchair users with spinal cord injury.

    Science.gov (United States)

    Passuni, Diego; Dalzotto, Elisa; F Gath, Christian; Buffetti, Eliana; Elizalde, Milagros; Jarmoluk, Verónica; Russo, Maria J; Intruvini, Silvia; Olmos, Lisandro E; Freixes, Orestes

    2018-05-03

    Cross-sectional. The majority of people with a spinal cord injury (SCI) are dependent on wheelchair for their mobility. Approximately, 36% of wheelchair users reported that obstacles such as curbs, uneven terrain, flooring surfaces and thresholds were barriers to mobility. Several studies have shown that assessment and training of wheelchair skills leads to improvements in those skills. The purpose of our study was to translate the Wheelchair Skill Test (4.2) and its report form into Spanish and then determine the inter-rater reliability of the WST 4.2 for manual wheelchairs operated by their users. Rehabilitation Unit, FLENI Institute, Buenos Aires, Argentina. The translation was performed by a physical therapist with advanced English language skills and specialized in the treatment of SCI subjects. We administrated and video-recorded the WST 4.2 manual Spanish version in 11 SCI subjects. Two physical therapists received specific training for administering the test and scoring the record. The reliability of the total percentage WST score were statistically quantified by intraclass correlation coefficient (ICC). ICC values for Interrater were 0.998 (p skills had a 100 percentage of agreement. Percentage of agreement in the three skills that presented less rating agreement was 73%, 81 % and 82 %, respectively. The results show that the Spanish version of WST 4.2 is a reliable assessment tool to evaluate the skills capacity of spinal cord manual wheelchair users. Implications for rehabilitation Wheelchair users require a proficient management of various wheelchair skills to achieve maximum independence in daily life. Determining which wheelchair skills should be addressed during the rehabilitation process is of great importance for their correct training. The WST 4.2 is an appropriate assessment tool to determine the functional capacity of wheelchair users. Making available the WST 4.2 in the Spanish language and demonstrating its reliability in this language

  4. MELCOR computer code manuals: Primer and user's guides, Version 1.8.3 September 1994. Volume 1

    International Nuclear Information System (INIS)

    Summers, R.M.; Cole, R.K. Jr.; Smith, R.C.; Stuart, D.S.; Thompson, S.L.; Hodge, S.A.; Hyman, C.R.; Sanders, R.L.

    1995-03-01

    MELCOR is a fully integrated, engineering-level computer code that models the progression of severe accidents in light water reactor nuclear power plants. MELCOR is being developed at Sandia National Laboratories for the US Nuclear Regulatory Commission as a second-generation plant risk assessment tool and the successor to the Source Term Code Package. A broad spectrum of severe accident phenomena in both boiling and pressurized water reactors is treated in MELCOR in a unified framework. These include: thermal-hydraulic response in the reactor coolant system, reactor cavity, containment, and confinement buildings; core heatup, degradation, and relocation; core-concrete attack; hydrogen production, transport, and combustion; fission product release and transport; and the impact of engineered safety features on thermal-hydraulic and radionuclide behavior. Current uses of MELCOR include estimation of severe accident source terms and their sensitivities and uncertainties in a variety of applications. This publication of the MELCOR computer code manuals corresponds to MELCOR 1.8.3, released to users in August, 1994. Volume 1 contains a primer that describes MELCOR's phenomenological scope, organization (by package), and documentation. The remainder of Volume 1 contains the MELCOR Users' Guides, which provide the input instructions and guidelines for each package. Volume 2 contains the MELCOR Reference Manuals, which describe the phenomenological models that have been implemented in each package

  5. Probabilistic methodology for assessing steam generator tube inspection - Phase II: User's manual for CANTIA Version 1.1

    International Nuclear Information System (INIS)

    Harris, J.E.; Gorman, J.A.; Turner, A.P.L.

    1997-03-01

    The objectives of this project were to develop a computer-based method for probabilistic assessment of inspection strategies for steam generator tubes, and to document the source code and to provide a user's manual for it. The program CANTIA was created to fulfill this objective, and the user's manual is provided in this volume. The documentation and verification of the CANTIA code is provided as a separate report. CANTIA uses Monte Carlo techniques to determine approximate probabilities of steam generator tube failures under accident conditions and primary-to-secondary leak rates under normal and accident conditions at future points in time. The program also determines approximate future flaw distributions and non-destructive examination results from the input data. The probabilities of failure and leak rates and the future flaw distributions can be influenced by performing inspections of the steam generator tubes at some future points in time, and removing defective tubes from the population. The effect of different inspection and maintenance strategies can therefore be determined as a direct effect on the probability of tube failure and primary-to-secondary leak rate

  6. ASSERT-4 user's manual

    International Nuclear Information System (INIS)

    Judd, R.A.; Tahir, A.; Carver, M.B.; Stewart, D.G.; Thibeault, P.R.; Rowe, D.S.

    1984-09-01

    ASSERT-4 is an advanced subchannel code being developed primarily to model single- and two-phase flow and heat transfer in horizontal rod bundles. This manual is intended to facilitate the application of this code to the analysis of flow in reactor fuel channels. It contains a brief description of the thermalhydraulic model and ASSERT-4 solution scheme, and other information required by users. This other information includes a detailed discussion of input data requirements, a sample problem and solution, and information describing how to access and run ASSERT-4 on the Chalk River computers

  7. GANDALF: users' manual

    International Nuclear Information System (INIS)

    Strout, R.E. II; Beach, J.L.

    1977-01-01

    The GANDALF computer code was written to calculate neutron dose equivalent given the pulse-height data obtained by using a Linear Energy Transfer (LET) proportional counter. The code also uses pre- and/or post-calibration spectra, from an alpha source, to determine a calibration factor in keV/μ/channel. Output from the code consists of the effective radius of the detection chamber in microns, a calibration factor in keV/μ/channel, and the total dose and dose equivalent in rad or rem between any two LET energies by using the equations by Attix and Roesch [Radiation Dosimetry, 1, 71 (1968)]. This report is a user's manual and is not intended as anything else, and assumes that the user has a basic knowledge of the LLL Octopus timesharing system. However, a very brief description of how the code operates is included

  8. UNSAT-H Version 3.0: Unsaturated Soil Water and Heat Flow Model Theory, User Manual, and Examples

    International Nuclear Information System (INIS)

    Fayer, M.J.

    2000-01-01

    The UNSAT-H model was developed at Pacific Northwest National Laboratory (PNNL) to assess the water dynamics of arid sites and, in particular, estimate recharge fluxes for scenarios pertinent to waste disposal facilities. During the last 4 years, the UNSAT-H model received support from the Immobilized Waste Program (IWP) of the Hanford Site's River Protection Project. This program is designing and assessing the performance of on-site disposal facilities to receive radioactive wastes that are currently stored in single- and double-shell tanks at the Hanford Site (LMHC 1999). The IWP is interested in estimates of recharge rates for current conditions and long-term scenarios involving the vadose zone disposal of tank wastes. Simulation modeling with UNSAT-H is one of the methods being used to provide those estimates (e.g., Rockhold et al. 1995; Fayer et al. 1999). To achieve the above goals for assessing water dynamics and estimating recharge rates, the UNSAT-H model addresses soil water infiltration, redistribution, evaporation, plant transpiration, deep drainage, and soil heat flow as one-dimensional processes. The UNSAT-H model simulates liquid water flow using Richards' equation (Richards 1931), water vapor diffusion using Fick's law, and sensible heat flow using the Fourier equation. This report documents UNSAT-H .Version 3.0. The report includes the bases for the conceptual model and its numerical implementation, benchmark test cases, example simulations involving layered soils and plants, and the code manual. Version 3.0 is an, enhanced-capability update of UNSAT-H Version 2.0 (Fayer and Jones 1990). New features include hysteresis, an iterative solution of head and temperature, an energy balance check, the modified Picard solution technique, additional hydraulic functions, multiple-year simulation capability, and general enhancements

  9. ETAP user's manual

    International Nuclear Information System (INIS)

    Watanabe, Norio; Higuchi, Suminori.

    1990-11-01

    The event tree analysis technique has been used in Probabilistic Safety Assessment for LWRs to delineate various accident scenarios leading to core melt or containment failure and to evaluate their frequencies. This technique often requires manual preparation of event trees with iterative process and time-consuming work in data handling. For the purpose of reducing manual efforts in event tree analysis, we developed a new software package named ETAP (Event Tree Analysis Supporting Program) for event tree analysis. ETAP is an interactive PC-based program which has the ability to construct, update, document, and quantify event trees. Because of its fast running capability to quantify event trees, use of the EATP program can make it easy to perform the sensitivity studies on a variety of system/containment performance issues. This report provides a user's manual for ETAP, which describes the structure, installation, and use of EATP. This software runs on NEC/PC-9800 or compatible PCs that have a 640 KB memory and MS-DOS 2.11 or higher. (author)

  10. Electronic Commerce user manual

    Energy Technology Data Exchange (ETDEWEB)

    1992-04-10

    This User Manual supports the Electronic Commerce Standard System. The Electronic Commerce Standard System is being developed for the Department of Defense of the Technology Information Systems Program at the Lawrence Livermore National Laboratory, operated by the University of California for the Department of Energy. The Electronic Commerce Standard System, or EC as it is known, provides the capability for organizations to conduct business electronically instead of through paper transactions. Electronic Commerce and Computer Aided Acquisition and Logistics Support, are two major projects under the DoD`s Corporate Information Management program, whose objective is to make DoD business transactions faster and less costly by using computer networks instead of paper forms and postage. EC runs on computers that use the UNIX operating system and provides a standard set of applications and tools that are bound together by a common command and menu system. These applications and tools may vary according to the requirements of the customer or location and may be customized to meet the specific needs of an organization. Local applications can be integrated into the menu system under the Special Databases & Applications option on the EC main menu. These local applications will be documented in the appendices of this manual. This integration capability provides users with a common environment of standard and customized applications.

  11. Electronic Commerce user manual

    Energy Technology Data Exchange (ETDEWEB)

    1992-04-10

    This User Manual supports the Electronic Commerce Standard System. The Electronic Commerce Standard System is being developed for the Department of Defense of the Technology Information Systems Program at the Lawrence Livermore National Laboratory, operated by the University of California for the Department of Energy. The Electronic Commerce Standard System, or EC as it is known, provides the capability for organizations to conduct business electronically instead of through paper transactions. Electronic Commerce and Computer Aided Acquisition and Logistics Support, are two major projects under the DoD's Corporate Information Management program, whose objective is to make DoD business transactions faster and less costly by using computer networks instead of paper forms and postage. EC runs on computers that use the UNIX operating system and provides a standard set of applications and tools that are bound together by a common command and menu system. These applications and tools may vary according to the requirements of the customer or location and may be customized to meet the specific needs of an organization. Local applications can be integrated into the menu system under the Special Databases Applications option on the EC main menu. These local applications will be documented in the appendices of this manual. This integration capability provides users with a common environment of standard and customized applications.

  12. Wien Automatic System Planning (WASP) Package. A computer code for power generating system expansion planning. Version WASP-IV. User's manual

    International Nuclear Information System (INIS)

    2001-01-01

    As a continuation of its efforts to provide methodologies and tools to Member States to carry out comparative assessment and analyse priority environmental issues related to the development of the electric power sector, the IAEA has completed a new version of the Wien Automatic System Planning (WASP) Package WASP-IV for carrying out power generation expansion planning taking into consideration fuel availability and environmental constraints. This manual constitutes a part of this work and aims to provide users with a guide to use effectively the new version of the model WASP-IV. WASP was originally developed in 1972 by the Tennessee Valley Authority and the Oak Ridge National Laboratory in the USA to meet the IAEA needs to analyse the economic competitiveness of nuclear power in comparison to other generation expansion alternatives for supplying the future electricity requirements of a country or region. Previous versions of the model were used by Member States in many national and regional studies to analyse the electric power system expansion planning and the role of nuclear energy in particular. Experience gained from its application allowed development of WASP into a very comprehensive planning tool for electric power system expansion analysis. New, improved versions were developed, which took into consideration the needs expressed by the users of the programme in order to address important emerging issues being faced by the electric system planners. In 1979, WASP-IV was released and soon after became an indispensable tool in many Member States for generation expansion planning. The WASP-IV version was continually upgraded and the development of version WASP-III Plus commenced in 1992. By 1995, WASP-III Plus was completed, which followed closely the methodology of the WASP-III but incorporated new features. In order to meet the needs of electricity planners and following the recommendations of the Helsinki symposium, development of a new version of WASP was

  13. TJ-II Library Manual (Version 2)

    International Nuclear Information System (INIS)

    Tribaldos, V.; Milligen, B. Ph. van; Lopez-Fraguas, A.

    2001-01-01

    This is a manual of use of the TJ2 Numerical Library that has been developed for making numerical computations of different TJ-II configurations. This manual is a new version of the earlier manual CIEMAT report 806. (Author)

  14. User manual for version 4.3 of the Tripoli-4 Monte-Carlo method particle transport computer code

    International Nuclear Information System (INIS)

    Both, J.P.; Mazzolo, A.; Peneliau, Y.; Petit, O.; Roesslinger, B.

    2003-01-01

    This manual relates to Version 4.3 TRIPOLI-4 code. TRIPOLI-4 is a computer code simulating the transport of neutrons, photons, electrons and positrons. It can be used for radiation shielding calculations (long-distance propagation with flux attenuation in non-multiplying media) and neutronic calculations (fissile medium, criticality or sub-criticality basis). This makes it possible to calculate k eff (for criticality), flux, currents, reaction rates and multi-group cross-sections. TRIPOLI-4 is a three-dimensional code that uses the Monte-Carlo method. It allows for point-wise description in terms of energy of cross-sections and multi-group homogenized cross-sections and features two modes of geometrical representation: surface and combinatorial. The code uses cross-section libraries in ENDF/B format (such as JEF2-2, ENDF/B-VI and JENDL) for point-wise description cross-sections in APOTRIM format (from the APOLLO2 code) or a format specific to TRIPOLI-4 for multi-group description. (authors)

  15. CALENDF-2010: user manual

    International Nuclear Information System (INIS)

    Sublet, Jean-Christophe; Ribon, Pierre; Coste-Delclaux, Mireille

    2011-09-01

    CALENDF-2010 represents a Fortran-95 update of the 1994, 2001 then 2005 code distribution with emphasise on programming quality and standards, physics and usage improvements. Devised to process multigroup cross-sections it relies on Gauss quadrature mathematical principle and strength. The followings processes can be handled by the code: moment probability table and effective cross-section calculation; pointwise cross section, probability table and effective cross-section regrouping; probability table condensation; probability table mix for several isotopes; probability table interpolation; effective cross section based probability table calculations; probability table calculations from effective cross-sections; cross-section comparison, complete energy pointwise cross-section processing and thickness dependent averaged transmission sample calculation. The CALENDF user manual, after having listed all principal code functions, describes sequentially each of them and gives comments on their associated output streams. Installation procedures, test cases and running time platform comparisons are given in the appendix. (authors)

  16. LCS Users Manual

    International Nuclear Information System (INIS)

    Redd, A.J.; Ignat, D.W.

    1998-01-01

    The Lower Hybrid Simulation Code (LSC) is a computational model of lower hybrid current drive in the presence of an electric field. Details of geometry, plasma profiles, and circuit equations are treated. Two-dimensional velocity space effects are approximated in a one-dimensional Fokker-Planck treatment. The LSC was originally written to be a module for lower hybrid current drive called by the Tokamak Simulation Code (TSC), which is a numerical model of an axisymmetric tokamak plasma and the associated control systems. The TSC simulates the time evolution of a free boundary plasma by solving the MHD equations on a rectangular computational grid. The MHD equations are coupled to the external circuits (representing poloidal field coils) through the boundary conditions. The code includes provisions for modeling the control system, external heating, and fusion heating. The LSC module can also be called by the TRANSP code. TRANSP represents the plasma with an axisymmetric, fixed-boundary model and focuses on calculation of plasma transport to determine transport coefficients from data on power inputs and parameters reached. This manual covers the basic material needed to use the LSC. If run in conjunction with TSC, the ''TSC Users Manual'' should be consulted. If run in conjunction with TRANSP, on-line documentation will be helpful. A theoretical background of the governing equations and numerical methods is given. Information on obtaining, compiling, and running the code is also provided

  17. Prediction of Turbulence-Generated Noise in Unheated Jets. Part 2; JeNo Users' Manual (Version 1.0)

    Science.gov (United States)

    Khavaran, Abbas; Wolter, John D.; Koch, L. Danielle

    2009-01-01

    JeNo (Version 1.0) is a Fortran90 computer code that calculates the far-field sound spectral density produced by axisymmetric, unheated jets at a user specified observer location and frequency range. The user must provide a structured computational grid and a mean flow solution from a Reynolds-Averaged Navier Stokes (RANS) code as input. Turbulence kinetic energy and its dissipation rate from a k-epsilon or k-omega turbulence model must also be provided. JeNo is a research code, and as such, its development is ongoing. The goal is to create a code that is able to accurately compute far-field sound pressure levels for jets at all observer angles and all operating conditions. In order to achieve this goal, current theories must be combined with the best practices in numerical modeling, all of which must be validated by experiment. Since the acoustic predictions from JeNo are based on the mean flow solutions from a RANS code, quality predictions depend on accurate aerodynamic input.This is why acoustic source modeling, turbulence modeling, together with the development of advanced measurement systems are the leading areas of research in jet noise research at NASA Glenn Research Center.

  18. User's manual (UM) for the enhanced logistics intratheater support tool (ELIST) database utility segment version 8.1.0.0 for solaris 7.; TOPICAL

    International Nuclear Information System (INIS)

    Dritz, K.

    2002-01-01

    This document is the User's Manual (UM) for the Enhanced Logistics Intratheater Support Tool (ELIST) Database Utility Segment. It tells how to use its features to administer ELIST database user accounts

  19. DIMAC program user's manual

    International Nuclear Information System (INIS)

    Lee, Byoung Oon; Song, Tae Young

    2003-11-01

    DIMAC (A DIspersion Metallic fuel performance Analysis Code) is a computer program for simulating the behavior of dispersion fuel rods under normal operating conditions of HYPER. It computes the one-dimensional temperature distribution and the thermo-mechanical characteristics of fuel rod under the steady state operation condition, including the swelling and rod deformation. DIMAC was developed based on the experience of research reactor fuel. DIMAC consists of the temperature calculation module, the mechanical swelling calculation module, and the fuel deformation calculation module in order to predict the deformation of a dispersion fuel as a function of power history. Because there are a little of available U-TRU-Zr or TRU-Zr characteristics, the material data of U-Pu-Zr or Pu-Zr are used for those of U-TRU-Zr or TRU-Zr. This report is mainly intended as a user's manual for the DIMAC code. The general description on this code, the description on input parameter, the description on each subroutine, the sample problem and the sample input and partial output are written in this report

  20. DIMAC program user's manual

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Byoung Oon; Song, Tae Young

    2003-11-01

    DIMAC (A DIspersion Metallic fuel performance Analysis Code) is a computer program for simulating the behavior of dispersion fuel rods under normal operating conditions of HYPER. It computes the one-dimensional temperature distribution and the thermo-mechanical characteristics of fuel rod under the steady state operation condition, including the swelling and rod deformation. DIMAC was developed based on the experience of research reactor fuel. DIMAC consists of the temperature calculation module, the mechanical swelling calculation module, and the fuel deformation calculation module in order to predict the deformation of a dispersion fuel as a function of power history. Because there are a little of available U-TRU-Zr or TRU-Zr characteristics, the material data of U-Pu-Zr or Pu-Zr are used for those of U-TRU-Zr or TRU-Zr. This report is mainly intended as a user's manual for the DIMAC code. The general description on this code, the description on input parameter, the description on each subroutine, the sample problem and the sample input and partial output are written in this repo0008.

  1. FAMIAS User Manual

    Science.gov (United States)

    Zima, Wolfgang

    2008-10-01

    The excitation of pulsation modes in Beta Cephei and Slowly Pulsating B stars is known to be very sensitive to opacity changes in the stellar interior where T ~ 2 x 10E5 K. In this region differences in opacity up to ~ 50% can be induced by the choice between OPAL and OP opacity tables, and between two different metal mixtures (Grevesse & Noels 1993 and Asplund et al. 2005). We have extended the non-adiabatic computations presented in Miglio et al. (2007) towards models of higher mass and pulsation modes of degree l = 3, and we present here the instability domains in the HR- and log P-log Teff diagrams resulting from different choices of opacity tables, and for three different metallicities. FAMIAS (Frequency Analysis and Mode Identification for AsteroSeismology) is a collection of state-of-the-art software tools for the analysis of photometric and spectroscopic time series data. It is one of the deliverables of the Work Package NA5: Asteroseismology of the European Coordination Action in Helio-and Asteroseismology (HELAS). Two main sets of tools are incorporated in FAMIAS. The first set allows to search for periodicities in the data using Fourier and non-linear least-squares fitting algorithms. The other set allows to carry out a mode identification for the detected pulsation frequencies to determine their pulsational quantum numbers, the harmonic degree, m. The types of stars to which famias is applicable are main-sequence pulsators hotter than the Sun. This includes the Gamma Dor stars, Delta Sct stars, the slowly pulsating B stars and the Beta Cep stars - basically all pulsating main-sequence stars, for which empirical mode identification is required to successfully carry out asteroseismology. This user manual describes how to use the different features of FAMIAS and provides two tutorials that demonstrate the usage of FAMIAS for spectroscopic and photometric mode identification.

  2. TMAP7 User Manual

    International Nuclear Information System (INIS)

    Longhurst, Glen R.

    2008-01-01

    The TMAP Code was written at the Idaho National Engineering and Environmental Laboratory by Brad Merrill and James Jones in the late 1980s as a tool for safety analysis of systems involving tritium. Since then it was upgraded to TMAP4 and has been used in numerous applications including experiments supporting fusion safety, predictions for advanced systems such as the International Thermonuclear Experimental Reactor (ITER), and estimates involving tritium production technologies. Its further upgrade to TMAP2000 and now to TMAP7 was accomplished in response to several needs. TMAP and TMAP4 had the capacity to deal with only a single trap for diffusing gaseous species in solid structures. TMAP7 includes up to three separate traps and up to 10 diffusing species. The original code had difficulty dealing with heteronuclear molecule formation such as HD and DT under solution-law dependent diffusion boundary conditions. That difficulty has been overcome. TMAP7 automatically generates heteronuclear molecular partial pressures when solubilities and partial pressures of the homonuclear molecular species are provided for law-dependent diffusion boundary conditions. A further sophistication is the addition of non-diffusing surface species. Atoms such as oxygen or nitrogen or formation and decay or combination of hydroxyl radicals on metal surfaces are sometimes important in reactions with diffusing hydrogen isotopes but do not themselves diffuse appreciably in the material. TMAP7 will accommodate up to 30 such surface species, allowing the user to specify relationships between those surface concentrations and partial pressures of gaseous species above the surfaces or to form them dynamically by combining diffusion species or other surface species. Additionally, TMAP7 allows the user to include a surface binding energy and an adsorption barrier energy. The code includes asymmetrical diffusion between the surface sites and regular diffusion sites in the bulk. All of the

  3. Task 7: ADPAC User's Manual

    Science.gov (United States)

    Hall, E. J.; Topp, D. A.; Delaney, R. A.

    1996-01-01

    The overall objective of this study was to develop a 3-D numerical analysis for compressor casing treatment flowfields. The current version of the computer code resulting from this study is referred to as ADPAC (Advanced Ducted Propfan Analysis Codes-Version 7). This report is intended to serve as a computer program user's manual for the ADPAC code developed under Tasks 6 and 7 of the NASA Contract. The ADPAC program is based on a flexible multiple- block grid discretization scheme permitting coupled 2-D/3-D mesh block solutions with application to a wide variety of geometries. Aerodynamic calculations are based on a four-stage Runge-Kutta time-marching finite volume solution technique with added numerical dissipation. Steady flow predictions are accelerated by a multigrid procedure. An iterative implicit algorithm is available for rapid time-dependent flow calculations, and an advanced two equation turbulence model is incorporated to predict complex turbulent flows. The consolidated code generated during this study is capable of executing in either a serial or parallel computing mode from a single source code. Numerous examples are given in the form of test cases to demonstrate the utility of this approach for predicting the aerodynamics of modem turbomachinery configurations.

  4. STWAVE: Steady-State Spectral Wave Model. Report 1: User's Manual for STWAVE Version 2.0

    National Research Council Canada - National Science Library

    Smith, Jane

    1999-01-01

    .... STWAVE has also been incorporated into the Surface-Water Modeling System, which provides a user interface and supporting software for grid generation, interpolation of current fields, generation...

  5. DESI-Detection of early-season invasives (software-installation manual and user's guide version 1.0)

    Science.gov (United States)

    Kokaly, Raymond F.

    2011-01-01

    This report describes a software system for detecting early-season invasive plant species, such as cheatgrass. The report includes instructions for installing the software and serves as a user's guide in processing Landsat satellite remote sensing data to map the distributions of cheatgrass and other early-season invasive plants. The software was developed for application to the semi-arid regions of southern Utah; however, the detection parameters can be altered by the user for application to other areas.

  6. MARFA version 3.2.2 user's manual: migration analysis of radionuclides in the far field

    Energy Technology Data Exchange (ETDEWEB)

    Painter, Scott; Mancillas, James (Center for Nuclear Waste Regulatory Analyses, Southwest Research Inst., San Antonio, TX (United States))

    2009-12-15

    The computer code Migration Analysis of Radionuclides in the Far Field (MARFA) uses a particle-based Monte Carlo method to simulate the transport of radionuclides in a sparsely fractured geological medium. Transport in sparsely fractured rock is of interest because this medium may serve as a barrier to migration of radionuclides to the accessible environment. The physical processes represented in MARFA include advection, longitudinal dispersion, Fickian diffusion into an infinite or finite rock matrix, equilibrium sorption, decay, and in-growth. Multiple non-branching decay chains of arbitrary length are supported. This document describes the technical basis and input requirements for MARFA Version 3.2.2. MARFA Version 3.2 included new capabilities to accommodate transient flow velocities and sorption parameters, which are assumed to be piecewise constant in time. Version 3.2.1 was a minor change from Version 3.2 to allow a more convenient input format for sorption information. New capabilities in Version 3.2.2 include an option to specify a non-zero start time for the simulation, an optional input parameter that decreases the amount of retention within a single fracture because of flow channeling, and an alternative method for sampling the radionuclide source. MARFA uses the particle on random streamline segment algorithm/Painter et al. 2006/, a Monte Carlo algorithm combining time-domain random walk methods with pathway stochastic simulation. The algorithm uses non-interacting particles to represent packets of radionuclide mass. These particles are moved through the system according to rules that mimic the underlying physical transport and retention processes. The set of times required for particles to pass through the geological barrier are then used to reconstruct discharge rates (mass or activity basis). Because the algorithm uses non-interacting particles, the transport and retention processes are limited to those that depend linearly on radionuclide

  7. User Manual for the Microsoft Window Edition of the Scanning Fast-Field Program (WSCAFFIP) Version 3.0

    National Research Council Canada - National Science Library

    Noble, John

    2003-01-01

    .... This model works over a flat earth and non-turbulent atmosphere. Even with these restrictions, the model performs very well for many Scenarios. The model contains a user-friendly interface that requires a minimum amount of information to run the model, yet there are flags that can be set to obtain more detailed information.

  8. User's manual for the National Water-Quality Assessment Program Invertebrate Data Analysis System (IDAS) software, version 5

    Science.gov (United States)

    Cuffney, Thomas F.; Brightbill, Robin A.

    2011-01-01

    The Invertebrate Data Analysis System (IDAS) software was developed to provide an accurate, consistent, and efficient mechanism for analyzing invertebrate data collected as part of the U.S. Geological Survey National Water-Quality Assessment (NAWQA) Program. The IDAS software is a stand-alone program for personal computers that run Microsoft Windows(Registered). It allows users to read data downloaded from the NAWQA Program Biological Transactional Database (Bio-TDB) or to import data from other sources either as Microsoft Excel(Registered) or Microsoft Access(Registered) files. The program consists of five modules: Edit Data, Data Preparation, Calculate Community Metrics, Calculate Diversities and Similarities, and Data Export. The Edit Data module allows the user to subset data on the basis of taxonomy or sample type, extract a random subsample of data, combine or delete data, summarize distributions, resolve ambiguous taxa (see glossary) and conditional/provisional taxa, import non-NAWQA data, and maintain and create files of invertebrate attributes that are used in the calculation of invertebrate metrics. The Data Preparation module allows the user to select the type(s) of sample(s) to process, calculate densities, delete taxa on the basis of laboratory processing notes, delete pupae or terrestrial adults, combine lifestages or keep them separate, select a lowest taxonomic level for analysis, delete rare taxa on the basis of the number of sites where a taxon occurs and (or) the abundance of a taxon in a sample, and resolve taxonomic ambiguities by one of four methods. The Calculate Community Metrics module allows the user to calculate 184 community metrics, including metrics based on organism tolerances, functional feeding groups, and behavior. The Calculate Diversities and Similarities module allows the user to calculate nine diversity and eight similarity indices. The Data Export module allows the user to export data to other software packages (CANOCO, Primer

  9. CONHOR. Code system for determination of power distribution and burnup for the HOR reactor. Version 1.0.. User's manual

    International Nuclear Information System (INIS)

    Serov, I.V.; Hoogenboom, J.E.

    1993-07-01

    The main calculational tool is the CITATION code. CITATION is used for both static and burnup calculations. The pointwise flux density and power distributions obtained from these calculations are used to obtain the values of the desired quantities at the beginning of a burnup cycle. To obtain the most trustful values of the desired quantities CONHOR employs experimental information together with the CITATION calculated flux distributions. Axially averaged foil activation rates are obtained based on both CITATION pointwise flux density distributions and measured foil activity counts. These two sets of activation rates are called the distributions of auxiliary quantities and are compared with each other in order to pick up the corrections to the U-235 number densities in fuel containing elements. The methodical corrections to the calculational auxiliary quantities are obtained on this basis as well. They are used to obtain the methodical corrections to the desired quantities. The corrected desired quantities are the recommended ones. The correction procedure requires the knowledge of the sensitivity coefficients of the average foil activation rates with respect to the U-235 number densities (through the text of this manual U-235 is denoted also and especially in the input-output description sections as a BUrning-COrrected material, or 'BuCo' material). These sensitivity coefficients are calculated by the CONHOR SENS module. CITATION is employed to perform the calculations with perturbed values of U-235 number densities. Burnup calculations can be performed being based on either corrected or uncorrected U-235 number densities. Through the text of this manual XXXX means a 4-symbol identification of the burnup cycle to be studied. XX-1 and XX+1 mean correspondingly the previous and the following cycles. (orig./HP)

  10. User's manual for the upper Delaware River riverine environmental flow decision support system (REFDSS), Version 1.1.2

    Science.gov (United States)

    Talbert, Colin; Maloney, Kelly O.; Holmquist-Johnson, Chris; Hanson, Leanne

    2014-01-01

    Between 2002 and 2006, the Fort Collins Science Center (FORT) at the U.S. Geological Survey (USGS) conducted field surveys, organized workshops, and performed analysis of habitat for trout and shad in the Upper Delaware River Basin. This work culminated in the development of decision support system software (the Delaware River DSS–DRDSS, Bovee and others, 2007) that works in conjunction with the Delaware River Basin Commission’s reservoir operations model, OASIS, to facilitate comparison of the habitat and water-delivery effects of alternative operating scenarios for the Basin. This original DRDSS application was developed in Microsoft Excel and is available to all interested parties through the FORT web site (http://www.fort.usgs.gov/Products/Software/DRDSS/). Initial user feedback on the original Excel-based DSS highlighted the need for a more user-friendly and powerful interface to effectively deliver the complex data and analyses encapsulated in the DSS. In order to meet this need, the USGS FORT and Northern Appalachian Research Branch (NARB) developed an entirely new graphical user interface (GUI) application. Support for this research was through the DOI WaterSmart program (http://www.doi.gov/watersmart/html/index.php) of which the USGS component is the National Water Census (http://water.usgs.gov/watercensus/WaterSMART.html). The content and methodology of the new GUI interface emulates those of the original DSS with a few exceptions listed below. Refer to Bovee and others (2007) for the original information. Significant alterations to the original DSS include: • We moved from Excel-based data storage and processing to a more powerful database back end powered by SQLite. The most notable effect of this is that the previous maximum temporal extent of 10 years has been replaced by a dynamic extent that can now cover the entire period of record for which we have data (1928–2000). • We incorporated interactive geographic information system (GIS

  11. AVERT User Manual

    Science.gov (United States)

    AVERT is a flexible modeling framework with a simple user interface designed specifically to meet the needs of state air quality planners and other interested stakeholders. Use this guide to get started.

  12. Low-level RF LabVIEW reg-sign control software user's manual: Version 1.0

    International Nuclear Information System (INIS)

    1992-06-01

    This document details information on the low-level radio frequency (LLRF) software control package. The chapters in this manual cover the following topics: Chapter one describes the general operating principles of the LabVIEW software package, and also discusses the high-level menu panels which allow access to the individual control panels. Chapter two covers the control panels used for conditioning the cavity, and for controlling the accelerator under normal operating conditions. Chapter three provides information on the resonance detection and reflectometer calibration function, including the setup and status panels for each. Chapter four contain instructions on the use of those panels dedicated to controlling the cavity RF field. Chapter five discusses the control panels that provide setup and status information on the diagnostic monitor subsystem. Chapter six outlines those panels used to control the timing functions provided by the LLRF system. Finally, chapter seven describes the control panels used to monitor and adjust the alarm and limit functions of the system. Throughout the document, it is assumed that the reader has a general working knowledge of accelerators, high-power amplifier equipment, and low-level RF (LLRF) control systems. References are listed as footnotes as they occur in the text

  13. MAP user's manual copyright

    International Nuclear Information System (INIS)

    Pillsbury, R.D. Jr.

    1991-12-01

    The program MITMAP represents a set of general purpose, two- dimensional, finite element programs for the calculation of magnetic fields. It consists of the program MAP and MAP2DJ. The two programs are used to solve different electromagnetic problems, but they have a common set of subrountines for pre- and postprocessing. Originally separate programs, they have been combined to make modification easier. The manuals, however, will remain separate. The program MAP is described in this manual. MAP is applicable to the class of problems with two-dimensional-planar or axisymmetric - geometries, in which the current density and the magnetic vector potential have only a single nonvanishing component. The single component is associated with the direction that is perpendicular to the plane of the problem and is invariant with respect to that direction. Maxwell's equations can be reduced to a solver diffusion equation in terms of the single, nonvanishing component of the magnetic vector potential for planar problems and to a single component of a vector potential for planar problems and to a single component of a vector diffusion equation for axisymmetric problems. The magnetic permeability appears in the governing equation. The permeability may be a function of the magnetic flux density. In addition, any electrically conducting material present will have eddy currents induced by a time varying magnetic field. These eddy currents must be included in the solution process. This manual provides a description of the structure of the input data and output for the program. There are several example problems presented that illustrate the major program features. Appendices are included that contain a derivation of the governing equations and the application of the finite element method to the solution of the equations

  14. Wien Automatic System Planning (WASP) Package. A computer code for power generating system expansion planning. Version WASP-III Plus. User's manual. Volume 1: Chapters 1-11

    International Nuclear Information System (INIS)

    1995-01-01

    determination of the optimal expansion of combined thermal and hydro power systems, taking into account the optimal operation of the hydro reservoirs throughout the year. Microcomputer (PC) versions of WASP-Ill and MAED have also been developed as stand alone programs and as part of an integrated package for energy and electricity planning called ENPEP (Energy and Power Evaluation Program). A PC version of the VALORAGUA model has also been completed in 1992. With all these developments, the catalogue of planning methodologies offered by the IAEA to its Member States has been upgraded to facilitate the work by electricity planners, WASP in particular is currently accepted as a powerful tool for electric system expansion planning. Nevertheless, experienced users of the program have indicated the need to introduce more enhancements within the WASP model in order to cope with the problems constantly faced by planners owing to the increasing complexity of this type of analysis. With several Member States, the IAEA has completed a new version of the WASP program, which has been called WASP-Ill Plus since it follows quite closely the methodology of the WASP-Ill model. The major enhancements in WASP-Ill Plus with respect to the WASP-Ill version are: increase in the number of thermal fuel types (from 5 to 10); verification of which configurations generated by CONGEN have already been simulated in previous iterations with MERSIM; direct calculation of combined Loading Order of FIXSYS and VARSYS plants; simulation of system operation includes consideration of physical constraints imposed on some fuel types (i.e., fuel availability for electricity generation); extended output of the resimulation of the optimal solution; generation of a file that can be used for graphical representation of the results of the resimulation of the optimal solution and cash flows of the investment costs; calculation of cash flows allows to include the capital costs of plants firmly committed or in construction

  15. Users' Manual and Installation Guide for the EverVIEW Slice and Dice Tool (Version 1.0 Beta)

    Science.gov (United States)

    Roszell, Dustin; Conzelmann, Craig; Chimmula, Sumani; Chandrasekaran, Anuradha; Hunnicut, Christina

    2009-01-01

    Network Common Data Form (NetCDF) is a self-describing, machine-independent file format for storing array-oriented scientific data. Over the past few years, there has been a growing movement within the community of natural resource managers in The Everglades, Fla., to use NetCDF as the standard data container for datasets based on multidimensional arrays. As a consequence, a need arose for additional tools to view and manipulate NetCDF datasets, specifically to create subsets of large NetCDF files. To address this need, we created the EverVIEW Slice and Dice Tool to allow users to create subsets of grid-based NetCDF files. The major functions of this tool are (1) to subset NetCDF files both spatially and temporally; (2) to view the NetCDF data in table form; and (3) to export filtered data to a comma-separated value file format.

  16. PRISM: Processing routines in IDL for spectroscopic measurements (installation manual and user's guide, version 1.0)

    Science.gov (United States)

    Kokaly, Raymond F.

    2011-01-01

    This report describes procedures for installing and using the U.S. Geological Survey Processing Routines in IDL for Spectroscopic Measurements (PRISM) software. PRISM provides a framework to conduct spectroscopic analysis of measurements made using laboratory, field, airborne, and space-based spectrometers. Using PRISM functions, the user can compare the spectra of materials of unknown composition with reference spectra of known materials. This spectroscopic analysis allows the composition of the material to be identified and characterized. Among its other functions, PRISM contains routines for the storage of spectra in database files, import/export of ENVI spectral libraries, importation of field spectra, correction of spectra to absolute reflectance, arithmetic operations on spectra, interactive continuum removal and comparison of spectral features, correction of imaging spectrometer data to ground-calibrated reflectance, and identification and mapping of materials using spectral feature-based analysis of reflectance data. This report provides step-by-step instructions for installing the PRISM software and running its functions.

  17. BBC users manual

    International Nuclear Information System (INIS)

    Ltterst, R.F.; Sutcliffe, W.G.; Warshaw, S.I.

    1977-11-01

    BBC is a two-dimensional, multifluid Eulerian hydro-radiation code based on KRAKEN and some subsequent ideas. It was developed in the explosion group in T-Division as a basic two-dimensional code to which various types of physics can be added. For this reason BBC is a FORTRAN (LRLTRAN) code. In order to gain the 2-to-1 to 4-to-1 speed advantage of the STACKLIB software on the 7600's and to be able to execute at high speed on the STAR, the vector extensions of LRLTRAN (STARTRAN) are used throughout the code. Either cylindrical- or slab-type problems can be run on BBC. The grid is bounded by a rectangular band of boundary zones. The interfaces between the regular and boundary zones can be selected to be either rigid or nonrigid. The setup for BBC problems is described in the KEG Manual and LEG Manual. The difference equations are described in BBC Hydrodynamics. Basic input and output for BBC are described

  18. TOTAL user manual

    Science.gov (United States)

    Johnson, Sally C.; Boerschlein, David P.

    1994-01-01

    Semi-Markov models can be used to analyze the reliability of virtually any fault-tolerant system. However, the process of delineating all of the states and transitions in the model of a complex system can be devastatingly tedious and error-prone. Even with tools such as the Abstract Semi-Markov Specification Interface to the SURE Tool (ASSIST), the user must describe a system by specifying the rules governing the behavior of the system in order to generate the model. With the Table Oriented Translator to the ASSIST Language (TOTAL), the user can specify the components of a typical system and their attributes in the form of a table. The conditions that lead to system failure are also listed in a tabular form. The user can also abstractly specify dependencies with causes and effects. The level of information required is appropriate for system designers with little or no background in the details of reliability calculations. A menu-driven interface guides the user through the system description process, and the program updates the tables as new information is entered. The TOTAL program automatically generates an ASSIST input description to match the system description.

  19. Social Values for Ecosystem Services, version 3.0 (SolVES 3.0): documentation and user manual

    Science.gov (United States)

    Sherrouse, Ben C.; Semmens, Darius J.

    2015-01-01

    The geographic information system (GIS) tool, Social Values for Ecosystem Services (SolVES), was developed to incorporate quantified and spatially explicit measures of social values into ecosystem service assessments. SolVES 3.0 continues to extend the functionality of SolVES, which was designed to assess, map, and quantify the social values of ecosystem services. Social values—the perceived, nonmarket values the public ascribes to ecosystem services, particularly cultural services, such as aesthetics and recreation—can be evaluated for various stakeholder groups. These groups are distinguishable by their attitudes and preferences regarding public uses, such as motorized recreation and logging. As with previous versions, SolVES 3.0 derives a quantitative 10-point, social-values metric—the value index—from a combination of spatial and nonspatial responses to public value and preference surveys. The tool also calculates metrics characterizing the underlying environment, such as average distance to water and dominant landcover. SolVES 3.0 is integrated with Maxent maximum entropy modeling software to generate more complete social-value maps and offer robust statistical models describing the relationship between the value index and explanatory environmental variables. A model’s goodness of fit to a primary study area and its potential performance in transferring social values to similar areas using value-transfer methodology can be evaluated. SolVES 3.0 provides an improved public-domain tool for decision makers and researchers to evaluate the social values of ecosystem services and to facilitate discussions among diverse stakeholders regarding the tradeoffs among ecosystem services in a variety of physical and social contexts ranging from forest and rangeland to coastal and marine.

  20. Tripoli-3: monte Carlo transport code for neutral particles - version 3.5 - users manual; Tripoli-3: code de transport des particules neutres par la methode de monte carlo - version 3.5 - manuel d'utilisation

    Energy Technology Data Exchange (ETDEWEB)

    Vergnaud, Th.; Nimal, J.C.; Chiron, M

    2001-07-01

    The TRIPOLI-3 code applies the Monte Carlo method to neutron, gamma-ray and coupled neutron and gamma-ray transport calculations in three-dimensional geometries, either in steady-state conditions or having a time dependence. It can be used to study problems where there is a high flux attenuation between the source zone and the result zone (studies of shielding configurations or source driven sub-critical systems, with fission being taken into account), as well as problems where there is a low flux attenuation (neutronic calculations -- in a fuel lattice cell, for example -- where fission is taken into account, usually with the calculation on the effective multiplication factor, fine structure studies, numerical experiments to investigate methods approximations, etc). TRIPOLI-3 has been operational since 1995 and is the version of the TRIPOLI code that follows on from TRIPOLI-2; it can be used on SUN, RISC600 and HP workstations and on PC using the Linux or Windows/NT operating systems. The code uses nuclear data libraries generated using the THEMIS/NJOY system. The current libraries were derived from ENDF/B6 and JEF2. There is also a response function library based on a number of evaluations, notably the dosimetry libraries IRDF/85, IRDF/90 and also evaluations from JEF2. The treatment of particle transport is the same in version 3.5 as in version 3.4 of the TRIPOLI code; but the version 3.5 is more convenient for preparing the input data and for reading the output. The french version of the user's manual exists. (authors)

  1. Tripoli-3: monte Carlo transport code for neutral particles - version 3.5 - users manual; Tripoli-3: code de transport des particules neutres par la methode de monte carlo - version 3.5 - manuel d'utilisation

    Energy Technology Data Exchange (ETDEWEB)

    Vergnaud, Th; Nimal, J C; Chiron, M

    2001-07-01

    The TRIPOLI-3 code applies the Monte Carlo method to neutron, gamma-ray and coupled neutron and gamma-ray transport calculations in three-dimensional geometries, either in steady-state conditions or having a time dependence. It can be used to study problems where there is a high flux attenuation between the source zone and the result zone (studies of shielding configurations or source driven sub-critical systems, with fission being taken into account), as well as problems where there is a low flux attenuation (neutronic calculations -- in a fuel lattice cell, for example -- where fission is taken into account, usually with the calculation on the effective multiplication factor, fine structure studies, numerical experiments to investigate methods approximations, etc). TRIPOLI-3 has been operational since 1995 and is the version of the TRIPOLI code that follows on from TRIPOLI-2; it can be used on SUN, RISC600 and HP workstations and on PC using the Linux or Windows/NT operating systems. The code uses nuclear data libraries generated using the THEMIS/NJOY system. The current libraries were derived from ENDF/B6 and JEF2. There is also a response function library based on a number of evaluations, notably the dosimetry libraries IRDF/85, IRDF/90 and also evaluations from JEF2. The treatment of particle transport is the same in version 3.5 as in version 3.4 of the TRIPOLI code; but the version 3.5 is more convenient for preparing the input data and for reading the output. The french version of the user's manual exists. (authors)

  2. Users Manual for TMY3 Data Sets (Revised)

    Energy Technology Data Exchange (ETDEWEB)

    Wilcox, S.; Marion, W.

    2008-05-01

    This users manual describes how to obtain and interpret the data in the Typical Meteorological Year version 3 (TMY3) data sets. These data sets are an update to the TMY2 data released by NREL in 1994.

  3. ASSIST user manual

    Science.gov (United States)

    Johnson, Sally C.; Boerschlein, David P.

    1995-01-01

    Semi-Markov models can be used to analyze the reliability of virtually any fault-tolerant system. However, the process of delineating all the states and transitions in a complex system model can be devastatingly tedious and error prone. The Abstract Semi-Markov Specification Interface to the SURE Tool (ASSIST) computer program allows the user to describe the semi-Markov model in a high-level language. Instead of listing the individual model states, the user specifies the rules governing the behavior of the system, and these are used to generate the model automatically. A few statements in the abstract language can describe a very large, complex model. Because no assumptions are made about the system being modeled, ASSIST can be used to generate models describing the behavior of any system. The ASSIST program and its input language are described and illustrated by examples.

  4. ASTRA Plus User Manual

    OpenAIRE

    MATUZAS Vaidas; CONTINI SERGIO

    2012-01-01

    This report describes the user interface and the main commands to perform system dependability analysis by means of ASTRA Plus. This package implements the analysis methods developed at the Institute for the Protection and Security of the Citizen from mid-2008. ASTRA Plus is composed of the Fault Tree Analysis (FTA) module and of the Concurrent Importance and Sensitivity Analysis (CISA) module. The FTA module contains three different methods for solving a fault tree; all are based on the...

  5. AVRAM user's manual

    International Nuclear Information System (INIS)

    McGrady, P.W.

    1988-02-01

    This document details the use of the reliability code for the Atomic Vapor Laser Isotope Separation (AVLIS) project. This code was designed by Tom Anklam and John Harris. In late 1984 Patrick McGrady and Elena Koontz of C and TD/TA were assigned the task of improving the code and converting it for use on the DEC-10 system. In early 1986, Patric McGrady converted it to the CRAY. The AVRAM code is divided into distinct parts (often referred to as programs in this document). There is a COSMOS file that controls the execution of the FORTRAN code and controls the naming of output datasets and the deletion of temporary datasets created by the code. The FORTRAN code consists of a main program as a driver and of three main subroutines: EDIT, PARAM, and AVRAM. The EDIT program allows the user to create a new user defined system or add to an existing system or to change certain parameters. The PARAM program allows the user to alter system parameters and to select options such as economics run, criticality analysis or sensitivity studies. The AVRAM program does a reliability analysis of the system

  6. XMGR5 users manual

    Energy Technology Data Exchange (ETDEWEB)

    Jones, K.R.; Fisher, J.E.

    1997-03-01

    ACE/gr is XY plotting tool for workstations or X-terminals using X. A few of its features are: User defined scaling, tick marks, labels, symbols, line styles, colors. Batch mode for unattended plotting. Read and write parameters used during a session. Polynomial regression, splines, running averages, DFT/FFT, cross/auto-correlation. Hardcopy support for PostScript, HP-GL, and FrameMaker.mif format. While ACE/gr has a convenient point-and-click interface, most parameter settings and operations are available through a command line interface (found in Files/Commands).

  7. Wien Automatic System Planning (WASP) Package. A computer code for power generating system expansion planning. Version WASP-III Plus. User's manual. Volume 1: Chapters 1-11

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-09-01

    determination of the optimal expansion of combined thermal and hydro power systems, taking into account the optimal operation of the hydro reservoirs throughout the year. Microcomputer (PC) versions of WASP-Ill and MAED have also been developed as stand alone programs and as part of an integrated package for energy and electricity planning called ENPEP (Energy and Power Evaluation Program). A PC version of the VALORAGUA model has also been completed in 1992. With all these developments, the catalogue of planning methodologies offered by the IAEA to its Member States has been upgraded to facilitate the work by electricity planners, WASP in particular is currently accepted as a powerful tool for electric system expansion planning. Nevertheless, experienced users of the program have indicated the need to introduce more enhancements within the WASP model in order to cope with the problems constantly faced by planners owing to the increasing complexity of this type of analysis. With several Member States, the IAEA has completed a new version of the WASP program, which has been called WASP-Ill Plus since it follows quite closely the methodology of the WASP-Ill model. The major enhancements in WASP-Ill Plus with respect to the WASP-Ill version are: increase in the number of thermal fuel types (from 5 to 10); verification of which configurations generated by CONGEN have already been simulated in previous iterations with MERSIM; direct calculation of combined Loading Order of FIXSYS and VARSYS plants; simulation of system operation includes consideration of physical constraints imposed on some fuel types (i.e., fuel availability for electricity generation); extended output of the resimulation of the optimal solution; generation of a file that can be used for graphical representation of the results of the resimulation of the optimal solution and cash flows of the investment costs; calculation of cash flows allows to include the capital costs of plants firmly committed or in construction

  8. WAM-E user's manual

    International Nuclear Information System (INIS)

    Rayes, L.G.; Riley, J.E.

    1986-07-01

    The WAM-E series of mainframe computer codes have been developed to efficiently analyze the large binary models (e.g., fault trees) used to represent the logic relationships within and between the systems of a nuclear power plant or other large, multisystem entity. These codes have found wide application in reliability and safety studies of nuclear power plant systems. There are now nine codes in the WAM-E series, with six (WAMBAM/WAMTAP, WAMCUT, WAMCUT-II, WAMFM, WAMMRG, and SPASM) classified as Type A Production codes and the other three (WAMFTP, WAMTOP, and WAMCONV) classified as Research codes. This document serves as a combined User's Guide, Programmer's Manual, and Theory Reference for the codes, with emphasis on the Production codes. To that end, the manual is divided into four parts: Part I, Introduction; Part II, Theory and Numerics; Part III, WAM-E User's Guide; and Part IV, WAMMRG Programmer's Manual

  9. Slycat™ User Manual

    Energy Technology Data Exchange (ETDEWEB)

    Crossno, Patricia J. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Gittinger, Jaxon [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Hunt, Warren L. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Letter, Matthew [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Martin, Shawn [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Sielicki, Milosz Aleksander [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2018-01-01

    Slycat™ is a web-based system for performing data analysis and visualization of potentially large quantities of remote, high-dimensional data. Slycat™ specializes in working with ensemble data. An ensemble is a group of related data sets, which typically consists of a set of simulation runs exploring the same problem space. An ensemble can be thought of as a set of samples within a multi-variate domain, where each sample is a vector whose value defines a point in high-dimensional space. To understand and describe the underlying problem being modeled in the simulations, ensemble analysis looks for shared behaviors and common features across the group of runs. Additionally, ensemble analysis tries to quantify differences found in any members that deviate from the rest of the group. The Slycat™ system integrates data management, scalable analysis, and visualization. Results are viewed remotely on a user’s desktop via commodity web clients using a multi-tiered hierarchy of computation and data storage, as shown in Figure 1. Our goal is to operate on data as close to the source as possible, thereby reducing time and storage costs associated with data movement. Consequently, we are working to develop parallel analysis capabilities that operate on High Performance Computing (HPC) platforms, to explore approaches for reducing data size, and to implement strategies for staging computation across the Slycat™ hierarchy. Within Slycat™, data and visual analysis are organized around projects, which are shared by a project team. Project members are explicitly added, each with a designated set of permissions. Although users sign-in to access Slycat™, individual accounts are not maintained. Instead, authentication is used to determine project access. Within projects, Slycat™ models capture analysis results and enable data exploration through various visual representations. Although for scientists each simulation run is a model of real-world phenomena given certain

  10. AMBER User's Manual

    International Nuclear Information System (INIS)

    Vay, J.L.; Fawley, W.

    2000-01-01

    AMBER is a Particle-In-Cell (PIC) code which models the evolution of a representative slice of a relativistic electron beam in a linear accelerator. The beam is modeled as a steady flow and therefore no electromagnetic waves: all the fields (external and self-fields) are electrostatic and magnetostatic fields (for a complete description, see chapter 5). The possible elements describing the accelerator lattice are solenoids, accelerating gaps, pipes and apertures. Several kinds of beam distribution can be loaded: KV, gaussian, semi-gaussian, etc. Alternatively, the user can reconstruct (or load) a distribution from the output of another codefile, for example, an interface generating the beam distribution from output produced from EGUN or LSP codes is available as an option. This documentation first describes in detail the input files needed to run AMBER and the procedure to start the executable. The possible data files and graphical output are explained in the two following chapters. The last chapter describes the physics model and numerical techniques used. An example of input files and the result obtained with these inputs are also given in the Appendix

  11. COSIS User's Manual

    International Nuclear Information System (INIS)

    Cho, J. Y.; Lee, K. B.; Koo, B. S.; Lee, W. K.; Lee, C. C.; Zee, S. Q.

    2006-02-01

    COSIS (COre State Indication System) which implemented in the SMART research reactor plays a role to supply the core state parameters or graphs for the operator to recognize the core state effectively. The followings are the main functions of COSIS. Validity Check for the Process Signals and Determination of the COSIS Inputs (SIGVAL), Coolant Flow Rate Calculation (FLOW), Core Thermal Power Calculation (COREPOW), In-core 3-Dimensional Power Distribution Calculation and Peaking Parameters Generation (POWER3D), Azimuthal Tilt Calculation (AZITILT). This report describes the structures of the I/O files that are essential for the users to run COSIS. COSIS handles the following 4 input files. DATABASE: The base input file, COSIS.INP: The signal input file, CCS.DAT: File required for the in-core detector signal processing and the 3-D power distribution calculation, TPFH2O: Steam table for the water properties The DATABASE file contains the base information for a nuclear power plant and is read at the first COSIS calculation. The COSIS.INP file contains the process input and detector signals, and is read by COSIS at every second. CCS.DAT file, that is produced by the COSISMAS code, contains the information for the in-core detector signal processing and the 3-D power distribution calculation. TPFH2O file is a steam table and is written in binary format. COSIS produces the following 4 output files. DATABASE.OUT: The output file for the DATABASE input file, COSIS.OUT: The normal output file produced after the COSIS calculation, COSIS.SUM: File for the operator to recognize the core state effectively, MAS S IG: File to run the COSISMAS code The DATABASE.OUT file is produced right after finishing DATABASE processing. The COSIS.OUT file is produced after finishing the input signal processing and the main COSIS calculation. The COSIS.SUM file is the summary file of the COSIS results for the operator to recognize the core state effectively. The MAS S IG file is the COSISMAS input

  12. THEAP-I: A computer program for thermal hydraulic analysis of a thermally interacting channel bundle of complex geometry. The micro computer version user`s manual

    Energy Technology Data Exchange (ETDEWEB)

    Megaritou, A; Bartzis, J G

    1987-09-01

    In the present report the micro computer version of the code is described. More emphasis is given in the new features of the code (i.e. input data structure). A set of instructions for running in an IBM-AT2 computer with the Microsoft FORTRAN V.4.0 is also included together with a sample problem refering to the Greek Research Reactor.

  13. CONHOR. Code system for determination of power distribution and burnup for the HOR reactor. Version 1.0.. User`s manual

    Energy Technology Data Exchange (ETDEWEB)

    Serov, I V; Hoogenboom, J E

    1993-07-01

    The main calculational tool is the CITATION code. CITATION is used for both static and burnup calculations. The pointwise flux density and power distributions obtained from these calculations are used to obtain the values of the desired quantities at the beginning of a burnup cycle. To obtain the most trustful values of the desired quantities CONHOR employs experimental information together with the CITATION calculated flux distributions. Axially averaged foil activation rates are obtained based on both CITATION pointwise flux density distributions and measured foil activity counts. These two sets of activation rates are called the distributions of auxiliary quantities and are compared with each other in order to pick up the corrections to the U-235 number densities in fuel containing elements. The methodical corrections to the calculational auxiliary quantities are obtained on this basis as well. They are used to obtain the methodical corrections to the desired quantities. The corrected desired quantities are the recommended ones. The correction procedure requires the knowledge of the sensitivity coefficients of the average foil activation rates with respect to the U-235 number densities (through the text of this manual U-235 is denoted also and especially in the input-output description sections as a BUrning-COrrected material, or `BuCo` material). These sensitivity coefficients are calculated by the CONHOR SENS module. CITATION is employed to perform the calculations with perturbed values of U-235 number densities. Burnup calculations can be performed being based on either corrected or uncorrected U-235 number densities. Through the text of this manual XXXX means a 4-symbol identification of the burnup cycle to be studied. XX-1 and XX+1 mean correspondingly the previous and the following cycles. (orig./HP).

  14. CMGTooL user's manual

    Science.gov (United States)

    Xu, Jingping; Lightsom, Fran; Noble, Marlene A.; Denham, Charles

    2002-01-01

    During the past several years, the sediment transport group in the Coastal and Marine Geology Program (CMGP) of the U. S. Geological Survey has made major revisions to its methodology of processing, analyzing, and maintaining the variety of oceanographic time-series data. First, CMGP completed the transition of the its oceanographic time-series database to a self-documenting NetCDF (Rew et al., 1997) data format. Second, CMGP’s oceanographic data variety and complexity have been greatly expanded from traditional 2-dimensional, single-point time-series measurements (e.g., Electro-magnetic current meters, transmissometers) to more advanced 3-dimensional and profiling time-series measurements due to many new acquisitions of modern instruments such as Acoustic Doppler Current Profiler (RDI, 1996), Acoustic Doppler Velocitimeter, Pulse-Coherence Acoustic Doppler Profiler (SonTek, 2001), Acoustic Bacscatter Sensor (Aquatec, 1001001001001001001). In order to accommodate the NetCDF format of data from the new instruments, a software package of processing, analyzing, and visualizing time-series oceanographic data was developed. It is named CMGTooL. The CMGTooL package contains two basic components: a user-friendly GUI for NetCDF file analysis, processing and manipulation; and a data analyzing program library. Most of the routines in the library are stand-alone programs suitable for batch processing. CMGTooL is written in MATLAB computing language (The Mathworks, 1997), therefore users must have MATLAB installed on their computer in order to use this software package. In addition, MATLAB’s Signal Processing Toolbox is also required by some CMGTooL’s routines. Like most MATLAB programs, all CMGTooL codes are compatible with different computing platforms including PC, MAC, and UNIX machines (Note: CMGTooL has been tested on different platforms that run MATLAB 5.2 (Release 10) or lower versions. Some of the commands related to MAC may not be compatible with later releases

  15. FBR metallic materials test manual (English version)

    International Nuclear Information System (INIS)

    Odaka, Susumu; Kato, Shoichi; Yoshida, Eiichi

    2003-06-01

    For the development of the fast breeder reactor, this manual describes the method of in-air and in-sodium material tests and the method of organization the data. This previous manual has revised in accordance with the revision of Japanese Industrial Standard (JIS) and the conversion to the international unit. The test methods of domestic committees such as the VAMAS (Versailles Project on Advanced Materials and Standards) workshop were also refereed. The material test technologies accumulated in this group until now were also incorporated. This English version was prepared in order to provide more engineers with the FBR metallic materials test manual. (author)

  16. GWSCREEN: A semi-analytical model for assessment of the groundwater pathway from surface or buried contamination: Version 2.0 theory and user`s manual

    Energy Technology Data Exchange (ETDEWEB)

    Rood, A.S.

    1993-06-01

    GWSCREEN was developed for assessment of the groundwater pathway from leaching of radioactive and non radioactive substances from surface or buried sources. The code was designed for implementation in the Track I and Track II assessment of CERCLA (Comprehensive Environmental Response, Compensation and Liability Act) sites identified as low probability hazard at the Idaho National Engineering Laboratory (DOE, 1992). The code calculates the limiting soil concentration such that, after leaching and transport to the aquifer, regulatory contaminant levels in groundwater are not exceeded. The code uses a mass conservation approach to model three processes: contaminant release from a source volume, contaminant transport in the unsaturated zone, and contaminant transport in the saturated zone. The source model considers the sorptive properties and solubility of the contaminant. Transport in the unsaturated zone is described by a plug flow model. Transport in the saturated zone is calculated with a semi-analytical solution to the advection dispersion equation in groundwater. In Version 2.0, GWSCREEN has incorporated an additional source model to calculate the impacts to groundwater resulting from the release to percolation ponds. In addition, transport of radioactive progeny has also been incorporated. GWSCREEN has shown comparable results when compared against other codes using similar algorithms and techniques. This code was designed for assessment and screening of the groundwater pathway when field data is limited. It was not intended to be a predictive tool.

  17. EQ3NR, a computer program for geochemical aqueous speciation-solubility calculations: Theoretical manual, user`s guide, and related documentation (Version 7.0); Part 3

    Energy Technology Data Exchange (ETDEWEB)

    Wolery, T.J.

    1992-09-14

    EQ3NR is an aqueous solution speciation-solubility modeling code. It is part of the EQ3/6 software package for geochemical modeling. It computes the thermodynamic state of an aqueous solution by determining the distribution of chemical species, including simple ions, ion pairs, and complexes, using standard state thermodynamic data and various equations which describe the thermodynamic activity coefficients of these species. The input to the code describes the aqueous solution in terms of analytical data, including total (analytical) concentrations of dissolved components and such other parameters as the pH, pHCl, Eh, pe, and oxygen fugacity. The input may also include a desired electrical balancing adjustment and various constraints which impose equilibrium with special pure minerals, solid solution end-member components (of specified mole fractions), and gases (of specified fugacities). The code evaluates the degree of disequilibrium in terms of the saturation index (SI = 1og Q/K) and the thermodynamic affinity (A = {minus}2.303 RT log Q/K) for various reactions, such as mineral dissolution or oxidation-reduction in the aqueous solution itself. Individual values of Eh, pe, oxygen fugacity, and Ah (redox affinity) are computed for aqueous redox couples. Equilibrium fugacities are computed for gas species. The code is highly flexible in dealing with various parameters as either model inputs or outputs. The user can specify modification or substitution of equilibrium constants at run time by using options on the input file.

  18. EQ6, a computer program for reaction path modeling of aqueous geochemical systems: Theoretical manual, user`s guide, and related documentation (Version 7.0); Part 4

    Energy Technology Data Exchange (ETDEWEB)

    Wolery, T.J.; Daveler, S.A.

    1992-10-09

    EQ6 is a FORTRAN computer program in the EQ3/6 software package (Wolery, 1979). It calculates reaction paths (chemical evolution) in reacting water-rock and water-rock-waste systems. Speciation in aqueous solution is an integral part of these calculations. EQ6 computes models of titration processes (including fluid mixing), irreversible reaction in closed systems, irreversible reaction in some simple kinds of open systems, and heating or cooling processes, as well as solve ``single-point`` thermodynamic equilibrium problems. A reaction path calculation normally involves a sequence of thermodynamic equilibrium calculations. Chemical evolution is driven by a set of irreversible reactions (i.e., reactions out of equilibrium) and/or changes in temperature and/or pressure. These irreversible reactions usually represent the dissolution or precipitation of minerals or other solids. The code computes the appearance and disappearance of phases in solubility equilibrium with the water. It finds the identities of these phases automatically. The user may specify which potential phases are allowed to form and which are not. There is an option to fix the fugacities of specified gas species, simulating contact with a large external reservoir. Rate laws for irreversible reactions may be either relative rates or actual rates. If any actual rates are used, the calculation has a time frame. Several forms for actual rate laws are programmed into the code. EQ6 is presently able to model both mineral dissolution and growth kinetics.

  19. User's manual (UM) for the enhanced logistics intratheater support tool (ELIST) software segment version 8.1.0.0 for solaris 7.; TOPICAL

    International Nuclear Information System (INIS)

    Dritz, K.

    2002-01-01

    This document is the User's Manual (UM) for the Enhanced Logistics Intratheater Support Tool (ELIST) Software Segment. It tells how to use the end-user and administrative features of the segment. The instructions in Sections 4.2.1, 5.3.1, and 5.3.2 for the end-user features (Run ELIST and Run ETEdit) only cover the launching of those features in the DII COE environment; full details on the operation of ELIST and ETEdit in any environment can be found in the documents listed in Section 2.1.3 and referenced elsewhere in this document. On the other hand, complete instructions for the administrative features (Add Map Data and Delete Map Data) are presented in Sections 4.2.2, 5.3.3, and 5.3.4 of this document

  20. HTGR Cost Model Users' Manual

    International Nuclear Information System (INIS)

    Gandrik, A.M.

    2012-01-01

    The High Temperature Gas-Cooler Reactor (HTGR) Cost Model was developed at the Idaho National Laboratory for the Next Generation Nuclear Plant Project. The HTGR Cost Model calculates an estimate of the capital costs, annual operating and maintenance costs, and decommissioning costs for a high-temperature gas-cooled reactor. The user can generate these costs for multiple reactor outlet temperatures; with and without power cycles, including either a Brayton or Rankine cycle; for the demonstration plant, first of a kind, or nth of a kind project phases; for a single or four-pack configuration; and for a reactor size of 350 or 600 MWt. This users manual contains the mathematical models and operating instructions for the HTGR Cost Model. Instructions, screenshots, and examples are provided to guide the user through the HTGR Cost Model. This model was design for users who are familiar with the HTGR design and Excel. Modification of the HTGR Cost Model should only be performed by users familiar with Excel and Visual Basic.

  1. LAURA Users Manual: 5.2-43231

    Science.gov (United States)

    Mazaheri, Alireza; Gnoffo, Peter A.; Johnston, Christopher O.; Kleb, Bil

    2009-01-01

    This users manual provides in-depth information concerning installation and execution of LAURA, version 5. LAURA is a structured, multi-block, computational aerothermodynamic simulation code. Version 5 represents a major refactoring of the original Fortran 77 LAURA code toward a modular structure afforded by Fortran 95. The refactoring improved usability and maintainability by eliminating the requirement for problem-dependent re-compilations, providing more intuitive distribution of functionality, and simplifying interfaces required for multiphysics coupling. As a result, LAURA now shares gas-physics modules, MPI modules, and other low-level modules with the FUN3D unstructured-grid code. In addition to internal refactoring, several new features and capabilities have been added, e.g., a GNU-standard installation process, parallel load balancing, automatic trajectory point sequencing, free-energy minimization, and coupled ablation and flowfield radiation.

  2. Laura Users Manual: 5.1-41601

    Science.gov (United States)

    Mazaheri, Alireza; Gnoffo, Peter A.; Johnston, Christopher O.; Kleb, Bil

    2009-01-01

    This users manual provides in-depth information concerning installation and execution of LAURA, version 5. LAURA is a structured, multi-block, computational aerothermodynamic simulation code. Version 5 represents a major refactoring of the original Fortran 77 LAURA code toward a modular structure afforded by Fortran 95. The refactoring improved usability and maintainability by eliminating the requirement for problem-dependent re-compilations, providing more intuitive distribution of functionality, and simplifying interfaces required for multiphysics coupling. As a result, LAURA now shares gas-physics modules, MPI modules, and other low-level modules with the FUN3D unstructured-grid code. In addition to internal refactoring, several new features and capabilities have been added, e.g., a GNU-standard installation process, parallel load balancing, automatic trajectory point sequencing, free-energy minimization, and coupled ablation and flowfield radiation.

  3. LAURA Users Manual: 5.3-48528

    Science.gov (United States)

    Mazaheri, Alireza; Gnoffo, Peter A.; Johnston, Chirstopher O.; Kleb, Bil

    2010-01-01

    This users manual provides in-depth information concerning installation and execution of LAURA, version 5. LAURA is a structured, multi-block, computational aerothermodynamic simulation code. Version 5 represents a major refactoring of the original Fortran 77 LAURA code toward a modular structure afforded by Fortran 95. The refactoring improved usability and maintainability by eliminating the requirement for problem-dependent re-compilations, providing more intuitive distribution of functionality, and simplifying interfaces required for multi-physics coupling. As a result, LAURA now shares gas-physics modules, MPI modules, and other low-level modules with the FUN3D unstructured-grid code. In addition to internal refactoring, several new features and capabilities have been added, e.g., a GNU-standard installation process, parallel load balancing, automatic trajectory point sequencing, free-energy minimization, and coupled ablation and flowfield radiation.

  4. LAURA Users Manual: 5.5-64987

    Science.gov (United States)

    Mazaheri, Alireza; Gnoffo, Peter A.; Johnston, Christopher O.; Kleb, William L.

    2013-01-01

    This users manual provides in-depth information concerning installation and execution of LAURA, version 5. LAURA is a structured, multi-block, computational aerothermodynamic simulation code. Version 5 represents a major refactoring of the original Fortran 77 LAURA code toward a modular structure afforded by Fortran 95. The refactoring improved usability and maintain ability by eliminating the requirement for problem dependent recompilations, providing more intuitive distribution of functionality, and simplifying interfaces required for multi-physics coupling. As a result, LAURA now shares gas-physics modules, MPI modules, and other low-level modules with the Fun3D unstructured-grid code. In addition to internal refactoring, several new features and capabilities have been added, e.g., a GNU standard installation process, parallel load balancing, automatic trajectory point sequencing, free-energy minimization, and coupled ablation and flowfield radiation.

  5. LAURA Users Manual: 5.4-54166

    Science.gov (United States)

    Mazaheri, Alireza; Gnoffo, Peter A.; Johnston, Christopher O.; Kleb, Bil

    2011-01-01

    This users manual provides in-depth information concerning installation and execution of Laura, version 5. Laura is a structured, multi-block, computational aerothermodynamic simulation code. Version 5 represents a major refactoring of the original Fortran 77 Laura code toward a modular structure afforded by Fortran 95. The refactoring improved usability and maintainability by eliminating the requirement for problem dependent re-compilations, providing more intuitive distribution of functionality, and simplifying interfaces required for multi-physics coupling. As a result, Laura now shares gas-physics modules, MPI modules, and other low-level modules with the Fun3D unstructured-grid code. In addition to internal refactoring, several new features and capabilities have been added, e.g., a GNU-standard installation process, parallel load balancing, automatic trajectory point sequencing, free-energy minimization, and coupled ablation and flowfield radiation.

  6. Users Manual for the FEHMN application

    International Nuclear Information System (INIS)

    Zyvoloski, G.A.; Robinson, B.A.; Dash, Z.V.; Trease, L.L.

    1996-01-01

    The user's manual documents the use of the Yucca Mountain Site Characterization Projects Finite element heat and mass transfer code (FEHMN) application. The manual covers: Program considerations, data files, input data, output, system interface, and examples

  7. User manual of UNF code

    International Nuclear Information System (INIS)

    Zhang Jingshang

    2001-01-01

    The UNF code (2001 version) written in FORTRAN-90 is developed for calculating fast neutron reaction data of structure materials with incident energies from about 1 Kev up to 20 Mev. The code consists of the spherical optical model, the unified Hauser-Feshbach and exciton model. The man nal of the UNF code is available for users. The format of the input parameter files and the output files, as well as the functions of flag used in UNF code, are introduced in detail, and the examples of the format of input parameters files are given

  8. The National Energy Audit (NEAT) Engineering Manual (Version 6)

    Energy Technology Data Exchange (ETDEWEB)

    Gettings, M.B.

    2001-04-20

    Government-funded weatherization assistance programs resulted from increased oil prices caused by the 1973 oil embargo. These programs were instituted to reduce US consumption of oil and help low-income families afford the increasing cost of heating their homes. In the summer of 1988, Oak Ridge National Laboratory (ORNL) began providing technical support to the Department of Energy (DOE) Weatherization Assistance Program (WAP). A preliminary study found no suitable means of cost-effectively selecting energy efficiency improvements (measures) for single-family homes that incorporated all the factors seen as beneficial in improving cost-effectiveness and usability. In mid-1989, ORNL was authorized to begin development of a computer-based measure selection technique. In November of 1992 a draft version of the program was made available to all WAP state directors for testing. The first production release, Version 4.3, was made available in october of 1993. The Department of Energy's Weatherization Assistance Program has continued funding improvements to the program increasing its user-friendliness and applicability. initial publication of this engineering manual coincides with availability of Version 6.1, November 1997, though algorithms described generally apply to all prior versions. Periodic updates of specific sections in the manual will permit maintaining a relevant document. This Engineering Manual delineates the assumptions used by NEAT in arriving at the measure recommendations based on the user's input of the building characteristics. Details of the actual data entry are available in the NEAT User's Manual (ORNL/Sub/91-SK078/1) and will not be discussed in this manual.

  9. Salinas. Theory Manual Version 2.8

    Energy Technology Data Exchange (ETDEWEB)

    Reese, Garth M. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Walsh, Timothy [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Bhardwaj, Manoj K. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2009-02-01

    Salinas provides a massively parallel implementation of structural dynamics finite element analysis, required for high fidelity, validated models used in modal, vibration, static and shock analysis of structural systems. This manual describes the theory behind many of the constructs in Salinas. For a more detailed description of how to use Salinas , we refer the reader to Salinas, Users Notes. Many of the constructs in Salinas are pulled directly from published material. Where possible, these materials are referenced herein. However, certain functions in Salinas are specific to our implementation. We try to be far more complete in those areas. The theory manual was developed from several sources including general notes, a programmer notes manual, the user's notes and of course the material in the open literature.

  10. THREETRAN (hex, z) users' manual

    International Nuclear Information System (INIS)

    Walters, W.F.; O'Dell, R.D.; Brinkley, F.W. Jr.

    1979-10-01

    THREETRAN (hex,z) is a three-dimensional, multigroup, discrete-ordinates neutral-particle transport code for use in solving problems in hexagonal, z geometries. An efficient and flexible data management strategy is incorporated and uses three hierarchies of storage: fast core (or small core memory), extended core (or large core memory), and random access disk. Both isotropic (P 0 ) and linearly anisotropic (P 1 ) scattering can be treated. This manual is intended to be a guide for the users of THREETRAN (hex,z) in setting up problem input and in interpreting the output. It is not intended to provide a description of code theory or architecture. 5 figures, 4 tables

  11. Generic communications index: User's manual

    International Nuclear Information System (INIS)

    Dean, R.S.; Steinbrecher, D.H.; Hennick, A.

    1987-12-01

    This report is a manual for providing information required to use a special computer program developed by the NRC for indexing generic communications. The program is written in a user-friendly menu driven form using dBASE III programming language. It facilitates use of the required dBASE III search and sort capabilities to access records in a database called Generic Communications Index. This index is made up of one record each for all bulletins, circulars, and information notices, including revisions and supplements, from 1971, when such documentation started, through 1986 (or to the latest update). The program is designed for use by anyone modestly acquainted with the general use of IBM-compatible personal computers. The manual contains both a brief overview and a detailed description of the program, as well as detailed instructions for getting started using the program on a personal computer with either a two-floppy disk or a hard disk system. Included at the end are a brief description of how to handle problems which might occur, and notes on the makeup of the program and database files for help in adding records of communications for future years

  12. INTRA/Mod3.2. Manual and code description. Volume 2 - User`s manual

    Energy Technology Data Exchange (ETDEWEB)

    Andersson, Jenny; Edlund, O.; Hermann, J.; Johansson, Lise-Lotte

    1999-01-01

    The INTRA Manual consists of two volumes. Volume I of the manual is a thorough description of the code INTRA, the physical modelling of INTRA and the ruling numerics, and volume II, the User`s Manual is an input description. This document, the User`s Manual, Volume II, contains a detailed description of how to use INTRA, how to set up an input file, how to run INTRA and also post-processing

  13. User manual for EXCALIBUR: A FE-BI numerical laboratory for cavity-backed antennas in a circular cylinder, version 1.2

    Science.gov (United States)

    Kempel, Leo C.

    1994-01-01

    The Finite Element-Boundary Integral (FE-BI) technique was used to analyze the scattering and radiation properties of cavity-backed patch antennas recessed in a metallic groundplane. A program, CAVITY3D, was written and found to yield accurate results for large arrays without the usual high memory and computational demand associated with competing formulations. Recently, the FE-BI approach was extended to cavity-backed antennas recessed in an infinite, metallic circular cylinder. EXCALIBUR is a computer program written in the Radiation Laboratory of the University of Michigan which implements this formulation. This user manual gives a brief introduction to EXCALIBUR and some hints as to its proper use. As with all computational electromagnetics programs (especially finite element programs), skilled use and best performance are only obtained through experience. However, several important aspects of the program such as portability, geometry generation, interpretation of results, and custom modification are addressed.

  14. Zgoubi user`s guide. Version 4

    Energy Technology Data Exchange (ETDEWEB)

    Meot, F. [Fermi National Accelerator Lab., Batavia, IL (United States). Dept. of Physics; Valero, S. [CEA, Gif-sur-Yvette (France)

    1997-10-15

    The computer code Zgoubi calculates trajectories of charged particles in magnetic and electric fields. At the origin specially adapted to the definition and adjustment of beam lines and magnetic spectrometers, it has so-evolved that it allows the study of systems including complex sequences of optical elements such as dipoles, quadrupoles, arbitrary multipoles and other magnetic or electric devices, and is able as well to handle periodic structures. Compared to other codes, it presents several peculiarities: (1) a numerical method for integrating the Lorentz equation, based on Taylor series, which optimizes computing time and provides high accuracy and strong symplecticity, (2) spin tracking, using the same numerical method as for the Lorentz equation, (3) calculation of the synchrotron radiation electric field and spectra in arbitrary magnetic fields, from the ray-tracing outcomes, (4) the possibility of using a mesh, which allows ray-tracing from simulated or measured (1-D, 2-D or 3-D) field maps, (5) Monte Carlo procedures: unlimited number of trajectories, in-flight decay, etc. (6) built-in fitting procedure, (7) multiturn tracking in circular accelerators including many features proper to machine parameter calculation and survey, and also the simulation of time-varying power supplies. The initial version of the Code, dedicated to the ray-tracing in magnetic fields, was developed by D. Garreta and J.C. Faivre at CEN-Saclay in the early 1970`s. It was perfected for the purpose of studying the four spectrometers (SPES I, II, III, IV) at the Laboratoire National Saturne (CEA-Saclay, France), and SPEG at Ganil (Caen, France). It is now in use in several national and foreign laboratories. This manual is intended only to describe the details of the most recent version of Zogoubi, which is far from being a {open_quotes}finished product{close_quotes}.

  15. PROSA version 4.0 manual

    International Nuclear Information System (INIS)

    Bicking, U.; Golly, W.; Peter, N.; Seifert, R.

    1991-05-01

    This report includes a comprehensive manual of the computer program PROSA which illustrate the handling and functioning of PROSA. The manual PROSA 4.0 (FORTRAN 77) describes the PC Version of PROSA including its program moduls. The PROSA program package is a statistical tool to decide on the basis of statistical assumptions whether in a given sequence of material balance periods a loss of material might have occurred. The evaluation of the material balance data is based on statistical test procedures. In the present PROSA Version 4.0 the three tests CUMUF test, PAGE's test and GEMUF test are applied to a sequence of material balances. PROSA Version 4.0 supports a real sequential evaluation. That means, PROSA is not only able to evaluate a series of MUF values sequentially after the campaign has finished, but also real sequentially during the campaign. PROSA Version 4.0 is a menu-guided computer program. Data input can be performed either by diskette or by key-enter. Result output is primarily an information whether or not an alarm is indicated. This information can be displayed either numerically or graphically. Therefore, a comfortable graphical output utility is attached to PROSA 4.0. The program moduls are compiled and linked with the Ryan Mc-Farland Compiler. The PROSA graphical utility uses the PLOT88 Library of Plotworks, Inc. (orig./HP) [de

  16. Elemental ABAREX -- a user's manual

    International Nuclear Information System (INIS)

    Smith, A.B.

    1999-01-01

    ELEMENTAL ABAREX is an extended version of the spherical optical-statistical model code ABAREX, designed for the interpretation of neutron interactions with elemental targets consisting of up to ten isotopes. The contributions from each of the isotopes of the element are explicitly dealt with, and combined for comparison with the elemental observables. Calculations and statistical fitting of experimental data are considered. The code is written in FORTRAN-77 and arranged for use on the IBM-compatible personal computer (PC), but it should operate effectively on a number of other systems, particularly VAX/VMS and IBM work stations. Effort is taken to make the code user friendly. With this document a reasonably skilled individual should become fluent with the use of the code in a brief period of time

  17. Users' manual for LEHGC: A Lagrangian-Eulerian Finite-Element Model of Hydrogeochemical Transport Through Saturated-Unsaturated Media. Version 1.1

    International Nuclear Information System (INIS)

    Yeh, Gour-Tsyh

    1995-11-01

    The computer program LEHGC is a Hybrid Lagrangian-Eulerian Finite-Element Model of HydroGeo-Chemical (LEHGC) Transport Through Saturated-Unsaturated Media. LEHGC iteratively solves two-dimensional transport and geochemical equilibrium equations and is a descendant of HYDROGEOCHEM, a strictly Eulerian finite-element reactive transport code. The hybrid Lagrangian-Eulerian scheme improves on the Eulerian scheme by allowing larger time steps to be used in the advection-dominant transport calculations. This causes less numerical dispersion and alleviates the problem of calculated negative concentrations at sharp concentration fronts. The code also is more computationally efficient than the strictly Eulerian version. LEHGC is designed for generic application to reactive transport problems associated with contaminant transport in subsurface media. Input to the program includes the geometry of the system, the spatial distribution of finite elements and nodes, the properties of the media, the potential chemical reactions, and the initial and boundary conditions. Output includes the spatial distribution of chemical element concentrations as a function of time and space and the chemical speciation at user-specified nodes. LEHGC Version 1.1 is a modification of LEHGC Version 1.0. The modification includes: (1) devising a tracking algorithm with the computational effort proportional to N where N is the number of computational grid nodes rather than N 2 as in LEHGC Version 1.0, (2) including multiple adsorbing sites and multiple ion-exchange sites, (3) using four preconditioned conjugate gradient methods for the solution of matrix equations, and (4) providing a model for some features of solute transport by colloids

  18. AFM-CMM integrated instrument user manual

    DEFF Research Database (Denmark)

    Marinello, Francesco; Bariani, Paolo

    This manual gives general important guidelines for a proper use of the integrated AFM-CMM instrument. More information can be collected reading: • N. Kofod Ph.D thesis [1]; • P. Bariani Ph.D thesis [2]; • Dualscope DME 95-200 operation manuals [3]; • SPIP help [4] • Stitching software user manual...

  19. Clean Lead Facility Inventory System user's manual

    International Nuclear Information System (INIS)

    Garcia, J.F.

    1994-12-01

    The purpose of this user's manual is to provide instruction and guidance needed to enter and maintain inventory information for the Clean Lead Facility (CLF), PER-612. Individuals responsible for maintaining and using the system should study and understand the information provided. The user's manual describes how to properly use and maintain the CLF Inventory System. Annual, quarterly, monthly, and current inventory reports may be printed from the Inventory System for reporting purposes. Profile reports of each shipment of lead may also be printed for verification and documentation of lead transactions. The CLF Inventory System was designed on Microsoft Access version 2.0. Similar inventory systems are in use at the Idaho National Engineering Laboratory (INEL) to facilitate site-wide compilations of mixed waste data. The CLF Inventory System was designed for inventorying the clean or non-radioactive contaminated lead stored at the CLF. This data, along with the mixed waste data, will be compiled into the Idaho Mixed Waste Information (IMWI) system for reporting to the Department of Energy Idaho Office, Department of Energy Headquarters, and/or the State of Idaho

  20. ADPAC v1.0: User's Manual

    Science.gov (United States)

    Hall, Edward J.; Heidegger, Nathan J.; Delaney, Robert A.

    1999-01-01

    The overall objective of this study was to evaluate the effects of turbulence models in a 3-D numerical analysis on the wake prediction capability. The current version of the computer code resulting from this study is referred to as ADPAC v7 (Advanced Ducted Propfan Analysis Codes -Version 7). This report is intended to serve as a computer program user's manual for the ADPAC code used and modified under Task 15 of NASA Contract NAS3-27394. The ADPAC program is based on a flexible multiple-block and discretization scheme permitting coupled 2-D/3-D mesh block solutions with application to a wide variety of geometries. Aerodynamic calculations are based on a four-stage Runge-Kutta time-marching finite volume solution technique with added numerical dissipation. Steady flow predictions are accelerated by a multigrid procedure. Turbulence models now available in the ADPAC code are: a simple mixing-length model, the algebraic Baldwin-Lomax model with user defined coefficients, the one-equation Spalart-Allmaras model, and a two-equation k-R model. The consolidated ADPAC code is capable of executing in either a serial or parallel computing mode from a single source code.

  1. Wien Automatic System Package (WASP). A computer code for power generating system expansion planning. Version WASP-III Plus. User's manual. Volume 2: Appendices

    International Nuclear Information System (INIS)

    1995-01-01

    With several Member States, the IAEA has completed a new version of the WASP program, which has been called WASP-Ill Plus since it follows quite closely the methodology of the WASP-Ill model. The major enhancements in WASP-Ill Plus with respect to the WASP-Ill version are: increase in the number of thermal fuel types (from 5 to 10); verification of which configurations generated by CONGEN have already been simulated in previous iterations with MERSIM; direct calculation of combined Loading Order of FIXSYS and VARSYS plants; simulation of system operation includes consideration of physical constraints imposed on some fuel types (i.e., fuel availability for electricity generation); extended output of the resimulation of the optimal solution; generation of a file that can be used for graphical representation of the results of the resimulation of the optimal solution and cash flows of the investment costs; calculation of cash flows allows to include the capital costs of plants firmly committed or in construction (FIXSYS plants); user control of the distribution of capital cost expenditures during the construction period (if required to be different from the general 'S' curve distribution used as default). This second volume of the document to support use of the WASP-Ill Plus computer code consists of 5 appendices giving some additional information about the WASP-Ill Plus program. Appendix A is mainly addressed to the WASP-Ill Plus system analyst and supplies some information which could help in the implementation of the program on the user computer facilities. This appendix also includes some aspects about WASP-Ill Plus that could not be treated in detail in Chapters 1 to 11. Appendix B identifies all error and warning messages that may appear in the WASP printouts and advises the user how to overcome the problem. Appendix C presents the flow charts of the programs along with a brief description of the objectives and structure of each module. Appendix D describes the

  2. A user's manual to the PMBOK guide

    CERN Document Server

    Stackpole Snyder, Cynthia

    2013-01-01

    The must-have manual to understand and use the latest edition of the Fifth Edition The professional standard in the field of project management, A Guide to the Project Management Body of Knowledge (PMBOK® Guide-Fifth Edition) published by the Project Management Institute (PMI) serves as the ultimate resource for professionals and as a valuable studying and training device for students taking the PMP® Exam. A User''s Manual to the PMBOK® Guide takes the next logical step to act as a true user''s manual. With an accessible format and easy-to-understand language, it helps to not only distill es

  3. PROTEUS-SN User Manual

    Energy Technology Data Exchange (ETDEWEB)

    Shemon, Emily R. [Argonne National Lab. (ANL), Argonne, IL (United States); Smith, Micheal A. [Argonne National Lab. (ANL), Argonne, IL (United States); Lee, Changho [Argonne National Lab. (ANL), Argonne, IL (United States)

    2016-02-16

    is a part of the SHARP multi-physics suite for coupled multi-physics analysis of nuclear reactors. This user manual describes how to set up a neutron transport simulation with the PROTEUS-SN code. A companion methodology manual describes the theory and algorithms within PROTEUS-SN.

  4. CASKS (Computer Analysis of Storage casKS): A microcomputer based analysis system for storage cask design review. User's manual to Version 1b (including program reference)

    International Nuclear Information System (INIS)

    Chen, T.F.; Gerhard, M.A.; Trummer, D.J.; Johnson, G.L.; Mok, G.C.

    1995-02-01

    CASKS (Computer Analysis of Storage casKS) is a microcomputer-based system of computer programs and databases developed at the Lawrence Livermore National Laboratory (LLNL) for evaluating safety analysis reports on spent-fuel storage casks. The bulk of the complete program and this user's manual are based upon the SCANS (Shipping Cask ANalysis System) program previously developed at LLNL. A number of enhancements and improvements were added to the original SCANS program to meet requirements unique to storage casks. CASKS is an easy-to-use system that calculates global response of storage casks to impact loads, pressure loads and thermal conditions. This provides reviewers with a tool for an independent check on analyses submitted by licensees. CASKS is based on microcomputers compatible with the IBM-PC family of computers. The system is composed of a series of menus, input programs, cask analysis programs, and output display programs. All data is entered through fill-in-the-blank input screens that contain descriptive data requests

  5. DAKOTA : a multilevel parallel object-oriented framework for design optimization, parameter estimation, uncertainty quantification, and sensitivity analysis. Version 5.0, user's manual.

    Energy Technology Data Exchange (ETDEWEB)

    Eldred, Michael Scott; Dalbey, Keith R.; Bohnhoff, William J.; Adams, Brian M.; Swiler, Laura Painton; Hough, Patricia Diane (Sandia National Laboratories, Livermore, CA); Gay, David M.; Eddy, John P.; Haskell, Karen H.

    2010-05-01

    The DAKOTA (Design Analysis Kit for Optimization and Terascale Applications) toolkit provides a flexible and extensible interface between simulation codes and iterative analysis methods. DAKOTA contains algorithms for optimization with gradient and nongradient-based methods; uncertainty quantification with sampling, reliability, and stochastic finite element methods; parameter estimation with nonlinear least squares methods; and sensitivity/variance analysis with design of experiments and parameter study methods. These capabilities may be used on their own or as components within advanced strategies such as surrogate-based optimization, mixed integer nonlinear programming, or optimization under uncertainty. By employing object-oriented design to implement abstractions of the key components required for iterative systems analyses, the DAKOTA toolkit provides a flexible and extensible problem-solving environment for design and performance analysis of computational models on high performance computers. This report serves as a user's manual for the DAKOTA software and provides capability overviews and procedures for software execution, as well as a variety of example studies.

  6. User's Manual for the Langley Aerothermodynamic Upwind Relaxation Algorithm (LAURA)

    Science.gov (United States)

    Gnoffo, Peter A.; Cheatwood, F. McNeil

    1996-01-01

    This user's manual provides detailed instructions for the installation and the application of version 4.1 of the Langley Aerothermodynamic Upwind Relaxation Algorithm (LAURA). Also provides simulation of flow field in thermochemical nonequilibrium around vehicles traveling at hypersonic velocities through the atmosphere. Earlier versions of LAURA were predominantly research codes, and they had minimal (or no) documentation. This manual describes UNIX-based utilities for customizing the code for special applications that also minimize system resource requirements. The algorithm is reviewed, and the various program options are related to specific equations and variables in the theoretical development.

  7. ERIC User Services Manual. Revised Edition.

    Science.gov (United States)

    Wagner, Judith O., Comp.

    This manual explains how the user services functions, usually performed by a User Services Coordinator, can be conducted in the 16 ERIC (Educational Resources Information Center) Clearinghouses and the various adjunct ERIC Clearinghouses. It provides guidelines, suggestions, and examples of how ERIC components currently perform the user services…

  8. T-3 cask users' manual. Revision 1

    International Nuclear Information System (INIS)

    1986-06-01

    This user's manual for the T-C spent fuel cask provides information on: operating procedures; inspection and maintenance procedures; criticality evaluation; shielding evaluation; thermal evaluation; structural evaluation; and limitations

  9. User's Manual for CoEAT Tool

    Science.gov (United States)

    The Co-EAT users manual is designed to help the anaerobic digestion system operators evaluate the costs and benefits of accepting and processing wasted food, fats, oils and greases (FOG) or other organic materials.

  10. Los Alamos waste drum shufflers users manual

    International Nuclear Information System (INIS)

    Rinard, P.M.; Adams, E.L.; Painter, J.

    1993-01-01

    This user manual describes the Los Alamos waste drum shufflers. The primary purpose of the instruments is to assay the mass of 235 U (or other fissile materials) in drums of assorted waste. It can perform passive assays for isotopes that spontaneously emit neutrons or active assays using the shuffler technique as described on this manual

  11. GWSCREEN: A Semi-analytical Model for Assessment of the Groundwater Pathway from Surface or Buried Contamination, Theory and User's Manual, Version 2.5

    Energy Technology Data Exchange (ETDEWEB)

    Rood, Arthur South

    1998-08-01

    GWSCREEN was developed for assessment of the groundwater pathway from leaching of radioactive and non-radioactive substances from surface or buried sources. The code was designed for implementation in the Track I and Track II assessment of Comprehensive Environmental Response, Compensation, and Liability Act sites identified as low probability hazard at the Idaho National Engineering Laboratory. The code calculates 1) the limiting soil concentration such that, after leaching and transport to the aquifer regulatory contaminant levels in groundwater are not exceeded, 2) peak aquifer concentration and associated human health impacts, and 3) aquifer concentrations and associated human health impacts as a function of time and space. The code uses a mass conservation approach to model three processes: contaminant release from a source volume, vertical contaminant transport in the unsaturated zone, and 2D or 3D contaminant transport in the saturated zone. The source model considers the sorptive properties and solubility of the contaminant. In Version 2.5, transport in the unsaturated zone is described by a plug flow or dispersive solution model. Transport in the saturated zone is calculated with a semi-analytical solution to the advection dispersion equation in groundwater. Three source models are included; leaching from a surface or buried source, infiltration pond, or user-defined arbitrary release. Dispersion in the aquifer may be described by fixed dispersivity values or three, spatial-variable dispersivity functions. Version 2.5 also includes a Monte Carlo sampling routine for uncertainty/sensitivity analysis and a preprocessor to allow multiple input files and multiple contaminants to be run in a single simulation. GWSCREEN has been validated against other codes using similar algorithms and techniques. The code was originally designed for assessment and screening of the groundwater pathway when field data are limited. It was intended to simulate relatively simple

  12. PAN AIR: A computer program for predicting subsonic or supersonic linear potential flows about arbitrary configurations using a higher order panel method. Volume 2: User's manual (version 3.0)

    Science.gov (United States)

    Sidwell, Kenneth W.; Baruah, Pranab K.; Bussoletti, John E.; Medan, Richard T.; Conner, R. S.; Purdon, David J.

    1990-01-01

    A comprehensive description of user problem definition for the PAN AIR (Panel Aerodynamics) system is given. PAN AIR solves the 3-D linear integral equations of subsonic and supersonic flow. Influence coefficient methods are used which employ source and doublet panels as boundary surfaces. Both analysis and design boundary conditions can be used. This User's Manual describes the information needed to use the PAN AIR system. The structure and organization of PAN AIR are described, including the job control and module execution control languages for execution of the program system. The engineering input data are described, including the mathematical and physical modeling requirements. Version 3.0 strictly applies only to PAN AIR version 3.0. The major revisions include: (1) inputs and guidelines for the new FDP module (which calculates streamlines and offbody points); (2) nine new class 1 and class 2 boundary conditions to cover commonly used modeling practices, in particular the vorticity matching Kutta condition; (3) use of the CRAY solid state Storage Device (SSD); and (4) incorporation of errata and typo's together with additional explanation and guidelines.

  13. CREST Cost of Renewable Energy Spreadsheet Tool: A Model for Developing Cost-Based Incentives in the United States; User Manual Version 4, August 2009 - March 2011 (Updated July 2013)

    Energy Technology Data Exchange (ETDEWEB)

    Gifford, J. S.; Grace, R. C.

    2013-07-01

    The objective of this document is to help model users understand how to use the CREST model to support renewable energy incentives, FITs, and other renewable energy rate-setting processes. This user manual will walk the reader through the spreadsheet tool, including its layout and conventions, offering context on how and why it was created. This user manual will also provide instructions on how to populate the model with inputs that are appropriate for a specific jurisdiction's policymaking objectives and context. Finally, the user manual will describe the results and outline how these results may inform decisions about long-term renewable energy support programs.

  14. The ISIS Open GENIE user manual

    International Nuclear Information System (INIS)

    Akeroyd, F.A.; Ashworth, R.L.; Campbell, S.I.; Johnston, S.D.; Martin, J.M.; Moreton-Smith, C.M.; Sivia, D.S.

    2000-01-01

    This manual should enable you to become familiar with Open GENIE quickly and easily. It therefore complements the Open GENIE Reference Manual which should be used to understand the full meaning of Open GENIE commands. The reference manual is accessible on the ISIS web server at: http://www.isis.rl.ac.uk/GENIEReferenceManual/ and the user manual is planned to be accessible by January '98 at http://www.isis.rl.ac.ukIGENIEUserManual/. The Open GENIE User Manual is separated into two parts: Part A. The User Manual. An introduction to the use of Open GENIE. Part B. The Installation Guide. General information on how to install and run Open GENIE. Assuming that you are new to Open GENIE and have just downloaded a copy you will need to consult the Installation Guide to get Open GENIE installed on your machine. After this we recommend you experiment with some of the example files to get an idea of the capabilities of Open GENIE. For further information, comments, additions of routines that you feel should be included, please contact us at genie at isise.rl.ac.uk

  15. Canopy Version 7.0: Canopy manual

    International Nuclear Information System (INIS)

    Fischler, M.; Uchima, M.; Hockney, G.; Mackenzie, P.

    1993-12-01

    Canopy provides a machine-independent environment for attacking grid-oriented problems. This document describes the concepts and routines common to all Canopy implementations, independent of the system and implementation. Information specific to the massively parallel ACPMAPS/indexACPMAPS system at FermiLab is contained in two other documents: The CANOPY ACPMAPS USER's GUIDE provides user-oriented instructions on compiling, running, file system usage, and production job control. The CANOPY ACPMAPS SYSTEM MANUAL describes system tools and installation and system management techniques. System-specific User's Guides may be created for implementations on other systems. The goal of Canopy is to allow scientists to use massively parallel systems for a broad class of applications without having to become expert in any particular system or in parallel programming techniques. The Canopy approach identifies grid-oriented concepts and implements them as routines in a library. Applications written in terms of these concepts will run on any system which supports the Canopy software. A side benefit in dealing with familiar concepts is that programs can more easily be understood by other researchers

  16. SES2D user's manual

    International Nuclear Information System (INIS)

    Johnson, J.D.; Lyon, S.P.

    1982-04-01

    SES2D is an interactive graphics code designed to generate plots of equation of state data from the Los Alamos National Laboratory Group T-4 computer libraries. This manual discusses the capabilities of the code. It describes the prompts and commands and illustrates their use with a sample run

  17. Smart roadside initiative : user manual.

    Science.gov (United States)

    2015-09-01

    This document provides the user instructions for the Smart Roadside Initiative (SRI) applications including mobile and web-based SRI applications. These applications include smartphone-enabled information exchange and notification, and software compo...

  18. [New portfolio, a users' manual].

    Science.gov (United States)

    Cougnoux, Nadège; Deken, Éric; Juif, Isabelle; Papas, Anne

    2015-10-01

    The portfolio, a tool for monitoring nursing students throughout their internship period, has now been modified. The new 2015 version can be used to monitor and trace the student's career as well as progress made. One of the major new points is the integration of an intermediate internship assessment. Copyright © 2015 Elsevier Masson SAS. All rights reserved.

  19. ROMUSE 2.0 User Manual

    Energy Technology Data Exchange (ETDEWEB)

    Khuwaileh, Bassam [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Turinsky, Paul [North Carolina State Univ., Raleigh, NC (United States); Williams, Brian J. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2016-10-04

    ROMUSE (Reduced Order Modeling Based Uncertainty/Sensitivity Estimator) is an effort within the Consortium for Advanced Simulation of Light water reactors (CASL) to provide an analysis tool to be used in conjunction with reactor core simulators, especially the Virtual Environment for Reactor Applications (VERA). ROMUSE is written in C++ and is currently capable of performing various types of parameters perturbations, uncertainty quantification, surrogate models construction and subspace analysis. Version 2.0 has the capability to interface with DAKOTA which gives ROMUSE access to the various algorithms implemented within DAKOTA. ROMUSE is mainly designed to interface with VERA and the Comprehensive Modeling and Simulation Suite for Nuclear Safety Analysis and Design (SCALE) [1,2,3], however, ROMUSE can interface with any general model (e.g. python and matlab) with Input/Output (I/O) format that follows the Hierarchical Data Format 5 (HDF5). In this brief user manual, the use of ROMUSE will be overviewed and example problems will be presented and briefly discussed. The algorithms provided here range from algorithms inspired by those discussed in Ref.[4] to nuclear-specific algorithms discussed in Ref. [3].

  20. TMAP4 User`s Manual

    Energy Technology Data Exchange (ETDEWEB)

    Longhurst, G.R.; Holland, D.F.; Jones, J.L.; Merrill, B.J.

    1992-06-12

    The Tritium Migration Analysis Program, Version 4 (TMAP4) has been developed by the Fusion Safety Program at the Idaho National Engineering Laboratory (INEL) as a safety analysis code, mainly to analyze tritium retention and loss in fusion reactor structures and systems during normal operation and accident conditions. TMAP4 incorporates one-dimensional thermal- and mass-diffusive transport and trapping calculations through structures and zero dimensional fluid transport between enclosures and across the interface between enclosures and structures. A key feature is the ability to input problem definition parameters as constants, interpolation tables, or FORTRAN equations. The code is specifically intended for use under a DOS operating system on PC-type mini-computers, but it has also been run successfully on workstations and mainframe computer systems. Use of the equation-input feature requires access to a FORTRAN-77 compiler and a linker program.

  1. User's manual of Tokamak Simulation Code

    International Nuclear Information System (INIS)

    Nakamura, Yukiharu; Nishino, Tooru; Tsunematsu, Toshihide; Sugihara, Masayoshi.

    1992-12-01

    User's manual for use of Tokamak Simulation Code (TSC), which simulates the time-evolutional process of deformable motion of axisymmetric toroidal plasma, is summarized. For the use at JAERI computer system, the TSC is linked with the data management system GAEA. This manual is forcused on the procedure for the input and output by using the GAEA system. Model equations to give axisymmetric motion, outline of code system, optimal method to get the well converged solution are also described. (author)

  2. How 2 HAWC2, the user's manual

    Energy Technology Data Exchange (ETDEWEB)

    Juul Larsen, T.; Melchior Hansen, A.

    2007-12-15

    The report contains the user's manual for the aeroelastic code HAWC2. The code is intended for calculating wind turbine response in time domain and has a structural formulation based on multi-body dynamics. The aerodynamic part of the code is based on the blade element momentum theory, but extended from the classic approach to handle dynamic inflow, dynamic stall, skew inflow, shear effects on the induction and effects from large deflections. It has been developed within the years 2003-2006 at the aeroelastic design research programme at Risoe National Laboratory, Denmark. This manual is updated for HAWC2 version 6.4. (au)

  3. PRETART/TARTV user's manual

    International Nuclear Information System (INIS)

    Dubois, P.F.

    1977-01-01

    PRETART and TARTV are preprocessors for input decks for TARTNP, a coupled neutron--photon Monte Carlo transport code. They accept the normal TARTNP input decks. The purpose of these routines is to aid users in checking their geometry before making a TARTNP run. PRETART finds the volume of each zone, or of any selected subset of zones. When the volumes of all zones are found, the user may select a percentage of random checking for gaps or overlaps between the zones. If gaps or overlaps are found, a diagnostic routine describes the difficulty as best it can. TARTV allows the user to see a picture on TMDS (with a fiche copy) of a plane slice, parallel to the x-y plane or parallel to the x-z plane, through space, with an arbitrary picture window. A complete description of how to use these routines follows. It needs to be emphasized that PRETART cannot be used naively. It requires an active user who understands what it is trying to do, and its limitations

  4. ADFStealthViewer User Manual

    Science.gov (United States)

    2013-05-01

    environmental objects are used to immerse the user in a 3D visualisation of the simulated war game. ADFStealthViewer has several ADF produced 3D models...OpenGL, audio , and networking devices. Some advanced functionality of the engine relies on modern graphics pixel and vertex shaders. These advanced

  5. FDTD-ANT User Manual

    Science.gov (United States)

    Zimmerman, Martin L.

    1995-01-01

    This manual explains the theory and operation of the finite-difference time domain code FDTD-ANT developed by Analex Corporation at the NASA Lewis Research Center in Cleveland, Ohio. This code can be used for solving electromagnetic problems that are electrically small or medium (on the order of 1 to 50 cubic wavelengths). Calculated parameters include transmission line impedance, relative effective permittivity, antenna input impedance, and far-field patterns in both the time and frequency domains. The maximum problem size may be adjusted according to the computer used. This code has been run on the DEC VAX and 486 PC's and on workstations such as the Sun Sparc and the IBM RS/6000.

  6. High School and Beyond: Twins and Siblings' File Users' Manual, User's Manual for Teacher Comment File, Friends File Users' Manual.

    Science.gov (United States)

    National Center for Education Statistics (ED), Washington, DC.

    These three users' manuals are for specific files of the High School and Beyond Study, a national longitudinal study of high school sophomores and seniors in 1980. The three files are computerized databases that are available on magnetic tape. As one component of base year data collection, information identifying twins, triplets, and some non-twin…

  7. Hanford inventory program user's manual

    International Nuclear Information System (INIS)

    Hinkelman, K.C.

    1994-01-01

    Provides users with instructions and information about accessing and operating the Hanford Inventory Program (HIP) system. The Hanford Inventory Program is an integrated control system that provides a single source for the management and control of equipment, parts, and material warehoused by Westinghouse Hanford Company in various site-wide locations. The inventory is comprised of spare parts and equipment, shop stock, special tools, essential materials, and convenience storage items. The HIP replaced the following systems; ACA, ASP, PICS, FSP, WSR, STP, and RBO. In addition, HIP manages the catalog maintenance function for the General Supplies inventory stocked in the 1164 building and managed by WIMS

  8. 46 CFR 160.176-21 - User manuals.

    Science.gov (United States)

    2010-10-01

    ... 46 Shipping 6 2010-10-01 2010-10-01 false User manuals. 160.176-21 Section 160.176-21 Shipping...: SPECIFICATIONS AND APPROVAL LIFESAVING EQUIPMENT Inflatable Lifejackets § 160.176-21 User manuals. (a) The manufacturer must develop a user's manual for each model of inflatable lifejacket. The content of the manual...

  9. DAKOTA : a multilevel parallel object-oriented framework for design optimization, parameter estimation, uncertainty quantification, and sensitivity analysis. Version 5.0, user's reference manual.

    Energy Technology Data Exchange (ETDEWEB)

    Eldred, Michael Scott; Dalbey, Keith R.; Bohnhoff, William J.; Adams, Brian M.; Swiler, Laura Painton; Hough, Patricia Diane (Sandia National Laboratories, Livermore, CA); Gay, David M.; Eddy, John P.; Haskell, Karen H.

    2010-05-01

    The DAKOTA (Design Analysis Kit for Optimization and Terascale Applications) toolkit provides a flexible and extensible interface between simulation codes and iterative analysis methods. DAKOTA contains algorithms for optimization with gradient and nongradient-based methods; uncertainty quantification with sampling, reliability, and stochastic finite element methods; parameter estimation with nonlinear least squares methods; and sensitivity/variance analysis with design of experiments and parameter study methods. These capabilities may be used on their own or as components within advanced strategies such as surrogate-based optimization, mixed integer nonlinear programming, or optimization under uncertainty. By employing object-oriented design to implement abstractions of the key components required for iterative systems analyses, the DAKOTA toolkit provides a flexible and extensible problem-solving environment for design and performance analysis of computational models on high performance computers. This report serves as a reference manual for the commands specification for the DAKOTA software, providing input overviews, option descriptions, and example specifications.

  10. ARES: automated response function code. Users manual

    International Nuclear Information System (INIS)

    Maung, T.; Reynolds, G.M.

    1981-06-01

    This ARES user's manual provides detailed instructions for a general understanding of the Automated Response Function Code and gives step by step instructions for using the complete code package on a HP-1000 system. This code is designed to calculate response functions of NaI gamma-ray detectors, with cylindrical or rectangular geometries

  11. C-TIC Console Operator's User Manual

    Science.gov (United States)

    1996-07-01

    The C-TIC Console Operator's User Manual is designed to assist the operator at : the Corridor Transportation Information Center with the navigation and use of : the application programs in the C-TIC. This document will concentrate solely on : the ext...

  12. National Radiobiology Archives Distributed Access user's manual

    International Nuclear Information System (INIS)

    Watson, C.; Smith, S.; Prather, J.

    1991-11-01

    This User's Manual describes installation and use of the National Radiobiology Archives (NRA) Distributed Access package. The package consists of a distributed subset of information representative of the NRA databases and database access software which provide an introduction to the scope and style of the NRA Information Systems

  13. NJOY nuclear data processing system: user's manual

    International Nuclear Information System (INIS)

    MacFarlane, R.E.; Barrett, R.J.; Muir, D.W.; Boicourt, R.M.

    1978-12-01

    The NJOY nuclear data processing system is a comprehensive computer code package for producing cross sections for neutron and photon transport calculations from ENDF/B-IV and -V evaluated nuclear data. This user's manual provides a concise description of the code, input instructions, sample problems, and installation instructions. 1 figure, 3 tables

  14. User's manual about visualizing debugger, vdebug

    International Nuclear Information System (INIS)

    Matsuda, Katsuyuki; Takemiya, Hiroshi; Kawasaki, Takuji

    1998-12-01

    We developed a visualizing debugger, vdebug, which works in cooperation with the visualization system AVS and source level debuggers (gdb, dbx, and ladebug), whereby we can visualize any array data without recompiling, and find errors in programs efficiently. This report is user's manual about a visualizing debugger, vdebug, and describes its usage and examples. (author)

  15. Interlibrary Loan Communications Subsystem: Users Manual.

    Science.gov (United States)

    OCLC Online Computer Library Center, Inc., Dublin, OH.

    The OCLC Interlibrary Loan (ILL) Communications Subsystem provides participating libraries with on-line control of ILL transactions. This user manual includes a glossary of terms related to the procedures in using the system. Sections describe computer entry, searching, loan request form, loan response form, ILL procedures, the special message…

  16. User manual Dieka PreProcessor

    NARCIS (Netherlands)

    Valkering, Kasper

    2000-01-01

    This is the user manual belonging to the Dieka-PreProcessor. This application was written by Wenhua Cao and revised and expanded by Kasper Valkering. The aim of this preproccesor is to be able to draw and mesh extrusion dies in ProEngineer, and do the FE-calculation in Dieka. The preprocessor makes

  17. BLOCKAGE 2.5 user's manual

    International Nuclear Information System (INIS)

    Rao, D.V.; Brideau, J.; Shaffer, C.; Souto, F.; Bernahl, W.

    1996-12-01

    The BLOCKAGE 2.5 code described in this User's Manual was developed by the US Nuclear Regulatory Commission (NRC) as a tool to evaluate licensee compliance with NRC Bulletin 96-03, ''Potential Plugging of Emergency Core Cooling Suction Strainers by Debris in Boiling Water Reactors.'' As such, BLOCKAGE 2.5 provides a generalized framework into which a user can input plant-specific and insulation-specific data for performing analyses in accordance with Regulatory Guide 1.82, Rev. 2. This user's manual describes the capabilities of BLOCKAGE 2.5 along with a description of the graphics user's interface provided for data entry. Each input/output dialog is described in detail along with special considerations related to developing and executing BLOCKAGE. Also, several sample problems are provided such that user can easily modify them to suit a particular plant of interest. The models used in BLOCKAGE 2.5 and their validation are presented in the accompanying NUREG/CR-6371. The BLOCKAGE models were designed to be parametric in nature, allowing the user flexibility to examine the impact of several modeling assumptions and to conduct sensitivity analyses. As a result, BLOCKAGE 2.5 results are known to be very sensitive to the user provided input. It is therefore strongly recommended that users become thoroughly familiar with BLOCKAGE models and their limitations as described in NUREG/CR-6224

  18. HANSF 1.3 user's manual

    International Nuclear Information System (INIS)

    PLYS, M.G.

    1999-01-01

    The HANSF analysis tool is an integrated model considering phenomena inside a multi-canister overpack (MCO) spent nuclear fuel container such as fuel oxidation, convective and radiative heat transfer, and the potential for fission product release. It may be used for all phases of spent fuel disposition including cold vacuum drying, transportation, and storage. This manual reflects HANSF version 1.3, a revised version of version 1.2a. HANSF 1.3 was written to add new models for axial nodalization, add new features for ease of usage, and correct errors. HANSF 1.3 is intended for use on personal computers such as IBM-compatible machines with Intel processors running under a DOS-type operating system. HANSF 1.3 is known to compile under Lahey TI and Digital Visual FORTRAN, Version 6.0, but this does not preclude operation in other environments

  19. HANSF 1.3 user's manual; TOPICAL

    International Nuclear Information System (INIS)

    PLYS, M.G.

    1999-01-01

    The HANSF analysis tool is an integrated model considering phenomena inside a multi-canister overpack (MCO) spent nuclear fuel container such as fuel oxidation, convective and radiative heat transfer, and the potential for fission product release. It may be used for all phases of spent fuel disposition including cold vacuum drying, transportation, and storage. This manual reflects HANSF version 1.3, a revised version of version 1.2a. HANSF 1.3 was written to add new models for axial nodalization, add new features for ease of usage, and correct errors. HANSF 1.3 is intended for use on personal computers such as IBM-compatible machines with Intel processors running under a DOS-type operating system. HANSF 1.3 is known to compile under Lahey TI and Digital Visual FORTRAN, Version 6.0, but this does not preclude operation in other environments

  20. SPORTS (version 1) user's guide

    International Nuclear Information System (INIS)

    Chatoorgoon, V.; Thibeault, P.R.

    1985-06-01

    SPORTS is a transient one-dimensional thermalhydraulic code formulated from the non-linear time dependent conservation equations and designed to investigate two-phase flow stability. The SPORTS Users' Guide contains some features of the code, a brief description of the program environment and access, and a description of the input data complete with a sample problem

  1. Hanford Environmental Information System (HEIS) user's manual

    International Nuclear Information System (INIS)

    1991-10-01

    The Hanford Environmental Information System (HEIS) is a consolidated set of automated resources that effectively manage the data gathered during environmental monitoring and restoration of the Hanford Site. The HEIS includes an integrated database that provides consistent and current data to all users and promotes sharing of data by the entire user community. Data stored in the HEIS are collected under several regulatory programs. Currently these include the Comprehensive Environmental Response, Compensation and Liability Act of 1980 (CERCLA); the Resource Conservation and Recovery Act of 1976 (RCRA); and the Ground-Water Environmental Surveillance Project, managed by the Pacific Northwest Laboratory. The HEIS is an information system with an inclusive database. The manual, the HEIS User's Manual, describes the facilities available to the scientist, engineer, or manager who uses the system for environmental monitoring, assessment, and restoration planning; and to the regulator who is responsible for reviewing Hanford Site operations against regulatory requirements and guidelines

  2. GWSCREEN: A semi-analytical model for assessment of the groundwater pathway from surface or buried contamination: Version 2.0 theory and user's manual

    International Nuclear Information System (INIS)

    Rood, A.S.

    1993-06-01

    GWSCREEN was developed for assessment of the groundwater pathway from leaching of radioactive and non radioactive substances from surface or buried sources. The code was designed for implementation in the Track I and Track II assessment of CERCLA (Comprehensive Environmental Response, Compensation and Liability Act) sites identified as low probability hazard at the Idaho National Engineering Laboratory (DOE, 1992). The code calculates the limiting soil concentration such that, after leaching and transport to the aquifer, regulatory contaminant levels in groundwater are not exceeded. The code uses a mass conservation approach to model three processes: contaminant release from a source volume, contaminant transport in the unsaturated zone, and contaminant transport in the saturated zone. The source model considers the sorptive properties and solubility of the contaminant. Transport in the unsaturated zone is described by a plug flow model. Transport in the saturated zone is calculated with a semi-analytical solution to the advection dispersion equation in groundwater. In Version 2.0, GWSCREEN has incorporated an additional source model to calculate the impacts to groundwater resulting from the release to percolation ponds. In addition, transport of radioactive progeny has also been incorporated. GWSCREEN has shown comparable results when compared against other codes using similar algorithms and techniques. This code was designed for assessment and screening of the groundwater pathway when field data is limited. It was not intended to be a predictive tool

  3. How 2 HAWC2, the user's manual

    DEFF Research Database (Denmark)

    Larsen, Torben J.; Hansen, Anders Melchior

    The report contains the user's manual for the aeroleastic code HAWC2. The code is intended for calculating wind turbine response in time domain and has a structural formulation based on multi-body dynamics. The aerodynamic part of the code is based on the blade element momentum theory, but extended...... from the classic approach to handle dynamic inflow, dynamic stall, skew inflow, shear effects on the induction and effects from large deflections. It has been developed within the years 2003-2006 at the aeroelastic design research programme at Risoe, National laboratory Denmark. This manual is updated...

  4. EQ3NR, a computer program for geochemical aqueous speciation-solubility calculations: Theoretical manual, user's guide, and related documentation (Version 7.0)

    International Nuclear Information System (INIS)

    Wolery, T.J.

    1992-01-01

    EQ3NR is an aqueous solution speciation-solubility modeling code. It is part of the EQ3/6 software package for geochemical modeling. It computes the thermodynamic state of an aqueous solution by determining the distribution of chemical species, including simple ions, ion pairs, and complexes, using standard state thermodynamic data and various equations which describe the thermodynamic activity coefficients of these species. The input to the code describes the aqueous solution in terms of analytical data, including total (analytical) concentrations of dissolved components and such other parameters as the pH, pHCl, Eh, pe, and oxygen fugacity. The input may also include a desired electrical balancing adjustment and various constraints which impose equilibrium with special pure minerals, solid solution end-member components (of specified mole fractions), and gases (of specified fugacities). The code evaluates the degree of disequilibrium in terms of the saturation index (SI = 1og Q/K) and the thermodynamic affinity (A = -2.303 RT log Q/K) for various reactions, such as mineral dissolution or oxidation-reduction in the aqueous solution itself. Individual values of Eh, pe, oxygen fugacity, and Ah (redox affinity) are computed for aqueous redox couples. Equilibrium fugacities are computed for gas species. The code is highly flexible in dealing with various parameters as either model inputs or outputs. The user can specify modification or substitution of equilibrium constants at run time by using options on the input file

  5. EQ6, a computer program for reaction path modeling of aqueous geochemical systems: Theoretical manual, user's guide, and related documentation (Version 7.0)

    International Nuclear Information System (INIS)

    Wolery, T.J.; Daveler, S.A.

    1992-01-01

    EQ6 is a FORTRAN computer program in the EQ3/6 software package (Wolery, 1979). It calculates reaction paths (chemical evolution) in reacting water-rock and water-rock-waste systems. Speciation in aqueous solution is an integral part of these calculations. EQ6 computes models of titration processes (including fluid mixing), irreversible reaction in closed systems, irreversible reaction in some simple kinds of open systems, and heating or cooling processes, as well as solve ''single-point'' thermodynamic equilibrium problems. A reaction path calculation normally involves a sequence of thermodynamic equilibrium calculations. Chemical evolution is driven by a set of irreversible reactions (i.e., reactions out of equilibrium) and/or changes in temperature and/or pressure. These irreversible reactions usually represent the dissolution or precipitation of minerals or other solids. The code computes the appearance and disappearance of phases in solubility equilibrium with the water. It finds the identities of these phases automatically. The user may specify which potential phases are allowed to form and which are not. There is an option to fix the fugacities of specified gas species, simulating contact with a large external reservoir. Rate laws for irreversible reactions may be either relative rates or actual rates. If any actual rates are used, the calculation has a time frame. Several forms for actual rate laws are programmed into the code. EQ6 is presently able to model both mineral dissolution and growth kinetics

  6. HANSF 1.3.2 User's Manual

    International Nuclear Information System (INIS)

    DUNCAN, D.R.

    1999-01-01

    The HANSF analysis tool is an integrated model considering phenomena inside a multi-canister overpack (MCO) spent nuclear fuel container such as fuel oxidation, convective and radiative heat transfer, and the potential for fission product release. This manual reflects the HANSF version 1.3.2, a revised version of 1.3.1. HANSF 1.3.2 was written to correct minor errors and to allow modeling of condensate flow on the MCO inner surface. HANSF 1.3.2 is intended for use on personal computers such as IBM-compatible machines with Intel processors running under Lahey TI or digital Visual FORTRAN, Version 6.0, but this does not preclude operation in other environments

  7. User's manual for THYDE-P1

    International Nuclear Information System (INIS)

    Asahi, Yoshiro

    1982-04-01

    THYDE-P1 is a computer code applicable to LWR (light water reactor) plant dynamics in response to various disturbances. This work is the user's mannual of THYDE-P1 (version SV02L03). The input requirements, steady state adjustment, execution of runs and output specifications are described. (author)

  8. SIMone user's manual. V. 2.1

    International Nuclear Information System (INIS)

    Silk, M.

    1990-03-01

    Simone is a computer application program which provides an environment in which to run the nuclear reactor thermal hydraulic simulation code RELAP5. It enables users to run a RELAP5 calculation on-line on a SUN4 workstation, and provides an interactive means of executing operator-like actions. In addition, a version of the graphical post-processing tool ISOVU is incorporated, allowing a real-time display of the RELAP5 calculation to be presented in the form of a system mimic diagram. This report comprises a description of the facilities available within the Simone application, and a user guide describing the user interface. (author)

  9. Manual for soil physical measurements; Version 3

    NARCIS (Netherlands)

    Stolte, J.

    1997-01-01

    Manuals are given for several laboratory methods for determining hydraulic conductivity, water retention and shrinkage characteristics of soil. Measurement techniques described are: the constant-head and falling-head methods for saturated conductivitythe drip infiltrometer for unsaturated

  10. Rooftop Unit Comparison Calculator User Manual

    Energy Technology Data Exchange (ETDEWEB)

    Miller, James D. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

    2015-04-30

    This document serves as a user manual for the Packaged rooftop air conditioners and heat pump units comparison calculator (RTUCC) and is an aggregation of the calculator’s website documentation. Content ranges from new-user guide material like the “Quick Start” to the more technical/algorithmic descriptions of the “Methods Pages.” There is also a section listing all the context-help topics that support the features on the “Controls” page. The appendix has a discussion of the EnergyPlus runs that supported the development of the building-response models.

  11. GWSCREEN: A semi-analytical model for assessment of the groundwater pathway from surface or buried contamination. Theory and user`s manual, Version 2.0: Revision 2

    Energy Technology Data Exchange (ETDEWEB)

    Rood, A.S.

    1994-06-01

    Multimedia exposure assessment of hazardous chemicals and radionuclides requires that all pathways of exposure be investigated. The GWSCREEN model was designed to perform initial screening calculations for groundwater pathway impacts resulting from the leaching of surficial and buried contamination at CERCLA sites identified as low probability hazard at the INEL. In Version 2.0, an additional model was added to calculate impacts to groundwater from the operation of a percolation pond. The model was designed to make best use of the data that would potentially be available. These data include the area and depth of contamination, sorptive properties and solubility limit of the contaminant, depth to aquifer, and the physical properties of the aquifer (porosity, velocity, and dispersivity). For the pond model, data on effluent flow rates and operation time are required. Model output includes the limiting soil concentration such that, after leaching and transport to the aquifer, regulatory contaminant levels in groundwater are not exceeded. Also, groundwater concentration as a function of time may be calculated. The model considers only drinking water consumption and does not include the transfer of contamination to food products due to irrigation with contaminated water. Radiological dose, carcinogenic risk, and the hazard quotient are calculated for the peak time using the user-defined input mass (or activity). Appendices contain sample problems and the source code listing.

  12. Model for Analysis of Energy Demand (MAED-2). User's manual

    International Nuclear Information System (INIS)

    2007-01-01

    The IAEA has been supporting its Member States in the area of energy planning for sustainable development. Development and dissemination of appropriate methodologies and their computer codes are important parts of this support. This manual has been produced to facilitate the use of the MAED model: Model for Analysis of Energy Demand. The methodology of the MAED model was originally developed by. B. Chateau and B. Lapillonne of the Institute Economique et Juridique de l'Energie (IEJE) of the University of Grenoble, France, and was presented as the MEDEE model. Since then the MEDEE model has been developed and adopted to be appropriate for modelling of various energy demand system. The IAEA adopted MEDEE-2 model and incorporated important modifications to make it more suitable for application in the developing countries, and it was named as the MAED model. The first version of the MAED model was designed for the DOS based system, which was later on converted for the Windows system. This manual presents the latest version of the MAED model. The most prominent feature of this version is its flexibility for representing structure of energy consumption. The model now allows country-specific representations of energy consumption patterns using the MAED methodology. The user can now disaggregate energy consumption according to the needs and/or data availability in her/his country. As such, MAED has now become a powerful tool for modelling widely diverse energy consumption patterns. This manual presents the model in details and provides guidelines for its application

  13. Model for Analysis of Energy Demand (MAED-2). User's manual

    International Nuclear Information System (INIS)

    2006-01-01

    The IAEA has been supporting its Member States in the area of energy planning for sustainable development. Development and dissemination of appropriate methodologies and their computer codes are important parts of this support. This manual has been produced to facilitate the use of the MAED model: Model for Analysis of Energy Demand. The methodology of the MAED model was originally developed by. B. Chateau and B. Lapillonne of the Institute Economique et Juridique de l'Energie (IEJE) of the University of Grenoble, France, and was presented as the MEDEE model. Since then the MEDEE model has been developed and adopted to be appropriate for modelling of various energy demand system. The IAEA adopted MEDEE-2 model and incorporated important modifications to make it more suitable for application in the developing countries, and it was named as the MAED model. The first version of the MAED model was designed for the DOS based system, which was later on converted for the Windows system. This manual presents the latest version of the MAED model. The most prominent feature of this version is its flexibility for representing structure of energy consumption. The model now allows country-specific representations of energy consumption patterns using the MAED methodology. The user can now disaggregate energy consumption according to the needs and/or data availability in her/his country. As such, MAED has now become a powerful tool for modelling widely diverse energy consumption patterns. This manual presents the model in details and provides guidelines for its application

  14. Minerva User Manual Version 1.0

    Energy Technology Data Exchange (ETDEWEB)

    J.J. Cogliati; M. L. Milvich; D. E. Wessol; C. A. Wemple

    2007-03-01

    MINERVA (Modality-Inclusive Environment for Radiotherapeutic Variable Analysis) is a Java-based patient-centric radiation treatment planning system (RTPS) for computational dosimetry and treatment planning in emerging areas of radiotherapy for cancer and other diseases. MINERVA was primarily developed at the Idaho National Laboratory (INL) and Montana State University (MSU). MINERVA allows the radiotherapist to make side-by-side comparison of plans for multiple treatment modalities with a common anatomical basis for the computational geometry, calculate doses for combinations of different radiotherapy modalities, and perform dose analysis and reporting functions. This provides the therapist with a consistent basis for selecting the modality or combination of modalities to use for treatment of the patient. MINERVA employs an integrated, lightweight plug-in architecture to accommodate multi-modal treatment planning using standard interface components. The MINERVA design facilitates integration of improved or emerging treatment planning technologies. MINERVA consists of the basic radiation treatment planning software modules managed by a consistent patient interface for developing multi-modal radiotherapy patient treatment plans. One of MINERVA's main functions is to provide a graphical environment for constructing and displaying uniform volume-element-based solid models derived from medical images. These solid models form the geometric basis of the target areas for the radiation transport model.

  15. CHEMCON User's Manual, Version 3.1

    International Nuclear Information System (INIS)

    Gaeta, M.J.; Merrill, B.J.

    1995-09-01

    CHEMCON is a computer program developed to analyze thermal transients of tokamak fusion reactors. It contains a one dimensional, cylindrical geometry, conduction model that allows a variety of heat transfer modes within nodes and at node boundaries. Solid regions can be grouped into segments that communicate at their boundaries through a radiation enclosure model. CHEMCON includes a single volume, pressurization/condensation model that is used to include the effects of an in-vessel LOCA and the resulting heat transfer between hot surfaces and cold surfaces in contact with this volume. The code includes properties for 11 solid materials and two gases. CHEMCON also contains specialized models for modeling chemical reactions of node boundaries with air and steam including the gases produced from these reactions. In addition, a model treating the collapse of radiation shields within a gap is also included. CHEMCON is used mainly to simulate the thermal transient for post-blowdown loss-of-coolant-accidents

  16. Users Manual AERCOARE Version 1.0

    Science.gov (United States)

    The work completed under this work assignment is a continuation of an evaluation report prepared by ENVIRON entitled “Evaluation of the COARE–AERMOD Alternative Modeling Approach for Simulation of Shell Exploratory Drilling Sources in the Beaufort and Chukchi Seas” dated Decembe...

  17. Early Childhood Longitudinal Study, Kindergarten Class of 2010-11 (ECLS-K:2011). User's Manual for the ECLS-K:2011 Kindergarten Data File and Electronic Codebook, Public Version. NCES 2015-074

    Science.gov (United States)

    Tourangeau, Karen; Nord, Christine; Lê, Thanh; Sorongon, Alberto G.; Hagedorn, Mary C.; Daly, Peggy; Najarian, Michelle

    2015-01-01

    This manual provides guidance and documentation for users of the kindergarten (or base year) data of the Early Childhood Longitudinal Study, Kindergarten Class of 2010-11 (ECLS-K:2011). It begins with an overview of the ECLS-K:2011. Subsequent chapters provide details on the study data collection instruments and methods; the direct and indirect…

  18. Early Childhood Longitudinal Study, Kindergarten Class of 2010-11 (ECLS-K:2011). User's Manual for the ECLS-K:2011 Kindergarten-First Grade Data File and Electronic Codebook, Public Version. NCES 2015-078

    Science.gov (United States)

    Tourangeau, Karen; Nord, Christine; Lê, Thanh; Wallner-Allen, Kathleen; Hagedorn, Mary C.; Leggitt, John; Najarian, Michelle

    2015-01-01

    This manual provides guidance and documentation for users of the longitudinal kindergarten-first grade (K-1) data file of the Early Childhood Longitudinal Study, Kindergarten Class of 2010-11 (ECLS-K:2011). It mainly provides information specific to the first-grade rounds of data collection. Data for the ECLS-K:2011 are released in both a…

  19. Bigfoot Field Manual, Version 2.1

    Energy Technology Data Exchange (ETDEWEB)

    Campbell, J.L.; Burrows, S.; Gower, S.T.; Cohen, W.B.

    1999-09-01

    The BigFoot Project is funded by the Earth Science Enterprise to collect and organize data to be used in the National Aeronautics and Space Administration's Earth Observing System (EOS) Validation Program. The data collected by the BigFoot Project are unique in being ground-based observations coincident with satellite overpasses. In addition to collecting data, the BigFoot project will develop and test new algorithms for scaling point measurements to the same spatial scales as the EOS satellite products. This BigFoot Field Manual will be used to achieve completeness and consistency of data collected at four initial BigFoot sites and at future sites that may collect similar validation data. Therefore, validation datasets submitted to the Oak Ridge National Laboratory Distributed Active Archive Center that have been compiled in a manner consistent with the field manual will be especially valuable in the validation program.

  20. Activity Management System user reference manual. Revision 1

    International Nuclear Information System (INIS)

    Gates, T.A.; Burdick, M.B.

    1994-01-01

    The Activity Management System (AMS) was developed in response to the need for a simple-to-use, low-cost, user interface system for collecting and logging Hanford Waste Vitrification Plant Project (HWVP) activities. This system needed to run on user workstations and provide common user access to a database stored on a local network file server. Most important, users wanted a system that provided a management tool that supported their individual process for completing activities. Existing system treated the performer as a tool of the system. All AMS data is maintained in encrypted format. Users can feel confident that any activities they have entered into the database are private and that, as the originator, they retain sole control over who can see them. Once entered into the AMS database, the activities cannot be accessed by anyone other than the originator, the designated agent, or by authorized viewers who have been explicitly granted the right to look at specific activities by the originator. This user guide is intended to assist new AMS users in learning how to use the application and, after the initial learning process, will serve as an ongoing reference for experienced users in performing infrequently used functions. Online help screens provide reference to some of the key information in this manual. Additional help screens, encompassing all the applicable material in this manual, will be incorporated into future AMS revisions. A third, and most important, source of help is the AMS administrator(s). This guide describes the initial production version of AMS, which has been designated Revision 1.0

  1. HTGR Application Economic Model Users' Manual

    International Nuclear Information System (INIS)

    Gandrik, A.M.

    2012-01-01

    The High Temperature Gas-Cooled Reactor (HTGR) Application Economic Model was developed at the Idaho National Laboratory for the Next Generation Nuclear Plant Project. The HTGR Application Economic Model calculates either the required selling price of power and/or heat for a given internal rate of return (IRR) or the IRR for power and/or heat being sold at the market price. The user can generate these economic results for a range of reactor outlet temperatures; with and without power cycles, including either a Brayton or Rankine cycle; for the demonstration plant, first of a kind, or nth of a kind project phases; for up to 16 reactor modules; and for module ratings of 200, 350, or 600 MWt. This users manual contains the mathematical models and operating instructions for the HTGR Application Economic Model. Instructions, screenshots, and examples are provided to guide the user through the HTGR Application Economic Model. This model was designed for users who are familiar with the HTGR design and Excel and engineering economics. Modification of the HTGR Application Economic Model should only be performed by users familiar with the HTGR and its applications, Excel, and Visual Basic.

  2. HOPSPACK 2.0 user manual.

    Energy Technology Data Exchange (ETDEWEB)

    Plantenga, Todd D.

    2009-09-01

    HOPSPACK (Hybrid Optimization Parallel Search PACKage) solves derivative-free optimization problems using an open source, C++ software framework. The framework enables parallel operation using MPI or multithreading, and allows multiple solvers to run simultaneously and interact to find solution points. HOPSPACK comes with an asynchronous pattern search solver that handles general optimization problems with linear and nonlinear constraints, and continuous and integer-valued variables. This user manual explains how to install and use HOPSPACK to solve problems, and how to create custom solvers within the framework.

  3. Explosives Classifications Tracking System User Manual

    Energy Technology Data Exchange (ETDEWEB)

    Genoni, R.P.

    1993-10-01

    The Explosives Classification Tracking System (ECTS) presents information and data for U.S. Department of Energy (DOE) explosives classifications of interest to EM-561, Transportation Management Division, other DOE facilities, and contractors. It is intended to be useful to the scientist, engineer, and transportation professional, who needs to classify or transport explosives. This release of the ECTS reflects upgrading of the software which provides the user with an environment that makes comprehensive retrieval of explosives related information quick and easy. Quarterly updates will be provided to the ECTS throughout its development in FY 1993 and thereafter. The ECTS is a stand alone, single user system that contains unclassified, publicly available information, and administrative information (contractor names, product descriptions, transmittal dates, EX-Numbers, etc.) information from many sources for non-decisional engineering and shipping activities. The data is the most up-to-date and accurate available to the knowledge of the system developer. The system is designed to permit easy revision and updating as new information and data become available. These, additions and corrections are welcomed by the developer. This user manual is intended to help the user install, understand, and operate the system so that the desired information may be readily obtained, reviewed, and reported.

  4. PANTHERMIX (PANTHER-THERMIX). User manual

    International Nuclear Information System (INIS)

    Oppe, J.; De Haas, J.B.M.; Kuijper, J.C.

    1998-06-01

    The PANTHER code calculates steady-state or time-dependent power distribution in a reactor with a given temperature distribution. The THERMIX-DIREKT code calculates temperature and coolant flow distributions, in steady-state or transient mode, in a system with a given power distribution. It is described how to use the combination of the general purpose modular reactor code PANTHER and the HTR thermal hydraulics code THERMIX-DIREKT. An earlier version of PANTHERMIX consisted of THERMIX-DIREKT plus 2 conversion programs. The jobs and scripts to be edited by the user were very complex in their interactions. Therefore this version of PANTHERMIX has been extended with macros that take care of all these interactions, so the interaction parts of the jobs become much less complex. 6 refs

  5. Desalination Economic Evaluation Program (DEEP). User's manual

    International Nuclear Information System (INIS)

    2000-01-01

    DEEP (formerly named ''Co-generation and Desalination Economic Evaluation'' Spreadsheet, CDEE) has been developed originally by General Atomics under contract, and has been used in the IAEA's feasibility studies. For further confidence in the software, it was validated in March 1998. After that, a user friendly version has been issued under the name of DEEP at the end of 1998. DEEP output includes the levelised cost of water and power, a breakdown of cost components, energy consumption and net saleable power for each selected option. Specific power plants can be modelled by adjustment of input data including design power, power cycle parameters and costs

  6. Computer System for Monitoring Environmental Campaigns. User's Guide. Version 1.0; Sistema Informatico para el Seguimiento de Campanas Ambientales. Manual de usuario. Version 1.0

    Energy Technology Data Exchange (ETDEWEB)

    Bailador, M. a.; Barcala, M.; Blanco, F.; Gonzalez, C.; Perez, J. M.; Sanchez, A.; Sanchez, E.; Willmot, C.

    2012-11-01

    CIEMAT has an environmental mobile unit to carry out the execution of environmental measures at diverse environments. During the last years, this unit has been involved in changes relative to its instrumentation, being necessary to developed an informatics system, SiSCA Informatics System for the monitoring of environmental campaigns, that is able to: Acquiring in a synchronized way the data from the environmental mobile unit instruments. Showing in a georrefential way these data by means of GIS technology. Transmitting in a secure way and in real time the data to a centralized data base repository This document is the user guide that picks up all the necessary information to use SiSCA when UMA environmental campaigns are carrying out. (Author)

  7. Orbitscreen reference manual, Version 1.3

    International Nuclear Information System (INIS)

    Evans, K. Jr.

    1995-08-01

    Orbitscreen is a Motif program to display arrays of process variables from the Advanced Photon Source control system. Although, in principal, any two arrays of process variables may be displayed, the most common use is to display the horizontal and vertical monitor readings. There are three display areas in the interface, one for each of the arrays and a zoom area. In the zoom area both arrays can be displayed at once along with symbols for the major elements of the lattice. There are a number of options to customize the way the values are displayed. It is also possible to: (1) store the current values internally; (2) store the values from a snapshot file internally; (3) display one of the stored sets of values along with the current values; (4) display the difference of the current values with one of the stored sets of values; and (5) write the current values to a snapshot file. The program continuously updates and displays the standard deviation, average, and maximum absolute values for each array and will show the envelope of recent values if desired. The values are sent to the program anytime they change outside of their dead band. If the dead band is chosen appropriately, this should result in less traffic over the control network than if all of the values were polled at fixed intervals. When the display updates, the current values that have been received are displayed. It is possible to manually update all the variables via the Options/EPICS/Rescan menu

  8. Maintenance Personnel Performance Simulation (MAPPS) model. Users' Manual

    International Nuclear Information System (INIS)

    Kopstein, F.F.; Wolf, J.J.

    1985-09-01

    This report (MAPPS User's Manual) is the last report to be published from this program and provides detailed guidelines for utilization of the MAPPS model. Although the model has been developed to be highly user-friendly and provides interactive means for controlling and running of the model, the user's manual is provided as a guide for the user in the event clarification or direction is required. The user will find that in general the model requires primarily user input that is self explanatory. Once initial familiarization with the model has been achieved by the user, the amount of interaction between the user's manual and the computer model will be minimal. It is suggested however that even the experienced user keep the user's manual handy for quick reference. 5 refs., 10 figs., 7 tabs

  9. Hydrogen Mixing Studies (HMS), user's manual

    International Nuclear Information System (INIS)

    Lam, K.L.; Wilson, T.L.; Travis, J.R.

    1994-12-01

    Hydrogen Mixing Studies (HMS) is a best-estimate analysis tool for predicting the transport, mixing, and combustion of hydrogen and other gases in nuclear reactor containments and other facilities. It can model geometrically complex facilities having multiple compartments and internal structures. The code can simulate the effects of steam condensation, heat transfer to walls and internal structures, chemical kinetics, and fluid turbulence. The gas mixture may consist of components included in a built-in library of 20 species. HMS is a finite-volume computer code that solves the time-dependent, three-dimensional (3D) compressible Navier Stokes equations. Both Cartesian and cylindrical coordinate systems are available. Transport equations for the fluid internal energy and for gas species densities are also solved. HMS was originally developed to run on Cray-type supercomputers with vector-processing units that greatly improve the computational speed, especially for large, complex problems. Recently the code has been converted to run on Sun workstations. Both the Cray and Sun versions have the same built-in graphics capabilities that allow 1D, 2D, 3D, and time-history plots of all solution variables. Other code features include a restart capability and flexible definitions of initial and time-dependent boundary conditions. This manual describes how to use the code. It explains how to set up the model geometry, define walls and obstacles, and specify gas species and material properties. Definitions of initial and boundary conditions are also described. The manual also describes various physical model and numerical procedure options, as well as how to turn them on. The reader also learns how to specify different outputs, especially graphical display of solution variables. Finally sample problems are included to illustrate some applications of the code. An input deck that illustrates the minimum required data to run HMS is given at the end of this manual

  10. User Manual for the PROTEUS Mesh Tools

    Energy Technology Data Exchange (ETDEWEB)

    Smith, Micheal A. [Argonne National Lab. (ANL), Argonne, IL (United States); Shemon, Emily R. [Argonne National Lab. (ANL), Argonne, IL (United States)

    2015-06-01

    This report describes the various mesh tools that are provided with the PROTEUS code giving both descriptions of the input and output. In many cases the examples are provided with a regression test of the mesh tools. The most important mesh tools for any user to consider using are the MT_MeshToMesh.x and the MT_RadialLattice.x codes. The former allows the conversion between most mesh types handled by PROTEUS while the second allows the merging of multiple (assembly) meshes into a radial structured grid. Note that the mesh generation process is recursive in nature and that each input specific for a given mesh tool (such as .axial or .merge) can be used as “mesh” input for any of the mesh tools discussed in this manual.

  11. Finite element program Lamcal. (User's manual)

    International Nuclear Information System (INIS)

    Lamain, L.G.; Blanckenburg, J.F.G.

    1982-01-01

    The present user's manual gives the input formats, job control and an input example for the finite element part of the Lamcal program. The input data have been organized in a more or less self explaining way, using keywords and standard input formats and is printed at the beginning of every run. To simplify the use of the whole program and to avoid unecessary data handling, all three parts of the Lamcal program, meshgeneration, plotting and, FE, are combined into one load module. This setup allows to do all calculations in one single run. However, preprocessing, postprocessing and restarts can be made in separate runs as well. The same reserved space for the dynamic core storage is used in all three parts, if the available space is not sufficient the FE program will stop

  12. UCB-NE-107 user's manual

    International Nuclear Information System (INIS)

    Lee, W.W.L.

    1989-03-01

    The purpose of this manual is to provide users of UCB-NE-107 with the information necessary to use UCB-NE-107 effectively. UCB-NE-107 is a computer code for calculating the fractional rate of readily soluble radionuclides that are released from nuclear waste emplaced in water-saturated porous media. Waste placed in such environments will gradually dissolve. For many species such as actinides and rare earths, the process of dissolution is governed by the exterior flow field, and the chemical reaction rate or leaching rate. However, for readily soluble species such as 135 Cs, 137 Cs, and 129 I, it has been observed that their dissolution rates are rapid. UCB-NE-107 is a code for calculating the release rate at the waste/rock interface, to check compliance with the US Nuclear Regulatory Commission's (USNRC) subsystem performance objective. It is an implementation of the analytic solution given below. 5 refs., 2 figs

  13. CalendF-2005: user manual

    International Nuclear Information System (INIS)

    Sublet, J.Ch.; Ribon, P.; Coste-Delclaux, M.

    2006-01-01

    CALENDF-2005 represents a Fortran-95 update of the 1994 code distribution with emphasize on programming quality and standard, physics and usage improvements. Devised to process multigroup cross-sections it relies on Gauss quadratures mathematical principle and strength. The followings processes can be handled by the code: moment probability tables and effective cross-sections calculation; regroups pointwise cross sections, probability tables and effective cross-sections; probability table condensation; probability table mix for several isotopes; probability table interpolation; effective cross section based probability table calculations; probability table calculations from effective cross-sections; cross-section comparison, complete energy pointwise cross-section processing and thickness dependant averaged transmission sample calculation, The CALENDF user manual, after having listed all principal code functions, describes sequentially each of them and gives comments on their associated output streams. Installation procedures, test cases and running time platforms comparisons are given in the appendix. (authors)

  14. User's manual for the TMAD code

    International Nuclear Information System (INIS)

    Finfrock, S.H.

    1995-01-01

    This document serves as the User's Manual for the TMAD code system, which includes the TMAD code and the LIBMAKR code. The TMAD code was commissioned to make it easier to interpret moisture probe measurements in the Hanford Site waste tanks. In principle, the code is an interpolation routine that acts over a library of benchmark data based on two independent variables, typically anomaly size and moisture content. Two additional variables, anomaly type and detector type, also can be considered independent variables, but no interpolation is done over them. The dependent variable is detector response. The intent is to provide the code with measured detector responses from two or more detectors. The code then will interrogate (and interpolate upon) the benchmark data library and find the anomaly-type/anomaly-size/moisture-content combination that provides the closest match to the measured data

  15. User Manual for the PROTEUS Mesh Tools

    International Nuclear Information System (INIS)

    Smith, Micheal A.; Shemon, Emily R.

    2015-01-01

    This report describes the various mesh tools that are provided with the PROTEUS code giving both descriptions of the input and output. In many cases the examples are provided with a regression test of the mesh tools. The most important mesh tools for any user to consider using are the MT M eshToMesh.x and the MT R adialLattice.x codes. The former allows the conversion between most mesh types handled by PROTEUS while the second allows the merging of multiple (assembly) meshes into a radial structured grid. Note that the mesh generation process is recursive in nature and that each input specific for a given mesh tool (such as .axial or .merge) can be used as ''mesh'' input for any of the mesh tools discussed in this manual.

  16. INTRA/Mod3.2. Manual and code description. Volume 2 - User's manual

    International Nuclear Information System (INIS)

    Andersson, Jenny; Edlund, O.; Hermann, J.; Johansson, Lise-Lotte

    1999-01-01

    The INTRA Manual consists of two volumes. Volume I of the manual is a thorough description of the code INTRA, the physical modelling of INTRA and the ruling numerics, and volume II, the User's Manual is an input description. This document, the User's Manual, Volume II, contains a detailed description of how to use INTRA, how to set up an input file, how to run INTRA and also post-processing

  17. Dairy Analytics and Nutrient Analysis (DANA) Prototype System User Manual

    Energy Technology Data Exchange (ETDEWEB)

    Sam Alessi; Dennis Keiser

    2012-10-01

    parameters be held and managed in a single managed data repository, while allows users to customize standard values and perform individual analysis. Server-based calculations can be easily extended, versions and upgrades managed, and any changes are immediately available to all users. This user manual describes how to use and/or modify input database tables, run DANA, view and modify reports.

  18. User Manual for Whisper-1.1

    Energy Technology Data Exchange (ETDEWEB)

    Brown, Forrest B. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Rising, Michael Evan [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Alwin, Jennifer Louise [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2017-01-26

    Whisper is a statistical analysis package developed in 2014 to support nuclear criticality safety (NCS) validation [1-3]. It uses the sensitivity profile data for an application as computed by MCNP6 [4-6] along with covariance files [7,8] for the nuclear data to determine a baseline upper-subcritical-limit (USL) for the application. Whisper version 1.0 was first developed and used at LANL in 2014 [3]. During 2015- 2016, Whisper was updated to version 1.1 and is to be included with the upcoming release of MCNP6.2. This document describes the user input and options for running whisper-1.1, including 2 perl utility scripts that simplify ordinary NCS work, whisper_mcnp.pl and whisper_usl.pl. For many detailed references on the theory, applications, nuclear data & covariances, SQA, verification-validation, adjointbased methods for sensitivity-uncertainty analysis, and more – see the Whisper – NCS Validation section of the MCNP Reference Collection at mcnp.lanl.gov. There are currently over 50 Whisper reference documents available.

  19. User Manual for Whisper-1.1

    International Nuclear Information System (INIS)

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

    2017-01-01

    Whisper is a statistical analysis package developed in 2014 to support nuclear criticality safety (NCS) validation [1-3]. It uses the sensitivity profile data for an application as computed by MCNP6 [4-6] along with covariance files [7,8] for the nuclear data to determine a baseline upper-subcritical-limit (USL) for the application. Whisper version 1.0 was first developed and used at LANL in 2014 [3]. During 2015- 2016, Whisper was updated to version 1.1 and is to be included with the upcoming release of MCNP6.2. This document describes the user input and options for running whisper-1.1, including 2 perl utility scripts that simplify ordinary NCS work, whisper_mcnp.pl and whisper_usl.pl. For many detailed references on the theory, applications, nuclear data & covariances, SQA, verification-validation, adjointbased methods for sensitivity-uncertainty analysis, and more - see the Whisper - NCS Validation section of the MCNP Reference Collection at mcnp.lanl.gov. There are currently over 50 Whisper reference documents available.

  20. AFTC Code for Automatic Fault Tree Construction: Users Manual

    International Nuclear Information System (INIS)

    Gopika Vinod; Saraf, R.K.; Babar, A.K.

    1999-04-01

    Fault Trees perform a predominant role in reliability and safety analysis of system. Manual construction of fault tree is a very time consuming task and moreover, it won't give a formalized result, since it relies highly on analysts experience and heuristics. This necessitates a computerised fault tree construction, which is still attracting interest of reliability analysts. AFTC software is a user friendly software model for constructing fault trees based on decision tables. Software is equipped with libraries of decision tables for components commonly used in various Nuclear Power Plant (NPP) systems. User is expected to make a nodal diagram of the system, for which fault tree is to be constructed, from the flow sheets available. The text nodal diagram goes as the sole input defining the system flow chart. AFTC software is a rule based expert system which draws the fault tree from the system flow chart and component decision tables. AFTC software gives fault tree in both text and graphic format. Help is provided as how to enter system flow chart and component decision tables. The software is developed in 'C' language. Software is verified with simplified version of the fire water system of an Indian PHWR. Code conversion will be undertaken to create a window based version. (author)

  1. User Manual for the Allpix$^2$ Simulation Framework

    CERN Document Server

    AUTHOR|(SzGeCERN)818092; Spannagel, Simon; Hynds, Daniel

    2017-01-01

    Several simulation tools exist for the detailed study of position sensitive silicon detectors, covering aspects ranging from the electrical properties of sensors to the behaviour of charged particles traversing a given detector setup. Each of these toolkits performs a very specialised task, and for the complete description of a silicon detector several such software packages must typically be used. Allpix$^2$ builds upon this work by providing a complete and easy-to-use C++ software package for simulating detector performance, from the interaction of particles to the digitisation of propagated carriers by the front-end electronics. A modular framework is used to flexibly add or remove modules from the simulation chain, each performing specific tasks such as interfacing to Geant4 to deposit energy in the detector and provide an accurate description of material effects, or the propagation of deposited charges through the sensor bulk. This document presents the user manual of the software as of release version 1...

  2. UCB-NE-101 user's manual

    International Nuclear Information System (INIS)

    Lee, W.W.L.

    1989-02-01

    The purpose of this manual is to provide users of UCB-NE-101 with the information necessary to use UCB-NE-101 effectively. UCB-NE-101 calculates the concentration of solubility-limited species as a function of space and time and its mass flux rates from a waste sphere buried in a nuclear waste repository in water-saturated rock. The waste is surrounded by one type of rock, and some distance away, there is another type of rock. The inner layer of rock can be a backfill around a nuclear waste package and the outer layer the natural rock. The mass flux calculated is at the interface of the two layers. The species concentration calculated is in the inner layer. A constant concentration of the species, usually the solubility, is specified at the waste sphere/inner layer interface. Dissolution and transport is governed by the solubility of the species, and diffusion in the porous media. 1 ref., 1 fig

  3. Database on wind characteristics. Users manual

    Energy Technology Data Exchange (ETDEWEB)

    Larsen, G.C.; Hansen, K.S.

    2001-11-01

    The main objective of IEA R and D Wind Annex XVII - Database on Wind Characteristics - is to provide wind energy planners and designers, as well as the international wind engineering community in general, with easy access to quality controlled measured wind field time series observed in a wide range of environments. The project partners are Sweden, Norway, U.S.A., The Netherlands, Japan and Denmark, with Denmark as the Operating Agent. The reporting of IEA R and D Annex XVII falls in three separate parts. Part one deals with the overall structure and philosophy behind the database (including the applied data quality control procedures), part two accounts in details for the available data in the established database bank and part three is the Users Manual describing the various ways to access and analyse the data. The present report constitutes part three of the Annex XVII reporting and contains a trough description of the available online facilities for identifying, selecting, downloading and handling measured wind field time series and resource data from 'Database on Wind Characteristics'. (au)

  4. The neutron transport code DTF-Traca users manual and input data

    Energy Technology Data Exchange (ETDEWEB)

    Ahnert, C

    1979-07-01

    This is a users manual of the neutron transport code DTF-TRACA, which is a version of the original DTF-IV with some modifications made at JEN. A detailed input data descriptions is given. The new options developed at JEN are included too. (Author) 18 refs.

  5. The neutron transport code DTF-Traca users manual and input data

    International Nuclear Information System (INIS)

    Ahnert, C.

    1979-01-01

    This is a users manual of the neutron transport code DTF-TRACA, which is a version of the original DTF-IV with some modifications made at JEN. A detailed input data descriptions is given. The new options developed at JEN are included too. (Author) 18 refs

  6. The neutron transport code DTF-TRACA. User's manual and input data

    International Nuclear Information System (INIS)

    Anhert, C.

    1979-01-01

    A user's manual of the neutron transport code DTF-TRACA, which is a version of the original DTF-IV with some modifications made at JEN. A detailed input data description is given. The new options developped at JEN are included too. (author)

  7. TOUGH2 User's Guide Version 2

    International Nuclear Information System (INIS)

    Pruess, K.; Oldenburg, C.M.; Moridis, G.J.

    1999-01-01

    TOUGH2 is a numerical simulator for nonisothermal flows of multicomponent, multiphase fluids in one, two, and three-dimensional porous and fractured media. The chief applications for which TOUGH2 is designed are in geothermal reservoir engineering, nuclear waste disposal, environmental assessment and remediation, and unsaturated and saturated zone hydrology. TOUGH2 was first released to the public in 1991; the 1991 code was updated in 1994 when a set of preconditioned conjugate gradient solvers was added to allow a more efficient solution of large problems. The current Version 2.0 features several new fluid property modules and offers enhanced process modeling capabilities, such as coupled reservoir-wellbore flow, precipitation and dissolution effects, and multiphase diffusion. Numerous improvements in previously released modules have been made and new user features have been added, such as enhanced linear equation solvers, and writing of graphics files. The T2VOC module for three-phase flows of water, air and a volatile organic chemical (VOC), and the T2DM module for hydrodynamic dispersion in 2-D flow systems have been integrated into the overall structure of the code and are included in the Version 2.0 package. Data inputs are upwardly compatible with the previous version. Coding changes were generally kept to a minimum, and were only made as needed to achieve the additional functionalities desired. TOUGH2 is written in standard FORTRAN77 and can be run on any platform, such as workstations, PCs, Macintosh, mainframe and supercomputers, for which appropriate FORTRAN compilers are available. This report is a self-contained guide to application of TOUGH2 to subsurface flow problems. It gives a technical description of the TOUGH2 code, including a discussion of the physical processes modeled, and the mathematical and numerical methods used. Illustrative sample problems are presented along with detailed instructions for preparing input data

  8. User Manual for the PROTEUS Mesh Tools

    Energy Technology Data Exchange (ETDEWEB)

    Smith, Micheal A. [Argonne National Lab. (ANL), Argonne, IL (United States); Shemon, Emily R [Argonne National Lab. (ANL), Argonne, IL (United States)

    2016-09-19

    PROTEUS is built around a finite element representation of the geometry for visualization. In addition, the PROTEUS-SN solver was built to solve the even-parity transport equation on a finite element mesh provided as input. Similarly, PROTEUS-MOC and PROTEUS-NEMO were built to apply the method of characteristics on unstructured finite element meshes. Given the complexity of real world problems, experience has shown that using commercial mesh generator to create rather simple input geometries is overly complex and slow. As a consequence, significant effort has been put into place to create multiple codes that help assist in the mesh generation and manipulation. There are three input means to create a mesh in PROTEUS: UFMESH, GRID, and NEMESH. At present, the UFMESH is a simple way to generate two-dimensional Cartesian and hexagonal fuel assembly geometries. The UFmesh input allows for simple assembly mesh generation while the GRID input allows the generation of Cartesian, hexagonal, and regular triangular structured grid geometry options. The NEMESH is a way for the user to create their own mesh or convert another mesh file format into a PROTEUS input format. Given that one has an input mesh format acceptable for PROTEUS, we have constructed several tools which allow further mesh and geometry construction (i.e. mesh extrusion and merging). This report describes the various mesh tools that are provided with the PROTEUS code giving both descriptions of the input and output. In many cases the examples are provided with a regression test of the mesh tools. The most important mesh tools for any user to consider using are the MT_MeshToMesh.x and the MT_RadialLattice.x codes. The former allows the conversion between most mesh types handled by PROTEUS while the second allows the merging of multiple (assembly) meshes into a radial structured grid. Note that the mesh generation process is recursive in nature and that each input specific for a given mesh tool (such as .axial

  9. PETSc Users Manual Revision 3.3

    Energy Technology Data Exchange (ETDEWEB)

    Balay, S. [Argonne National Lab. (ANL), Argonne, IL (United States). Mathematics and Computer Science Division; Brown, J. [Argonne National Lab. (ANL), Argonne, IL (United States). Mathematics and Computer Science Division; Buschelman, K. [Argonne National Lab. (ANL), Argonne, IL (United States). Mathematics and Computer Science Division; Eijkhout, V. [Argonne National Lab. (ANL), Argonne, IL (United States). Mathematics and Computer Science Division; Gropp, W. [Argonne National Lab. (ANL), Argonne, IL (United States). Mathematics and Computer Science Division; Kaushik, D. [Argonne National Lab. (ANL), Argonne, IL (United States). Mathematics and Computer Science Division; Knepley, M. [Argonne National Lab. (ANL), Argonne, IL (United States). Mathematics and Computer Science Division; McInnes, L. Curfman [Argonne National Lab. (ANL), Argonne, IL (United States). Mathematics and Computer Science Division; Smith, B. [Argonne National Lab. (ANL), Argonne, IL (United States). Mathematics and Computer Science Division; Zhang, H. [Argonne National Lab. (ANL), Argonne, IL (United States). Mathematics and Computer Science Division

    2013-05-11

    This manual describes the use of PETSc for the numerical solution of partial differential equations and related problems on high-performance computers. The Portable, Extensible Toolkit for Scientific Computation (PETSc) is a suite of data structures and routines that provide the building blocks for the implementation of large-scale application codes on parallel (and serial) computers. PETSc uses the MPI standard for all message-passing communication. PETSc includes an expanding suite of parallel linear, nonlinear equation solvers and time integrators that may be used in application codes written in Fortran, C, C++, Python, and MATLAB (sequential). PETSc provides many of the mechanisms needed within parallel application codes, such as parallel matrix and vector assembly routines. The library is organized hierarchically, enabling users to employ the level of abstraction that is most appropriate for a particular problem. By using techniques of object-oriented programming, PETSc provides enormous flexibility for users. PETSc is a sophisticated set of software tools; as such, for some users it initially has a much steeper learning curve than a simple subroutine library. In particular, for individuals without some computer science background, experience programming in C, C++ or Fortran and experience using a debugger such as gdb or dbx, it may require a significant amount of time to take full advantage of the features that enable efficient software use. However, the power of the PETSc design and the algorithms it incorporates may make the efficient implementation of many application codes simpler than “rolling them” yourself; For many tasks a package such as MATLAB is often the best tool; PETSc is not intended for the classes of problems for which effective MATLAB code can be written. PETSc also has a MATLAB interface, so portions of your code can be written in MATLAB to “try out” the PETSc solvers. The resulting code will not be scalable however because

  10. PETSc Users Manual Revision 3.5

    Energy Technology Data Exchange (ETDEWEB)

    Balay, S. [Argonne National Lab. (ANL), Argonne, IL (United States). Mathematics and Computer Science Division; Abhyankar, S. [Argonne National Lab. (ANL), Argonne, IL (United States). Mathematics and Computer Science Division; Adams, M. [Argonne National Lab. (ANL), Argonne, IL (United States). Mathematics and Computer Science Division; Brown, J. [Argonne National Lab. (ANL), Argonne, IL (United States). Mathematics and Computer Science Division; Brune, P. [Argonne National Lab. (ANL), Argonne, IL (United States). Mathematics and Computer Science Division; Buschelman, K. [Argonne National Lab. (ANL), Argonne, IL (United States). Mathematics and Computer Science Division; Eijkhout, V. [Argonne National Lab. (ANL), Argonne, IL (United States). Mathematics and Computer Science Division; Gropp, W. [Argonne National Lab. (ANL), Argonne, IL (United States). Mathematics and Computer Science Division; Kaushik, D. [Argonne National Lab. (ANL), Argonne, IL (United States). Mathematics and Computer Science Division; Knepley, M. [Argonne National Lab. (ANL), Argonne, IL (United States). Mathematics and Computer Science Division; McInnes, L. Curfman [Argonne National Lab. (ANL), Argonne, IL (United States). Mathematics and Computer Science Division; Rupp, K. [Argonne National Lab. (ANL), Argonne, IL (United States). Mathematics and Computer Science Division; Smith, B. [Argonne National Lab. (ANL), Argonne, IL (United States). Mathematics and Computer Science Division; Zhang, H. [Argonne National Lab. (ANL), Argonne, IL (United States). Mathematics and Computer Science Division

    2014-09-08

    This manual describes the use of PETSc for the numerical solution of partial differential equations and related problems on high-performance computers. The Portable, Extensible Toolkit for Scientific Computation (PETSc) is a suite of data structures and routines that provide the building blocks for the implementation of large-scale application codes on parallel (and serial) computers. PETSc uses the MPI standard for all message-passing communication. PETSc includes an expanding suite of parallel linear, nonlinear equation solvers and time integrators that may be used in application codes written in Fortran, C, C++, Python, and MATLAB (sequential). PETSc provides many of the mechanisms needed within parallel application codes, such as parallel matrix and vector assembly routines. The library is organized hierarchically, enabling users to employ the level of abstraction that is most appropriate for a particular problem. By using techniques of object-oriented programming, PETSc provides enormous flexibility for users. PETSc is a sophisticated set of software tools; as such, for some users it initially has a much steeper learning curve than a simple subroutine library. In particular, for individuals without some computer science background, experience programming in C, C++ or Fortran and experience using a debugger such as gdb or dbx, it may require a significant amount of time to take full advantage of the features that enable efficient software use. However, the power of the PETSc design and the algorithms it incorporates may make the efficient implementation of many application codes simpler than “rolling them” yourself. ;For many tasks a package such as MATLAB is often the best tool; PETSc is not intended for the classes of problems for which effective MATLAB code can be written. PETSc also has a MATLAB interface, so portions of your code can be written in MATLAB to “try out” the PETSc solvers. The resulting code will not be scalable however because

  11. PETSc Users Manual Revision 3.4

    Energy Technology Data Exchange (ETDEWEB)

    Balay, S. [Argonne National Lab. (ANL), Argonne, IL (United States). Mathematics and Computer Science Division; Brown, J. [Argonne National Lab. (ANL), Argonne, IL (United States). Mathematics and Computer Science Division; Buschelman, K. [Argonne National Lab. (ANL), Argonne, IL (United States). Mathematics and Computer Science Division; Eijkhout, V. [Argonne National Lab. (ANL), Argonne, IL (United States). Mathematics and Computer Science Division; Gropp, W. [Argonne National Lab. (ANL), Argonne, IL (United States). Mathematics and Computer Science Division; Kaushik, D. [Argonne National Lab. (ANL), Argonne, IL (United States). Mathematics and Computer Science Division; Knepley, M. [Argonne National Lab. (ANL), Argonne, IL (United States). Mathematics and Computer Science Division; McInnes, L. Curfman [Argonne National Lab. (ANL), Argonne, IL (United States). Mathematics and Computer Science Division; Smith, B. [Argonne National Lab. (ANL), Argonne, IL (United States). Mathematics and Computer Science Division; Zhang, H. [Argonne National Lab. (ANL), Argonne, IL (United States). Mathematics and Computer Science Division

    2014-06-29

    This manual describes the use of PETSc for the numerical solution of partial differential equations and related problems on high-performance computers. The Portable, Extensible Toolkit for Scientific Computation (PETSc) is a suite of data structures and routines that provide the building blocks for the implementation of large-scale application codes on parallel (and serial) computers. PETSc uses the MPI standard for all message-passing communication. PETSc includes an expanding suite of parallel linear, nonlinear equation solvers and time integrators that may be used in application codes written in Fortran, C, C++, Python, and MATLAB (sequential). PETSc provides many of the mechanisms needed within parallel application codes, such as parallel matrix and vector assembly routines. The library is organized hierarchically, enabling users to employ the level of abstraction that is most appropriate for a particular problem. By using techniques of object-oriented programming, PETSc provides enormous flexibility for users. PETSc is a sophisticated set of software tools; as such, for some users it initially has a much steeper learning curve than a simple subroutine library. In particular, for individuals without some computer science background, experience programming in C, C++ or Fortran and experience using a debugger such as gdb or dbx, it may require a significant amount of time to take full advantage of the features that enable efficient software use. However, the power of the PETSc design and the algorithms it incorporates may make the efficient implementation of many application codes simpler than “rolling them” yourself; For many tasks a package such as MATLAB is often the best tool; PETSc is not intended for the classes of problems for which effective MATLAB code can be written. PETSc also has a MATLAB interface, so portions of your code can be written in MATLAB to “try out” the PETSc solvers. The resulting code will not be scalable however because

  12. Facility Interface Capability Assessment (FICA) user manual

    International Nuclear Information System (INIS)

    Pope, R.B.; MacDonald, R.R.; Massaglia, J.L.; Williamson, D.A.; Viebrock, J.M.; Mote, N.

    1995-09-01

    The US Department of Energy's (DOE) Office of Civilian Radioactive Waste Management (OCRWM) is responsible for developing the Civilian Radioactive Waste Management System (CRWMS) to accept spent nuclear fuel from commercial facilities. The objective of the Facility Interface Capability Assessment (FICA) project was to assess the capability of each commercial spent nuclear fuel (SNF) storage facility, at which SNF is stored, to handle various SNF shipping casks. The purpose of this report is describe the FICA computer software and to provide the FICA user with a guide on how to use the FICA system. The FICA computer software consists of two executable programs: the FICA Reactor Report program and the FICA Summary Report program (written in the Ca-Clipper version 5.2 development system). The complete FICA software system is contained on either a 3.5 in. (double density) or a 5.25 in. (high density) diskette and consists of the two FICA programs and all the database files (generated using dBASE III). The FICA programs are provided as ''stand alone'' systems and neither the Ca-Clipper compiler nor dBASE III is required to run the FICA programs. The steps for installing the FICA software system and executing the FICA programs are described in this report. Instructions are given on how to install the FICA software system onto the hard drive of the PC and how to execute the FICA programs from the FICA subdirectory on the hard drive. Both FICA programs are menu driven with the up-arrow and down-arrow keys used to move the cursor to the desired selection

  13. Equipment Qualification Data Base user manual

    International Nuclear Information System (INIS)

    Decker, Q.R.; Fackrell, L.J.; Fitch, L.R.; Meeky, O.B.

    1985-09-01

    This manual details the Equipment Qualification Data Base (EQDB), its usage, and contents. The EQDB consists of two files; the Plant Qualification File (PQF) and the Equipment Qualification File (EQF). The PQF contains plant specific environmental data and the EQF contains summaries of various test results. Two data management systems are used to manipulate the data and are discussed in this manual. SAS Institute System 2000 (S2K) is the management system for the PQF and Query Update (QU) is the operating system for the EQF. Each management system contains report writers. These writers and how to use them are discussed in detail in this manual

  14. Quality manual for the Danish greenhouse gas inventory. Version 2

    Energy Technology Data Exchange (ETDEWEB)

    Nielsen, O.-K.; Plejdrup, M.S.; Winther, M. [and others

    2013-02-15

    This report outlines the quality work undertaken by the emission inventory group at the Department of Environmental Science, Aarhus University in connection with the preparation and reporting of the Danish greenhouse gas inventory. This report updates and expands on the first version of the quality manual published in 2005. The report fulfils the mandatory requirements for a quality assurance/quality control (QA/QC) plan as lined out in the UNFCCC reporting guidelines and the specifications related to reporting under the Kyoto Protocol. The report describes all elements of the internal QC procedures as well as the QA and verification activities carried out in connection with the Danish greenhouse gas inventory. (Author)

  15. PAVECHECK : training material updated user's manual including GPS.

    Science.gov (United States)

    2009-01-01

    PAVECHECK is a software package used to integrate nondestructive test data from various testing systems to provide the pavement engineer with a comprehensive evaluation of both surface and subsurface conditions. This User's Manual is intended to demo...

  16. Prototype road weather performance management tool : installation instructions & user manual.

    Science.gov (United States)

    2016-07-20

    This document is the Installation Instructions and User Manual for the Road Weather Performance Management (RW-PM) Tool developed for the project on Development and Demonstration of a Prototype Road Weather Performance Management Application that Use...

  17. SSC-K code user's manual

    Energy Technology Data Exchange (ETDEWEB)

    Kwon, Y M; Lee, Y B; Chang, W P; Hahn, D

    2000-07-01

    , constitutive laws and correlations required to execute the SSC-K are described. It is noted that the user's manual will be revised later with the further development of SSC-K.

  18. Applying Minimal Manual Principles for Documentation of Graphical User Interfaces.

    Science.gov (United States)

    Nowaczyk, Ronald H.; James, E. Christopher

    1993-01-01

    Investigates the need to include computer screens in documentation for software using a graphical user interface. Describes the uses and purposes of "minimal manuals" and their principles. Studies student reaction to their use of one of three on-screen manuals: screens, icon, and button. Finds some benefit for including icon and button…

  19. Integrated Reliability and Risk Analysis System (IRRAS), Version 2.5: Reference manual

    International Nuclear Information System (INIS)

    Russell, K.D.; McKay, M.K.; Sattison, M.B.; Skinner, N.L.; Wood, S.T.; Rasmuson, D.M.

    1991-03-01

    The Integrated Reliability and Risk Analysis System (IRRAS) is a state-of-the-art, microcomputer-based probabilistic risk assessment (PRA) model development and analysis tool to address key nuclear plant safety issues. IRRAS is an integrated software tool that gives the user the ability to create and analyze fault trees and accident sequences using a microcomputer. This program provides functions that range from graphical fault tree construction to cut set generation and quantification. Version 1.0 of the IRRAS program was released in February of 1987. Since that time, many user comments and enhancements have been incorporated into the program providing a much more powerful and user-friendly system. This version has been designated IRRAS 2.5 and is the subject of this Reference Manual. Version 2.5 of IRRAS provides the same capabilities as Version 1.0 and adds a relational data base facility for managing the data, improved functionality, and improved algorithm performance. 7 refs., 348 figs

  20. Rad Chem data acquisition chassis users manual

    International Nuclear Information System (INIS)

    Jones, B.A.

    1980-01-01

    The Shiva Laser at LLL requires many forms of diagnostics to measure and analyze fusion experiments. This manual describes the operation of a Micro-Processor controlled data acquisition system designed at LLL to measure Neutron Activation during fusion experiments on the Shiva Laser

  1. User Manual for SSG Power Simulation 2

    DEFF Research Database (Denmark)

    Jensen, Palle Meinert; Gilling, Lasse; Kofoed, Jens Peter

    This manual gives a detailed description of the use of the computer program SSG Power Simulation 2. Furthermore, the underlying mathematics and algorithms are briefly described. The program is based on experimental data from model testing of Seawave Slot-Cone Generator (SSG) presented in Kofoed...

  2. User's manual for the master equipment list. Phase 1

    International Nuclear Information System (INIS)

    Sandoval, J.D.

    1997-01-01

    This manual is intended to provide a user with enough detailed instruction to guide them through the Master Equipment List Phase 1 (MEL Phase 1) application system operations. The MEL Phase 1 application is a database system that stores Equipment Identification Number (EIN) information to support equipment tracking in the 200E and 200W Tank Farms for the Tank Waste Remediation System Division. The MEL Phase 1 application supports both the user application and administrative control functions. The user application functions include: viewing by Folder, reporting, performing queries, and editing specific data. The administrative control functions include: maintaining valid user identifications, passwords, privileges, defining drop-down lists, and review of the change log relating to EIN data entries, additions, deletions, and editing. The scope of this User's Manual is to discuss these functions and is intended to guide users and answer questions regarding the MEL Phase 1 application

  3. PETSc Users Manual Revision 3.7

    Energy Technology Data Exchange (ETDEWEB)

    Balay, S.; Brune, P.; Buschelman, K.; Gropp, W.; Karpeyev, D.; Kaushik, D.; Knepley, M.; McInnes, L. Curfman; Rupp, K.; Smith, B.; Zhang, H.; Abhyankar, S.; Adams, M.; Dalcin, L.; Zampini, S.; Zhang, H.

    2016-04-01

    This manual describes the use of PETSc for the numerical solution of partial differential equations and related problems on high-performance computers. The Portable, Extensible Toolkit for Scientific Computation (PETSc) is a suite of data structures and routines that provide the building blocks for the implementation of large-scale application codes on parallel (and serial) computers. PETSc uses the MPI standard for all message-passing communication.

  4. PETSc Users Manual Revision 3.8

    Energy Technology Data Exchange (ETDEWEB)

    Balay, S. [Argonne National Lab. (ANL), Argonne, IL (United States); Abhyankar, S. [Argonne National Lab. (ANL), Argonne, IL (United States); Adams, M. [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States); Brown, J. [Argonne National Lab. (ANL), Argonne, IL (United States); Brune, P. [Argonne National Lab. (ANL), Argonne, IL (United States); Buschelman, K. [Argonne National Lab. (ANL), Argonne, IL (United States); Dalcin, L. D. [King Abdullah Univ. of Science and Technology, Thuwal (Saudi Arabia); Eijkhout, V. [Univ. of Texas, Austin, TX (United States); Gropp, W. [Argonne National Lab. (ANL), Argonne, IL (United States); Kaushik, D. [Argonne National Lab. (ANL), Argonne, IL (United States); Knepley, M. [Argonne National Lab. (ANL), Argonne, IL (United States); May, D. [ETH Zurich (Switzerland); McInnes, L. Curfman [Argonne National Lab. (ANL), Argonne, IL (United States); Munson, T. [Argonne National Lab. (ANL), Argonne, IL (United States); Rupp, K. [Argonne National Lab. (ANL), Argonne, IL (United States); Sanan, P. [Univ. of Italian Switzerland, Lugano (Switzerland); Smith, B. [Argonne National Lab. (ANL), Argonne, IL (United States); Zampini, S. [King Abdullah Univ. of Science and Technology, Thuwal (Saudi Arabia); Zhang, H. [Illinois Inst. of Technology, Chicago, IL (United States); Zhang, H. [Argonne National Lab. (ANL), Argonne, IL (United States)

    2017-09-01

    This manual describes the use of PETSc for the numerical solution of partial differential equations and related problems on high-performance computers. The Portable, Extensible Toolkit for Scientific Computation (PETSc) is a suite of data structures and routines that provide the building blocks for the implementation of large-scale application codes on parallel (and serial) computers. PETSc uses the MPI standard for all message-passing communication.

  5. Infrastructure Management Information System User Manual

    Science.gov (United States)

    1998-10-01

    This publication describes and explains the user interface for the Infrastructure Management Information System (IMIS). The IMIS is designed to answer questions regarding public water supply, wastewater treatment, and census information. This publica...

  6. The International Nuclear Event Scale (INES) user's manual. 2001 edition

    International Nuclear Information System (INIS)

    2001-12-01

    The International Nuclear Event Scale (INES) was introduced in March 1990 jointly by the International Atomic Energy Agency (IAEA) and the Nuclear Energy Agency of the Organisation for Economic Co-operation and Development (OECD/NEA). Its primary purpose is to facilitate communication and understanding between the nuclear community, the media and the public on the safety significance of events occurring at nuclear installations. The scale was refined in 1992 in the light of experience gained and extended to be applicable to any event associated with radioactive material and/or radiation, including the transport of radioactive materials.This edition of the INES User's Manual incorporates experience gained from applying the 1992 version of the scale and the document entitled 'Clarification of Issues Raised'. As such, it replaces those earlier publications. It does not amend the technical basis of the INES rating procedure but is expected to facilitate the task of those who are required to rate the safety significance of events using the INES scale. The INES communication network currently receives and disseminates event information to the INES National Officers of 60 Member States on special Event Rating Forms which represent official information on the events, including the rating. The INES communication process has led each participating country to set up an internal network which ensures that all events are promptly communicated and rated whenever they have to be reported outside or inside the country. The IAEA provides training services on the use of INES on request

  7. INES - The International Nuclear Event Scale. User's manual

    International Nuclear Information System (INIS)

    2005-01-01

    The International Nuclear Event Scale (INES) was introduced in March 1990 jointly by the International Atomic Energy Agency (IAEA) and the Nuclear Energy Agency of the Organisation for Economic Co-operation and Development (OECD/NEA). Its primary purpose is to facilitate communication and understanding between the nuclear community, the media and the public on the safety significance of events occurring at nuclear installations. The scale was refined in 1992 in the light of experience gained and extended to be applicable to any event associated with radioactive material and/or radiation, including the transport of radioactive materials. This edition of the INES User's Manual incorporates experience gained from applying the 1992 version of the scale and the document entitled 'Clarification of Issues Raised'. As such, it replaces those earlier publications. It does not amend the technical basis of the INES rating procedure but is expected to facilitate the task of those who are required to rate the safety significance of events using the INES scale. The INES communication network currently receives and disseminates event information to the INES National Officers of 60 Member States on special Event Rating Forms which represent official information on the events, including the rating. The INES communication process has led each participating country to set up an internal network which ensures that all events are promptly communicated and rated whenever they have to be reported outside or inside the country. The IAEA provides training services on the use of INES on request

  8. The International Nuclear Event Scale (INES) user's manual. 2001 edition

    International Nuclear Information System (INIS)

    2001-02-01

    The International Nuclear Event Scale (INES) was introduced in March 1990 jointly by the International Atomic Energy Agency (IAEA) and the Nuclear Energy Agency of the Organisation for Economic Co-operation and Development (OECD/NEA). Its primary purpose is to facilitate communication and understanding between the nuclear community, the media and the public on the safety significance of events occurring at nuclear installations. The scale was refined in 1992 in the light of experience gained and extended to be applicable to any event associated with radioactive material and/or radiation, including the transport of radioactive materials.This edition of the INES User's Manual incorporates experience gained from applying the 1992 version of the scale and the document entitled ''Clarification of Issues Raised''. As such, it replaces those earlier publications. It does not amend the technical basis of the INES rating procedure but is expected to facilitate the task of those who are required to rate the safety significance of events using the INES scale. The INES communication network currently receives and disseminates event information to the INES National Officers of 60 Member States on special Event Rating Forms which represent official information on the events, including the rating. The INES communication process has led each participating country to set up an internal network which ensures that all events are promptly communicated and rated whenever they have to be reported outside or inside the country. The IAEA provides training services on the use of INES on request

  9. WASTES: Wastes system transportation and economic simulation: Version 2, Programmer's reference manual

    International Nuclear Information System (INIS)

    Buxbaum, M.E.; Shay, M.R.

    1986-11-01

    The WASTES Version II (WASTES II) Programmer's Reference Manual was written to document code development activities performed under the Monitored Retrievable Storage (MRS) Program at Pacific Northwest Laboratory (PNL). The manual will also serve as a valuable tool for programmers involved in maintenance of and updates to the WASTES II code. The intended audience for this manual are experienced FORTRAN programmers who have only a limited knowledge of nuclear reactor operation, the nuclear fuel cycle, or nuclear waste management practices. It is assumed that the readers of this manual have previously reviewed the WASTES II Users Guide published as PNL Report 5714. The WASTES II code is written in FORTRAN 77 as an extension to the SLAM commercial simulation package. The model is predominately a FORTRAN based model that makes extensive use of the SLAM file maintenance and time management routines. This manual documents the general manner in which the code is constructed and the interactions between SLAM and the WASTES subroutines. The functionality of each of the major WASTES subroutines is illustrated with ''block flow'' diagrams. The basic function of each of these subroutines, the algorithms used in them, and a discussion of items of particular note in the subroutine are reviewed in this manual. The items of note may include an assumption, a coding practice that particularly applies to a subroutine, or sections of the code that are particularly intricate or whose mastery may be difficult. The appendices to the manual provide extensive detail on the use of arrays, subroutines, included common blocks, parameters, variables, and files

  10. Important wheelchair skills for new manual wheelchair users: health care professional and wheelchair user perspectives.

    Science.gov (United States)

    Morgan, Kerri A; Engsberg, Jack R; Gray, David B

    2017-01-01

    The purpose of this project was to identify wheelchair skills currently being taught to new manual wheelchair users, identify areas of importance for manual wheelchair skills' training during initial rehabilitation, identify similarities and differences between the perspectives of health care professionals and manual wheelchair users and use the ICF to organize themes related to rehabilitation and learning how to use a manual wheelchair. Focus groups were conducted with health care professionals and experienced manual wheelchair users. ICF codes were used to identify focus group themes. The Activities and Participation codes were more frequently used than Structure, Function and Environment codes. Wheelchair skills identified as important for new manual wheelchair users included propulsion techniques, transfers in an out of the wheelchair, providing maintenance to the wheelchair and navigating barriers such as curbs, ramps and rough terrain. Health care professionals and manual wheelchair users identified the need to incorporate the environment (home and community) into the wheelchair training program. Identifying essential components for training the proper propulsion mechanics and wheelchair skills in new manual wheelchair users is an important step in preventing future health and participation restrictions. Implications for Rehabilitation Wheelchair skills are being addressed frequently during rehabilitation at the activity-dependent level. Propulsion techniques, transfers in an out of the wheelchair, providing maintenance to the wheelchair and navigating barriers such as curbs, ramps and rough terrain are important skills to address during wheelchair training. Environment factors (in the home and community) are important to incorporate into wheelchair training to maximize safe and multiple-environmental-setting uses of manual wheelchairs. The ICF has application to understanding manual wheelchair rehabilitation for wheelchair users and therapists for improving

  11. TALENT user's manual.

    Energy Technology Data Exchange (ETDEWEB)

    Merchant, Bion John

    2012-01-01

    The Ground-Based Monitoring R and E Component Evaluation project performs testing on the hardware components that make up Seismic and Infrasound monitoring systems. The majority of the testing is focused on the Digital Waveform Recorder (DWR), Seismic Sensor, and Infrasound Sensor. The software tool used to capture and analyze the data collected from testing is called TALENT: Test and Analysis Evaluation Tool. This document is the manual for using TALENT. Other reports document the testing procedures that are in place (Kromer, 2007) and the algorithms employed in the test analysis (Merchant, 2011).

  12. YAQUI user's manual for fireball calculations

    International Nuclear Information System (INIS)

    Norton, J.L.; Ruppel, H.M.

    1976-12-01

    Recent modifications and additions made to the YAQUI code are described. This code, which was written to simulate nuclear explosions in the atmosphere, has been improved to include the effects of turbulence. In addition, it now allows input data to be obtained by direct interpolation in the one-dimensional results of early time radiation codes. This new version also makes most of the input free-format (namelist) and is composed of modules for easier modification and isolation of computer system dependence

  13. Design Optimization Toolkit: Users' Manual

    Energy Technology Data Exchange (ETDEWEB)

    Aguilo Valentin, Miguel Alejandro [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States). Computational Solid Mechanics and Structural Dynamics

    2014-07-01

    The Design Optimization Toolkit (DOTk) is a stand-alone C++ software package intended to solve complex design optimization problems. DOTk software package provides a range of solution methods that are suited for gradient/nongradient-based optimization, large scale constrained optimization, and topology optimization. DOTk was design to have a flexible user interface to allow easy access to DOTk solution methods from external engineering software packages. This inherent flexibility makes DOTk barely intrusive to other engineering software packages. As part of this inherent flexibility, DOTk software package provides an easy-to-use MATLAB interface that enables users to call DOTk solution methods directly from the MATLAB command window.

  14. Reliability and Maintainability Model (RAM): User and Maintenance Manual. Part 2; Improved Supportability Analysis

    Science.gov (United States)

    Ebeling, Charles E.

    1996-01-01

    This report documents the procedures for utilizing and maintaining the Reliability & Maintainability Model (RAM) developed by the University of Dayton for the National Aeronautics and Space Administration (NASA) Langley Research Center (LaRC). The purpose of the grant is to provide support to NASA in establishing operational and support parameters and costs of proposed space systems. As part of this research objective, the model described here was developed. This Manual updates and supersedes the 1995 RAM User and Maintenance Manual. Changes and enhancements from the 1995 version of the model are primarily a result of the addition of more recent aircraft and shuttle R&M data.

  15. User's manual for a process model code

    International Nuclear Information System (INIS)

    Kern, E.A.; Martinez, D.P.

    1981-03-01

    The MODEL code has been developed for computer modeling of materials processing facilities associated with the nuclear fuel cycle. However, it can also be used in other modeling applications. This report provides sufficient information for a potential user to apply the code to specific process modeling problems. Several examples that demonstrate most of the capabilities of the code are provided

  16. Database on wind characteristics. Users manual

    DEFF Research Database (Denmark)

    Larsen, Gunner Chr.; Hansen, K.S.

    2001-01-01

    quality control procedures), part two accounts in details for the available data in the established database bank and part three is the Users Manualdescribing the various ways to access and analyse the data. The present report constitutes part three of the Annex XVII reporting and contains a trough...

  17. SSC-K code users manual (rev.1)

    International Nuclear Information System (INIS)

    Kwon, Y. M.; Lee, Y. B.; Chang, W. P.; Hahn, D.

    2002-01-01

    The Supper System Code of KAERI (SSC-K) is a best-estimate system code for analyzing a variety of off-normal or accidents in the heat transport system of a pool type LMR design. It is being developed at Korea Atomic Energy Research Institution (KAERI) on the basis of SSC-L, originally developed at BNL to analyze loop-type LMR transients. SSC-K can handle both designs of loop and pool type LMRs. SSC-K contains detailed mechanistic models of transient thermal, hydraulic, neutronic, and mechanical phenomena to describe the response of the reactor core, coolant, fuel elements, and structures to accident conditions. This report provides a revised User's Manual (rev.1) of the SSC-K computer code, focusing on phenomenological model descriptions for new thermal, hydraulic, neutronic, and mechanical modules. A comprehensive description of the models for pool-type reactor is given in Chapters 2 and 3; the steady-state plant characterization, prior to the initiation of transient is described in Chapter 2 and their transient counterparts are discussed in Chapter 3. Discussions on the intermediate heat exchanger (IHX) and the electromagnetic (EM) pump are described in Chapter 4 and 5, respectively. A model of passive safety decay heat removal system (PSDRS) is discussed in Chapter 6, and models for various reactivity feedback effects are discussed in Chapter 7. In Chapter 8, constitutive laws and correlations required to execute the SSC-K are described. New models developed for SSC-K rev.1 are two dimensional hot pool model in Chapter 9, and long term cooling model in Chapter 10. Finally, a brief description of MINET code adopted to simulate BOP is presented in Chapter 11. Based on test runs for typical LMFBR accident analyses, it was found that the present version of SSC-K would be used for the safety analysis of KALIMER. However, the further validation of SSC-K is required for real applications. It is noted that the user's manual of SSC-K will be revised later with the

  18. User's manual for a measurement simulation code

    International Nuclear Information System (INIS)

    Kern, E.A.

    1982-07-01

    The MEASIM code has been developed primarily for modeling process measurements in materials processing facilities associated with the nuclear fuel cycle. In addition, the code computes materials balances and the summation of materials balances along with associated variances. The code has been used primarily in performance assessment of materials' accounting systems. This report provides the necessary information for a potential user to employ the code in these applications. A number of examples that demonstrate most of the capabilities of the code are provided

  19. Renewable Electric Plant Information System user interface manual: Paradox 7 Runtime for Windows

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-11-01

    The Renewable Electric Plant Information System (REPiS) is a comprehensive database with detailed information on grid-connected renewable electric plants in the US. The current version, REPiS3 beta, was developed in Paradox for Windows. The user interface (UI) was developed to facilitate easy access to information in the database, without the need to have, or know how to use, Paradox for Windows. The UI is designed to provide quick responses to commonly requested sorts of the database. A quick perusal of this manual will familiarize one with the functions of the UI and will make use of the system easier. There are six parts to this manual: (1) Quick Start: Instructions for Users Familiar with Database Applications; (2) Getting Started: The Installation Process; (3) Choosing the Appropriate Report; (4) Using the User Interface; (5) Troubleshooting; (6) Appendices A and B.

  20. TMAP4 User's Manual

    Energy Technology Data Exchange (ETDEWEB)

    Longhurst, G.R.; Holland, D.F.; Jones, J.L.; Merrill, B.J.

    1992-06-12

    The Tritium Migration Analysis Program, Version 4 (TMAP4) has been developed by the Fusion Safety Program at the Idaho National Engineering Laboratory (INEL) as a safety analysis code, mainly to analyze tritium retention and loss in fusion reactor structures and systems during normal operation and accident conditions. TMAP4 incorporates one-dimensional thermal- and mass-diffusive transport and trapping calculations through structures and zero dimensional fluid transport between enclosures and across the interface between enclosures and structures. A key feature is the ability to input problem definition parameters as constants, interpolation tables, or FORTRAN equations. The code is specifically intended for use under a DOS operating system on PC-type mini-computers, but it has also been run successfully on workstations and mainframe computer systems. Use of the equation-input feature requires access to a FORTRAN-77 compiler and a linker program.

  1. A-THREE: a user's manual

    International Nuclear Information System (INIS)

    Auerbach, E.H.

    1977-06-01

    A-THREE is an optical-model code for elastic scattering, specifically designed for the requirements of heavy-ion projectiles. Fast search procedures for fitting model parameters to experimental data are provided. Because of structural similarity, provision for bound-state calculation is also included. In a sense, this code is ''grandson of ABACUS-2;'' it has, however, been written completely anew. Principal features include the ability to calculate to high partial waves (up to l = 800), refinement of integration meshes for large wave number, and a variety of forms for the optical potentials. The very superior Manchester Coulomb Wave Functions Routine, good in all parts of the (rho, eta) plane is used. This code, written in Fortran-extended, has been in use at Brookhaven on its CDC-7600 for the last two years, during which a number of minor improvements have been added. A general overview of the principal features of the code is given first, with some recommendations for input. This overview is intended to guide the user, and is not intended as a detailed description of the code. Then follow sections describing the input cards and the output generated by the code. These sections are sufficiently detailed to permit a user to prepare input without reference to a code listing. Finally, material necessary for writing special potential well subroutines and tables of control and parameter numbers are appended

  2. The users manual and concepts of nuclear materials accounting system

    International Nuclear Information System (INIS)

    Lee, Byung Du; Jeon, In

    1996-03-01

    This report is to describe the concepts, operation status and user's manuals of nuclear materials accounting system which was developed to not only make out, report and manage the IAEA accounting reports but also maintain the accounting information. Therefore, facility operator could effectively make use of the accounting system without a special training by using this report. 3 tabs., 15 figs., (Author) .new

  3. National Radiobiology Archives Distributed Access user's manual

    Energy Technology Data Exchange (ETDEWEB)

    Watson, C.; Smith, S. (Pacific Northwest Lab., Richland, WA (United States)); Prather, J. (Linfield Coll., McMinnville, OR (United States))

    1991-11-01

    This User's Manual describes installation and use of the National Radiobiology Archives (NRA) Distributed Access package. The package consists of a distributed subset of information representative of the NRA databases and database access software which provide an introduction to the scope and style of the NRA Information Systems.

  4. ARES: automated response function code. Users manual. [HPGAM and LSQVM

    Energy Technology Data Exchange (ETDEWEB)

    Maung, T.; Reynolds, G.M.

    1981-06-01

    This ARES user's manual provides detailed instructions for a general understanding of the Automated Response Function Code and gives step by step instructions for using the complete code package on a HP-1000 system. This code is designed to calculate response functions of NaI gamma-ray detectors, with cylindrical or rectangular geometries.

  5. User's Manual. Vocational Education Readiness Test (VERT). Revised Edition.

    Science.gov (United States)

    Thomas, Edward L.; And Others

    This user's manual provides information suggesting various ways in which educational personnel may wish to utilize the eight modules included in the Vocational Education Readiness Test (VERT). The introductory section presents questions which can be used by school personnel to determine whether or not VERT will be useful in their school system.…

  6. HANSF 1.3 user's manual

    Energy Technology Data Exchange (ETDEWEB)

    PLYS, M.G.

    1999-05-21

    The HANSF analysis tool is an integrated model considering phenomena inside a multi-canister overpack (MCO) spent nuclear fuel container such as fuel oxidation, convective and radiative heat transfer, and the potential for fission product release. It may be used for all phases of spent fuel disposition including cold vacuum drying, transportation, and storage. This manual reflects HANSF version 1.3, a revised version of version 1.2a. HANSF 1.3 was written to add new models for axial nodalization, add new features for ease of usage, and correct errors. HANSF 1.3 is intended for use on personal computers such as IBM-compatible machines with Intel processors running under a DOS-type operating system. HANSF 1.3 is known to compile under Lahey TI and Digital Visual FORTRAN, Version 6.0, but this does not preclude operation in other environments.

  7. The Image of User Instructions: Comparing Users' Expectations of and Experiences with an Official and a Commercial Software Manual

    NARCIS (Netherlands)

    de Jong, Menno D.T.; Karreman, Joyce

    2017-01-01

    Purpose: The market for (paid-for) commercial software manuals is flourishing, while (free) official manuals are often assumed to be neglected by users. To investigate differences in user perceptions of commercial and official manuals, we conducted two studies: one focusing on user expectations and

  8. Radiological Safety Analysis Computer (RSAC) Program Version 7.0 Users’ Manual

    Energy Technology Data Exchange (ETDEWEB)

    Dr. Bradley J Schrader

    2009-03-01

    The Radiological Safety Analysis Computer (RSAC) Program Version 7.0 (RSAC-7) is the newest version of the RSAC legacy code. It calculates the consequences of a release of radionuclides to the atmosphere. A user can generate a fission product inventory from either reactor operating history or a nuclear criticality event. RSAC-7 models the effects of high-efficiency particulate air filters or other cleanup systems and calculates the decay and ingrowth during transport through processes, facilities, and the environment. Doses are calculated for inhalation, air immersion, ground surface, ingestion, and cloud gamma pathways. RSAC-7 can be used as a tool to evaluate accident conditions in emergency response scenarios, radiological sabotage events and to evaluate safety basis accident consequences. This users’ manual contains the mathematical models and operating instructions for RSAC-7. Instructions, screens, and examples are provided to guide the user through the functions provided by RSAC-7. This program was designed for users who are familiar with radiological dose assessment methods.

  9. Radiological Safety Analysis Computer (RSAC) Program Version 7.2 Users’ Manual

    Energy Technology Data Exchange (ETDEWEB)

    Dr. Bradley J Schrader

    2010-10-01

    The Radiological Safety Analysis Computer (RSAC) Program Version 7.2 (RSAC-7) is the newest version of the RSAC legacy code. It calculates the consequences of a release of radionuclides to the atmosphere. A user can generate a fission product inventory from either reactor operating history or a nuclear criticality event. RSAC-7 models the effects of high-efficiency particulate air filters or other cleanup systems and calculates the decay and ingrowth during transport through processes, facilities, and the environment. Doses are calculated for inhalation, air immersion, ground surface, ingestion, and cloud gamma pathways. RSAC-7 can be used as a tool to evaluate accident conditions in emergency response scenarios, radiological sabotage events and to evaluate safety basis accident consequences. This users’ manual contains the mathematical models and operating instructions for RSAC-7. Instructions, screens, and examples are provided to guide the user through the functions provided by RSAC-7. This program was designed for users who are familiar with radiological dose assessment methods.

  10. Element Load Data Processor (ELDAP) Users Manual

    Science.gov (United States)

    Ramsey, John K., Jr.; Ramsey, John K., Sr.

    2015-01-01

    Often, the shear and tensile forces and moments are extracted from finite element analyses to be used in off-line calculations for evaluating the integrity of structural connections involving bolts, rivets, and welds. Usually the maximum forces and moments are desired for use in the calculations. In situations where there are numerous structural connections of interest for numerous load cases, the effort in finding the true maximum force and/or moment combinations among all fasteners and welds and load cases becomes difficult. The Element Load Data Processor (ELDAP) software described herein makes this effort manageable. This software eliminates the possibility of overlooking the worst-case forces and moments that could result in erroneous positive margins of safety and/or selecting inconsistent combinations of forces and moments resulting in false negative margins of safety. In addition to forces and moments, any scalar quantity output in a PATRAN report file may be evaluated with this software. This software was originally written to fill an urgent need during the structural analysis of the Ares I-X Interstage segment. As such, this software was coded in a straightforward manner with no effort made to optimize or minimize code or to develop a graphical user interface.

  11. EPRI fuel performance data base: user's manual. Final report

    International Nuclear Information System (INIS)

    Simpson, J.; Lee, S.; Rumble, E.

    1980-10-01

    This user's manual provides instructions for accessing the data in the EPRI fuel performance data base (FPDB) and manipulating that data to solve specific problems that the user wishes to specify. The user interacts with the FPDB through the Relational Information Management System (RIMS) computer program. The structure and format of the FPDB and the general syntax of the data base commands are described. Instructions follow for the use of each command. Appendixes provide more detailed information about the FPDB and its software. The FPDB currently resides on a PRIME-750 computer

  12. Miro V3.0: user guide and reference manual

    International Nuclear Information System (INIS)

    Donnat, Ph.; Treimany, C.; Morice, O.; Ribeyre, X.

    1998-06-01

    This paper contains the user's guide and reference manual of Miro software. This software is used for simulating propagation and amplification of laser beams in laser devices as Megajoules or NIF. The physical effects taken into account ar essentially: saturated amplification, absorption, Kerr effect, birefringence and aberrations. The models of propagation are either geometrical optics of parallel beams, or Fresnel diffraction. A graphic user interface as been included to allow interactive management of optical devices and results. A Unix environment with X-Window and Motif is required to run Miro. The user's guide gives a short insight of the software. The reference manual details the physical models and the way they are implanted in Miro. (author)

  13. European correlation counter (ECC) VER. 1.0 users manual

    International Nuclear Information System (INIS)

    Vocino, V.

    1989-01-01

    The users manual is conceived for the utilization of personal computers linked to a shift register for the assay of Pu containing fuel. It is based on an MS DOS system and permits the users to store calibration curves, constants, measurement and assay data on floppy disks for ulterior utilisation. The interpretation models use the latest theories of neutron multiplication and dead time effects. The inspector is guided by the screen display step by step from the instrument test via calibration to the assay and data storage. All test, calibration and assay data can be printed out on paper tape and serve to the inspector to prepare the respective inspection report. The users are invited to make suggestions to the authors, such that the manual's use can be adapted to further requirements

  14. User's manual for computer program BASEPLOT

    Science.gov (United States)

    Sanders, Curtis L.

    2002-01-01

    The checking and reviewing of daily records of streamflow within the U.S. Geological Survey is traditionally accomplished by hand-plotting and mentally collating tables of data. The process is time consuming, difficult to standardize, and subject to errors in computation, data entry, and logic. In addition, the presentation of flow data on the internet requires more timely and accurate computation of daily flow records. BASEPLOT was developed for checking and review of primary streamflow records within the U.S. Geological Survey. Use of BASEPLOT enables users to (1) provide efficiencies during the record checking and review process, (2) improve quality control, (3) achieve uniformity of checking and review techniques of simple stage-discharge relations, and (4) provide a tool for teaching streamflow computation techniques. The BASEPLOT program produces tables of quality control checks and produces plots of rating curves and discharge measurements; variable shift (V-shift) diagrams; and V-shifts converted to stage-discharge plots, using data stored in the U.S. Geological Survey Automatic Data Processing System database. In addition, the program plots unit-value hydrographs that show unit-value stages, shifts, and datum corrections; input shifts, datum corrections, and effective dates; discharge measurements; effective dates for rating tables; and numeric quality control checks. Checklist/tutorial forms are provided for reviewers to ensure completeness of review and standardize the review process. The program was written for the U.S. Geological Survey SUN computer using the Statistical Analysis System (SAS) software produced by SAS Institute, Incorporated.

  15. Data acquisition for X ray microprobe. User's manual

    International Nuclear Information System (INIS)

    2002-01-01

    A modified data acquisition software for X ray microprobe was developed by the Physics Group, Instrumentation Unit, IAEA Laboratories at Seibersdorf, with assistance from M. Bogovac, Croatia. The software consists of data acquisition (scanning and calibration), automatic positioning and micro-movement of sample, data reduction and evaluation. The acquisition software was designed in order to support different measurement set-ups which are applied in low-energy nuclear physics. The modification was done in 1999-2000 under the projects Nuclear Spectrometry and Utilization of Particle Accelerators. The manual supersedes the first version entitled Microanalysis Data Acquisition and Control Program published under Computer Manual Series, No. 9 in 1996. The software described in this manual is freely available from the IAEA upon request

  16. COSIS User's Manual

    Energy Technology Data Exchange (ETDEWEB)

    Cho, J. Y.; Lee, K. B.; Koo, B. S.; Lee, W. K.; Lee, C. C.; Zee, S. Q

    2006-02-15

    COSIS (COre State Indication System) which implemented in the SMART research reactor plays a role to supply the core state parameters or graphs for the operator to recognize the core state effectively. The followings are the main functions of COSIS. Validity Check for the Process Signals and Determination of the COSIS Inputs (SIGVAL), Coolant Flow Rate Calculation (FLOW), Core Thermal Power Calculation (COREPOW), In-core 3-Dimensional Power Distribution Calculation and Peaking Parameters Generation (POWER3D), Azimuthal Tilt Calculation (AZITILT). This report describes the structures of the I/O files that are essential for the users to run COSIS. COSIS handles the following 4 input files. DATABASE: The base input file, COSIS.INP: The signal input file, CCS.DAT: File required for the in-core detector signal processing and the 3-D power distribution calculation, TPFH2O: Steam table for the water properties The DATABASE file contains the base information for a nuclear power plant and is read at the first COSIS calculation. The COSIS.INP file contains the process input and detector signals, and is read by COSIS at every second. CCS.DAT file, that is produced by the COSISMAS code, contains the information for the in-core detector signal processing and the 3-D power distribution calculation. TPFH2O file is a steam table and is written in binary format. COSIS produces the following 4 output files. DATABASE.OUT: The output file for the DATABASE input file, COSIS.OUT: The normal output file produced after the COSIS calculation, COSIS.SUM: File for the operator to recognize the core state effectively, MAS{sub S}IG: File to run the COSISMAS code The DATABASE.OUT file is produced right after finishing DATABASE processing. The COSIS.OUT file is produced after finishing the input signal processing and the main COSIS calculation. The COSIS.SUM file is the summary file of the COSIS results for the operator to recognize the core state effectively. The MAS{sub S}IG file is the

  17. Software Users Manual (SUM): Extended Testability Analysis (ETA) Tool

    Science.gov (United States)

    Maul, William A.; Fulton, Christopher E.

    2011-01-01

    This software user manual describes the implementation and use the Extended Testability Analysis (ETA) Tool. The ETA Tool is a software program that augments the analysis and reporting capabilities of a commercial-off-the-shelf (COTS) testability analysis software package called the Testability Engineering And Maintenance System (TEAMS) Designer. An initial diagnostic assessment is performed by the TEAMS Designer software using a qualitative, directed-graph model of the system being analyzed. The ETA Tool utilizes system design information captured within the diagnostic model and testability analysis output from the TEAMS Designer software to create a series of six reports for various system engineering needs. The ETA Tool allows the user to perform additional studies on the testability analysis results by determining the detection sensitivity to the loss of certain sensors or tests. The ETA Tool was developed to support design and development of the NASA Ares I Crew Launch Vehicle. The diagnostic analysis provided by the ETA Tool was proven to be valuable system engineering output that provided consistency in the verification of system engineering requirements. This software user manual provides a description of each output report generated by the ETA Tool. The manual also describes the example diagnostic model and supporting documentation - also provided with the ETA Tool software release package - that were used to generate the reports presented in the manual

  18. The Radiological Safety Analysis Computer Program (RSAC-5) user's manual

    International Nuclear Information System (INIS)

    Wenzel, D.R.

    1994-02-01

    The Radiological Safety Analysis Computer Program (RSAC-5) calculates the consequences of the release of radionuclides to the atmosphere. Using a personal computer, a user can generate a fission product inventory from either reactor operating history or nuclear criticalities. RSAC-5 models the effects of high-efficiency particulate air filters or other cleanup systems and calculates decay and ingrowth during transport through processes, facilities, and the environment. Doses are calculated through the inhalation, immersion, ground surface, and ingestion pathways. RSAC+, a menu-driven companion program to RSAC-5, assists users in creating and running RSAC-5 input files. This user's manual contains the mathematical models and operating instructions for RSAC-5 and RSAC+. Instructions, screens, and examples are provided to guide the user through the functions provided by RSAC-5 and RSAC+. These programs are designed for users who are familiar with radiological dose assessment methods

  19. Automated Transportation Management System (ATMS) user's manual. Revision 1

    International Nuclear Information System (INIS)

    Smith, P.D.

    1994-01-01

    The Automated Transportation Management System (ATMS) Software User Guide (SUG) constitutes the user procedures for the ATMS System. Information in this document will be used by the user to operate the automated system. It is intended to be used as a reference manual to guide and direct the user(s) through the ATMS software product and its environment. The objectives of ATMS are as follows: to better support the Procurement function with freight rate information; to free Transportation Logistics personnel from routine activities such as the auditing and input of freight billing information; to comply with Headquarters Department of Energy-Inspector General (DOE-IG) audit findings to automate transportation management functions; to reduce the keying of data into the Shipment Mobility Accountability Collection (SMAC) database; and to provide automation for the preparing of Bill of Lading, Declaration of Dangerous Goods, Emergency Response Guide and shipping Labels using HM181 Retrieval of hazardous material table text information

  20. Computer-Aided System Engineering and Analysis (CASE/A) Programmer's Manual, Version 5.0

    Science.gov (United States)

    Knox, J. C.

    1996-01-01

    The Computer Aided System Engineering and Analysis (CASE/A) Version 5.0 Programmer's Manual provides the programmer and user with information regarding the internal structure of the CASE/A 5.0 software system. CASE/A 5.0 is a trade study tool that provides modeling/simulation capabilities for analyzing environmental control and life support systems and active thermal control systems. CASE/A has been successfully used in studies such as the evaluation of carbon dioxide removal in the space station. CASE/A modeling provides a graphical and command-driven interface for the user. This interface allows the user to construct a model by placing equipment components in a graphical layout of the system hardware, then connect the components via flow streams and define their operating parameters. Once the equipment is placed, the simulation time and other control parameters can be set to run the simulation based on the model constructed. After completion of the simulation, graphical plots or text files can be obtained for evaluation of the simulation results over time. Additionally, users have the capability to control the simulation and extract information at various times in the simulation (e.g., control equipment operating parameters over the simulation time or extract plot data) by using "User Operations (OPS) Code." This OPS code is written in FORTRAN with a canned set of utility subroutines for performing common tasks. CASE/A version 5.0 software runs under the VAX VMS(Trademark) environment. It utilizes the Tektronics 4014(Trademark) graphics display system and the VTIOO(Trademark) text manipulation/display system.

  1. Users manual for CAFE-3D : a computational fluid dynamics fire code

    International Nuclear Information System (INIS)

    Khalil, Imane; Lopez, Carlos; Suo-Anttila, Ahti Jorma

    2005-01-01

    The Container Analysis Fire Environment (CAFE) computer code has been developed to model all relevant fire physics for predicting the thermal response of massive objects engulfed in large fires. It provides realistic fire thermal boundary conditions for use in design of radioactive material packages and in risk-based transportation studies. The CAFE code can be coupled to commercial finite-element codes such as MSC PATRAN/THERMAL and ANSYS. This coupled system of codes can be used to determine the internal thermal response of finite element models of packages to a range of fire environments. This document is a user manual describing how to use the three-dimensional version of CAFE, as well as a description of CAFE input and output parameters. Since this is a user manual, only a brief theoretical description of the equations and physical models is included

  2. Solar Advisor Model User Guide for Version 2.0

    Energy Technology Data Exchange (ETDEWEB)

    Gilman, P.; Blair, N.; Mehos, M.; Christensen, C.; Janzou, S.; Cameron, C.

    2008-08-01

    The Solar Advisor Model (SAM) provides a consistent framework for analyzing and comparing power system costs and performance across the range of solar technologies and markets, from photovoltaic systems for residential and commercial markets to concentrating solar power and large photovoltaic systems for utility markets. This manual describes Version 2.0 of the software, which can model photovoltaic and concentrating solar power technologies for electric applications for several markets. The current version of the Solar Advisor Model does not model solar heating and lighting technologies.

  3. User's Manual for the Object User Interface (OUI): An Environmental Resource Modeling Framework

    Science.gov (United States)

    Markstrom, Steven L.; Koczot, Kathryn M.

    2008-01-01

    The Object User Interface is a computer application that provides a framework for coupling environmental-resource models and for managing associated temporal and spatial data. The Object User Interface is designed to be easily extensible to incorporate models and data interfaces defined by the user. Additionally, the Object User Interface is highly configurable through the use of a user-modifiable, text-based control file that is written in the eXtensible Markup Language. The Object User Interface user's manual provides (1) installation instructions, (2) an overview of the graphical user interface, (3) a description of the software tools, (4) a project example, and (5) specifications for user configuration and extension.

  4. TRIPOLI-4R Version 8 User Guide

    International Nuclear Information System (INIS)

    Brun, Emeric; Damian, Frederic; Dumonteil, Eric; Hugot, Francois-Xavier; Lee, Yi-Kang; Malvagi, Fausto; Mazzolo, Alain; Petit, Odile; Trama, Jean-Christophe; Visonneau, Thierry; Zoia, Andrea

    2013-02-01

    TRIPOLI-4 R solves the linear Boltzmann equation for neutrons, photons, electrons and positrons, with the Monte Carlo method, in any 3D geometry. The code uses ENDF format continuous energy cross-sections, from various international evaluations including JEFF-3.1.1, ENDF/B-VII.0, JENDL4 and FENDL2.1. Its official nuclear data library for applications, named CEAV5.1.1, is mainly based on the European evaluation JEFF-3.1.1. TRIPOLI-4 R solves fixed source as well as eigenvalue problems. It has advanced variance reduction methods to address deep penetration issues. Thanks to its robust and efficient parallelism capability, calculations are easily performed on multi-core single units, heterogeneous networks of workstations and massively parallel machines. Additional productivity tools, graphical as well as algorithmic, allow the user to efficiently set its input decks. With its large V and V data base, TRIPOLI-4 R is used as a reference code for industrial purposes, as well as a R and D and teaching tool, for radiation protection and shielding, core physics, nuclear criticality-safety and nuclear instrumentation. TRIPOLI-4 R is a registered trademark of CEA. (authors)

  5. Tripoli-4 version 4 user guide

    International Nuclear Information System (INIS)

    Petit, O.; Hugot, F.X.; Lee, Y.K.; Jouanne, C.; Mazzolo, A.

    2008-01-01

    TRIPOLI-4 is a general purpose radiation transport code. It uses the Monte Carlo method to simulate neutron and photon behaviour in three-dimensional geometries. The main areas of applications include but are not restricted to: radiation protection and shielding, nuclear criticality safety, fission and fusion reactor design, nuclear instrumentation. Any pointwise cross-section data in ENDF/B format may be used: JEF2, ENDF/B-VI, JEFF3, ENDF/B-VII, JENDL3.3 etc. As for thermal neutrons, both free gas and S(alpha, beta) models are available. Easy-to-use powerful variance-reduction tools help the user to solve deep penetration problems. TRIPOLI-4 features a versatile and robust parallel operation mode, for heterogeneous network of workstations, or massively parallel machines. TRIPOLI-4 is supported by a range of graphics and algorithmic productivity tools which means that checking for geometry and input deck errors is easy. As for the qualification, TRIPOLI-4 benefits from an extensive range of benchmarks and comparisons with real measurements, and is therefore qualified for R and D, teaching as well as industrial use. (authors)

  6. A deterministic-probabilistic model for contaminant transport. User manual

    Energy Technology Data Exchange (ETDEWEB)

    Schwartz, F W; Crowe, A

    1980-08-01

    This manual describes a deterministic-probabilistic contaminant transport (DPCT) computer model designed to simulate mass transfer by ground-water movement in a vertical section of the earth's crust. The model can account for convection, dispersion, radioactive decay, and cation exchange for a single component. A velocity is calculated from the convective transport of the ground water for each reference particle in the modeled region; dispersion is accounted for in the particle motion by adding a readorn component to the deterministic motion. The model is sufficiently general to enable the user to specify virtually any type of water table or geologic configuration, and a variety of boundary conditions. A major emphasis in the model development has been placed on making the model simple to use, and information provided in the User Manual will permit changes to the computer code to be made relatively easily for those that might be required for specific applications. (author)

  7. Climate change scenarios for Canada's national parks : a users manual

    International Nuclear Information System (INIS)

    Jones, B.; Wun, N.; Scott, D.; Barrow, E.

    2003-01-01

    A screening level impact assessment has shown that the implications of climate change for Canada's national parks are considerable. Climate change scenarios will be an important component in examining the potential climate change impacts and the implications of adaptation strategies. Most climate change scenarios are based on vulnerability, impact and adaptation research. This user's manual describes the development of 3 types of climate change scenarios including scenarios from global climate models (GCMs), bioclimate scenarios and daily scenarios for use by Parks Canada. The manual offers advice to first-time climate change scenario users in choosing and interpreting climate change, bioclimate and daily scenarios. It also addresses the theoretical and practical foundations of each climate scenario and shows how to access data regarding the various scenarios. Hands-on exercises are included as an interpretive aid. 20 refs., 4 tabs., 19 figs

  8. Real-Time Multiprocessor Programming Language (RTMPL) user's manual

    Science.gov (United States)

    Arpasi, D. J.

    1985-01-01

    A real-time multiprocessor programming language (RTMPL) has been developed to provide for high-order programming of real-time simulations on systems of distributed computers. RTMPL is a structured, engineering-oriented language. The RTMPL utility supports a variety of multiprocessor configurations and types by generating assembly language programs according to user-specified targeting information. Many programming functions are assumed by the utility (e.g., data transfer and scaling) to reduce the programming chore. This manual describes RTMPL from a user's viewpoint. Source generation, applications, utility operation, and utility output are detailed. An example simulation is generated to illustrate many RTMPL features.

  9. User's Manual for FEM-BEM Method. 1.0

    Science.gov (United States)

    Butler, Theresa; Deshpande, M. D. (Technical Monitor)

    2002-01-01

    A user's manual for using FORTRAN code to perform electromagnetic analysis of arbitrarily shaped material cylinders using a hybrid method that combines the finite element method (FEM) and the boundary element method (BEM). In this method, the material cylinder is enclosed by a fictitious boundary and the Maxwell's equations are solved by FEM inside the boundary and by BEM outside the boundary. The electromagnetic scattering on several arbitrarily shaped material cylinders using this FORTRAN code is computed to as examples.

  10. User's manual for elegant Program Version 12.4, Manual Version 1

    International Nuclear Information System (INIS)

    Borland, M.

    1993-01-01

    Elegant stands for ''Electron Generation and Tracking,'' a somewhat out-of-date description of a fully 6D accelerator program that now does much more than generate particle distributions and track them elegant, written entirely in the C programming language, uses a variant of the MAD input format to describe accelerators, which may be either transport lines, circular machines, or a combination thereof. Program execution is driven by commands in a namelist format. This document describes the features available in elegant, listing the commands and their arguments. The differences between elegant and MAD formats for describing accelerators are listed. A series of examples of elegant input and output are given. Finally, appendices are included describing the post-processing programs

  11. 75 FR 52976 - Issuance of Revised Users' Manual for Commission Mediation Program for Investigations Under...

    Science.gov (United States)

    2010-08-30

    ... INTERNATIONAL TRADE COMMISSION Issuance of Revised Users' Manual for Commission Mediation Program... 65615 (Nov. 8, 2008). The Commission has determined to issue a revised Users' Manual for its program for the mediation of investigations under section 337 of the Tariff Act of 1930. The revised Users' Manual...

  12. User Manual for SAHM package for VisTrails

    Science.gov (United States)

    Talbert, C.B.; Talbert, M.K.

    2012-01-01

    The Software for Assisted Habitat I\\•1odeling (SAHM) has been created to both expedite habitat modeling and help maintain a record of the various input data, pre-and post-processing steps and modeling options incorporated in the construction of a species distribution model. The four main advantages to using the combined VisTrail: SAHM package for species distribution modeling are: 1. formalization and tractable recording of the entire modeling process 2. easier collaboration through a common modeling framework 3. a user-friendly graphical interface to manage file input, model runs, and output 4. extensibility to incorporate future and additional modeling routines and tools. This user manual provides detailed information on each module within the SAHM package, their input, output, common connections, optional arguments, and default settings. This information can also be accessed for individual modules by right clicking on the documentation button for any module in VisTrail or by right clicking on any input or output for a module and selecting view documentation. This user manual is intended to accompany the user guide which provides detailed instructions on how to install the SAHM package within VisTrails and then presents information on the use of the package.

  13. The Montana Rivers Information System: Edit/entry program user`s manual

    Energy Technology Data Exchange (ETDEWEB)

    1992-07-01

    The Montana Rivers Information System (MRIS) was initiated to assess the state`s fish, wildlife, and recreation value; and natural cultural and geologic features. The MRIS is now a set of data bases containing part of the information in the Natural Heritage Program natural features and threatened and endangered species data bases. The purpose of this User`s Manual is to: (1) describe to the user how to maintain the MRIS database of their choice by updating, changing, deleting, and adding records using the edit/entry programs; and (2) provide to the user all information and instructions necessary to complete data entry into the MRIS databases.

  14. ENDF-6 formats manual. Version of Oct. 1991

    International Nuclear Information System (INIS)

    Rose, P.F.; Dunford, C.L.

    1992-01-01

    ENDF-6 is the international computer file format for evaluated nuclear data. In contrast to the earlier versions (ENDF-4 and ENDF-5) the new version ENDF-6 has been designed not only for neutron reaction data but also for photo-nuclear and charged-particle nuclear reaction data. This document gives a detailed description of the formats and procedures adopted for ENDF-6. The present version includes update pages dated Oct. 1991. (author). Refs, figs, and tabs

  15. User manual of FUNF code for fissile material data calculation

    International Nuclear Information System (INIS)

    Zhang, Jingshang

    2006-03-01

    The FUNF code (2005 version) is used to calculate fast neutron reaction data of fissile materials with incident energies from about 1 keV up to 20 MeV. The first version of the FUNF code was completed in 1994. the code has been developed continually since that time and has often been used as an evaluation tool for setting up CENDL and for analyzing the measurements of fissile materials. During these years many improvements have been made. In this manual, the format of the input parameter files and the output files, as well as the functions of flag used in FUNF code, are introduced in detail, and the examples of the format of input parameters files are given. FUNF code consists of the spherical optical model, the Hauser-Feshbach model, and the unified Hauser-Feshbach and exciton model. (authors)

  16. User manual for version 4.3 of the Tripoli-4 Monte-Carlo method particle transport computer code; Notice d'utilisation du code Tripoli-4, version 4.3: code de transport de particules par la methode de Monte Carlo

    Energy Technology Data Exchange (ETDEWEB)

    Both, J.P.; Mazzolo, A.; Peneliau, Y.; Petit, O.; Roesslinger, B

    2003-07-01

    This manual relates to Version 4.3 TRIPOLI-4 code. TRIPOLI-4 is a computer code simulating the transport of neutrons, photons, electrons and positrons. It can be used for radiation shielding calculations (long-distance propagation with flux attenuation in non-multiplying media) and neutronic calculations (fissile medium, criticality or sub-criticality basis). This makes it possible to calculate k{sub eff} (for criticality), flux, currents, reaction rates and multi-group cross-sections. TRIPOLI-4 is a three-dimensional code that uses the Monte-Carlo method. It allows for point-wise description in terms of energy of cross-sections and multi-group homogenized cross-sections and features two modes of geometrical representation: surface and combinatorial. The code uses cross-section libraries in ENDF/B format (such as JEF2-2, ENDF/B-VI and JENDL) for point-wise description cross-sections in APOTRIM format (from the APOLLO2 code) or a format specific to TRIPOLI-4 for multi-group description. (authors)

  17. Social values for ecosystem services (SolVES): A GIS application for assessing, mapping, and quantifying the social values of ecosystem services-Documentation and user manual, version 1.0

    Science.gov (United States)

    Sherrouse, Benson C.; Riegle, Jodi L.; Semmens, Darius J.

    2010-01-01

    In response to the need for incorporating quantified and spatially explicit measures of social values into ecosystem services assessments, the Rocky Mountain Geographic Science Center, in collaboration with Colorado State University, has developed a geographic information system application, Social Values for Ecosystem Services (SolVES). SolVES can be used to assess, map, and quantify the perceived social values of ecosystem services. SolVES derives a quantitative social values metric, the Value Index, from a combination of spatial and nonspatial responses to public attitude and preference surveys. SolVES also generates landscape metrics, such as average elevation and distance to water, calculated from spatial data layers describing the underlying physical environment. Using kernel density calculations and zonal statistics, SolVES derives and maps the 10-point Value Index and reports landscape metrics associated with each index value for social value types such as aesthetics, biodiversity, and recreation. This can be repeated for various survey subgroups as distinguished by their attitudes and preferences regarding public uses of the forests such as motorized recreation and logging for fuels reduction. The Value Index provides a basis of comparison within and among survey subgroups to consider the effect of social contexts on the valuation of ecosystem services. SolVES includes regression coefficients linking the predicted value (the Value Index) to landscape metrics. These coefficients are used to generate predicted social value maps using value transfer techniques for areas where primary survey data are not available. SolVES was developed, and will continue to be enhanced through future versions, as a public domain tool to enable decision makers and researchers to map the social values of ecosystem services and to facilitate discussions among diverse stakeholders regarding tradeoffs between different ecosystem services in a variety of physical and social contexts.

  18. HTGR Application Economic Model Users' Manual

    Energy Technology Data Exchange (ETDEWEB)

    A.M. Gandrik

    2012-01-01

    The High Temperature Gas-Cooled Reactor (HTGR) Application Economic Model was developed at the Idaho National Laboratory for the Next Generation Nuclear Plant Project. The HTGR Application Economic Model calculates either the required selling price of power and/or heat for a given internal rate of return (IRR) or the IRR for power and/or heat being sold at the market price. The user can generate these economic results for a range of reactor outlet temperatures; with and without power cycles, including either a Brayton or Rankine cycle; for the demonstration plant, first of a kind, or nth of a kind project phases; for up to 16 reactor modules; and for module ratings of 200, 350, or 600 MWt. This users manual contains the mathematical models and operating instructions for the HTGR Application Economic Model. Instructions, screenshots, and examples are provided to guide the user through the HTGR Application Economic Model. This model was designed for users who are familiar with the HTGR design and Excel and engineering economics. Modification of the HTGR Application Economic Model should only be performed by users familiar with the HTGR and its applications, Excel, and Visual Basic.

  19. Comparative ergonomic assessment of manual wheelchairs by paraplegic users.

    Science.gov (United States)

    Gil-Agudo, Angel; Solís-Mozos, Marta; del-Ama, Antonio J; Crespo-Ruiz, Beatriz; de la Peña-González, Ana Isabel; Pérez-Nombela, Soraya

    2013-07-01

    The aim of the present study was to describe and test the reliability of a comprehensive product-centered approach to assessing functional performance and wheelchair user perceptions on device ergonomics and satisfaction of performance. A pilot study was implemented using this approach to evaluate differences among four manual wheelchairs. Six wheelchair users with complete spinal cord injury (SCI) at the thoracic level and with no previous upper limbs impairment were recruited for this study. After finishing circuit tasks, subjects were asked to complete a questionnaire about ergonomic wheelchair characteristics (manoeuvrability, stability, comfort and ease of propulsion) and satisfaction about task performance. On the other hand, objective data were recorded during user performance as the time required to complete each test, kinetic wheelchair propulsion data obtained with two SMARTWheels® and physiological parameters (heart rate and physiological index). Kuschall Champion® and Otto Bock Voyage® wheelchairs were ranked best for most ergonomic aspects specially in manoeuvrability (p importance of looking both kinds of information, user perception and user functional performance when evaluating a wheelchair or comparing across devices.

  20. KAFEPA-II program users' manual and description

    International Nuclear Information System (INIS)

    Suk, H. C.; Hwang, W.; Kim, B. G.; Sim, K. S.; Heo, Y. H.; Byun, T. S.; Park, G. S.

    1992-04-01

    KAFEPA-II is a computer program for simulating the behaviour of UO 2 fuel elements under normal operating conditions of a CANDU reactor. It computes the one-dimensional temperature distribution and thermal expansion of the fuel pellets. The amount of gas released during irradiation of the fuel is also computed. Thermal expansion and gas pressure inside the fuel element are then used to compute the strains and stresses in the sheath. This document is intended as a user's manual and description for KAFEPA-II. (Author)

  1. The development of nuclear material accountability system - software user's manual

    International Nuclear Information System (INIS)

    Byeon, Kee Hoh; Kim, Ho Dong; Song, Dae Yong; Ko, Won Il; Hong, Jong Sook; Lee, Byung Doo

    1999-07-01

    We have developed the near-real time nuclear material accountability system, named by DMAS, for DUPIC Test Facility in the basis of the survey of DUPIC process and activities for the accountability of the system, and the review of the rules and regulations related to the nuclear material accounting. Our system adopts the structure and technologies used in COREMAS which was developed by LANL. This technical report illustrates the system structure and program usage as a user manual for DMAS. (author). 56 tabs., 1 fig

  2. Synfuel program analysis. Volume 2: VENVAL users manual

    Science.gov (United States)

    Muddiman, J. B.; Whelan, J. W.

    1980-07-01

    This volume is intended for program analysts and is a users manual for the VENVAL model. It contains specific explanations as to input data requirements and programming procedures for the use of this model. VENVAL is a generalized computer program to aid in evaluation of prospective private sector production ventures. The program can project interrelated values of installed capacity, production, sales revenue, operating costs, depreciation, investment, dent, earnings, taxes, return on investment, depletion, and cash flow measures. It can also compute related public sector and other external costs and revenues if unit costs are furnished.

  3. User's manual for the two-dimensional transputer graphics toolkit

    Science.gov (United States)

    Ellis, Graham K.

    1988-01-01

    The user manual for the 2-D graphics toolkit for a transputer based parallel processor is presented. The toolkit consists of a package of 2-D display routines that can be used for the simulation visualizations. It supports multiple windows, double buffered screens for animations, and simple graphics transformations such as translation, rotation, and scaling. The display routines are written in occam to take advantage of the multiprocessing features available on transputers. The package is designed to run on a transputer separate from the graphics board.

  4. DarcyTools, Version 2.1. User's guide

    International Nuclear Information System (INIS)

    Svensson, Urban; Ferry, Michel

    2004-03-01

    DarcyTools is a computer code for simulation of flow and transport in porous and/or fractured media. The fractured media in mind is a fractured rock and the porous media the soil cover on the top of the rock; it is hence groundwater flows, which is the class of flows in mind.The User's Guide for DarcyTools V2.1 is intended to assist new users of DarcyTools. The Guide is far from complete and it has not been the ambition to write a manual that answers all questions a user may have. The objectives of the Guide can be stated as follows: - Give an overview of the code structure and how DarcyTools is used. - Get familiar with the 'Compact Input File', which is the main way to specify input data. - Get familiar with the 'Fortran Input File', which is the more advanced way to specify input data

  5. RUPS: Research Utilizing Problem Solving. Administrators Version. Leader's Manual.

    Science.gov (United States)

    Jung, Charles; And Others

    This manual is to be used by leaders of RUPS (Research Utilizing Problem Solving) workshops for school or district administrators. The workshop's goal is for administrators to develop problem solving skills by using the RUPS simulation situations in a teamwork setting. Although workshop leaders should be familiar with the RUPS materials and…

  6. RUPS: Research Utilizing Problem Solving. Classroom Version. Leader's Manual.

    Science.gov (United States)

    Jung, Charles; And Others

    This training manual is for teachers participating in the Research Utilizing Problem Solving (RUPS) workshops. The workshops last for four and one-half days and are designed to improve the school setting and to increase teamwork skills. The teachers participate in simulation exercises in which they help a fictitious teacher or principal solve a…

  7. User's manual for the reactor burnup system, REBUS

    International Nuclear Information System (INIS)

    Olson, A.P.; Regis, J.P.; Meneley, D.A.; Hoover, L.J.

    1972-01-01

    A user's manual for the REBUS System (REactor BUrnup System) is presented. Its primary purpose is to provide sufficient information about the REBUS capability to the user to ensure its efficient utilization. The current REBUS System either solves for the infinite time (equilibrium) operating conditions of a recycle system under fixed conditions, or solves for operating conditions during a single time step (non-equilibrium). The capability of studying various in-reactor fuel management and ex-reactor fuel management schemes has been included. REBUS has been operated with one- and two-dimensional diffusion theory neutronics solutions up to the present time. The model was specifically designed for extension to other neutronics models such as three-dimensional diffusion or transport theory and direct or synthesis solutions

  8. ARIES segmented gamma-ray scanner user manual

    International Nuclear Information System (INIS)

    Biddle, R.S.; Sheppard, G.A.; Schneider, C.M.

    1998-01-01

    The segmented gamma-ray scatter (SGS) designated as Win SGS at the Los Alamos Plutonium Facility has been installed and is intended for use in quantifying the radioisotope content of DOE-STD-3013-96 equivalent containers. The SGS features new software written in C and a new user interface that runs under Microsoft Windows trademark. The operation of the ARIES Segmented Gamma-ray Scanner is documented in this manual. It covers user instructions as well as hardware and software details. Additional information is found in the documentation for the commercially available components and modules that compose the SGS. The objective of the ARIES project is to demonstrate technology to dismantle plutonium pits from excess nuclear weapons, convert the plutonium to a metal ingot or an oxide powder, package the metal or oxide, and verify the contents of the package by nondestructive assay

  9. User manual of nuclide dispersion in phreatic aquifers model

    International Nuclear Information System (INIS)

    Rives, D.E.

    1999-01-01

    The Nuclide Dispersion in Phreatic Aquifers (DRAF) model was developed in the 'Division Estudios Ambientales' of the 'Gerencia de Seguridad Radiologica y Nuclear, Comision Nacional de Energia Atomica' (1991), for the Safety Assessment of Near Surface Radioactive Waste Disposal Facilities. Afterwards, it was modified in several opportunities, adapting it to a number of application conditions. The 'Manual del usuario del codigo DRAF' here presented is a reference document for the use of the last three versions of the code developed for the 'Autoridad Regulatoria Nuclear' between 1995 and 1996. The DRAF model solves the three dimension's solute transport equation for porous media by the finite differences method. It takes into account the advection, dispersion, radioactive decay, and retention in the solid matrix processes, and has multiple possibilities for the source term. There are three versions of the model, two of them for the saturated zone and one for the unsaturated zone. All the versions have been verified in different conditions, and have been applied in exercises of the International Atomic Energy Agency and also in real cases. (author)

  10. Stimulation model for lenticular sands: Volume 2, Users manual

    Energy Technology Data Exchange (ETDEWEB)

    Rybicki, E.F.; Luiskutty, C.T.; Sutrick, J.S.; Palmer, I.D.; Shah, G.H.; Tomutsa, L.

    1987-07-01

    This User's Manual contains information for four fracture/proppant models. TUPROP1 contains a Geertsma and de Klerk type fracture model. The section of the program utilizing the proppant fracture geometry data from the pseudo three-dimensional highly elongated fracture model is called TUPROPC. The analogous proppant section of the program that was modified to accept fracture shape data from SA3DFRAC is called TUPROPS. TUPROPS also includes fracture closure. Finally there is the penny fracture and its proppant model, PENNPROP. In the first three chapters, the proppant sections are based on the same theory for determining the proppant distribution but have modifications to support variable height fractures and modifications to accept fracture geometry from three different fracture models. Thus, information about each proppant model in the User's Manual builds on information supplied in the previous chapter. The exception to the development of combined treatment models is the penny fracture and its proppant model. In this case, a completely new proppant model was developed. A description of how to use the combined treatment model for the penny fracture is contained in Chapter 4. 2 refs.

  11. H2A Production Model, Version 2 User Guide

    Energy Technology Data Exchange (ETDEWEB)

    Steward, D.; Ramsden, T.; Zuboy, J.

    2008-09-01

    The H2A Production Model analyzes the technical and economic aspects of central and forecourt hydrogen production technologies. Using a standard discounted cash flow rate of return methodology, it determines the minimum hydrogen selling price, including a specified after-tax internal rate of return from the production technology. Users have the option of accepting default technology input values--such as capital costs, operating costs, and capacity factor--from established H2A production technology cases or entering custom values. Users can also modify the model's financial inputs. This new version of the H2A Production Model features enhanced usability and functionality. Input fields are consolidated and simplified. New capabilities include performing sensitivity analyses and scaling analyses to various plant sizes. This User Guide helps users already familiar with the basic tenets of H2A hydrogen production cost analysis get started using the new version of the model. It introduces the basic elements of the model then describes the function and use of each of its worksheets.

  12. SIERRA/Aero User Manual Version 4.44

    Energy Technology Data Exchange (ETDEWEB)

    Sierra Thermal/Fluid Team

    2017-04-01

    SIERRA/Aero is a compressible fluid dynamics program intended to solve a wide variety compressible fluid flows including transonic and hypersonic problems. This document describes the commands for assembling a fluid model for analysis with this module, henceforth referred to simply as Aero for brevity. Aero is an application developed using the SIERRA Toolkit (STK). The intent of STK is to provide a set of tools for handling common tasks that programmers encounter when developing a code for numerical simulation. For example, components of STK provide field allocation and management, and parallel input/output of field and mesh data. These services also allow the development of coupled mechanics analysis software for a massively parallel computing environment. In the definitions of the commands that follow, the term Real_Max denotes the largest floating point value that can be represented on a given computer. Int_Max is the largest such integer value.

  13. National Energy Audit (NEAT) Users Manual Version 7; TOPICAL

    International Nuclear Information System (INIS)

    Gettings, M.

    2001-01-01

    Welcome to the U.S. Department of Energy's (DOE's) energy auditing tool, called ''NEAT.'' NEAT, an acronym for National Energy Audit Tool, a program for personal computers that was designed for use by local agencies in the Weatherization Assistance Program. It is an approved alternative audit that meets all auditing requirements set forth by the Program. NEAT is easy to use. It applies engineering and economic calculations to evaluate energy conservation measures for single-family, detached houses or small multifamily buildings. You can use it to rank measures for each individual house, or to establish a priority list of conservation measures for nearly identical housing types. NEAT was written for the Weatherization Assistance Program by Oak Ridge National Laboratory. Many building energy consumption algorithms are taken from Lawrence Berkeley Laboratory's Computerized Instrumented Residential Audit (CIRA), published in 1982 for the Department of Energy. Equipment retrofit conservation measures are based on published reports on various heating retrofits. Heating and cooling system replacement conservation measures are based on the energy ratings of new heating and cooling equipment. The Weatherization Program anticipates that this computer-based energy audit will offer substantial performance improvements to many states who choose to incorporate it into their programs. When conservation measures are evaluated locally according to climate, fuel cost, measure cost, and existing house conditions, the Program will be closer to its goal of assuring the maximum return for every federal dollar spent

  14. SIERRA Multimechanics Module: Aria User Manual Version 4.42.

    Energy Technology Data Exchange (ETDEWEB)

    Sierra Thermal/Fluid Team

    2016-10-01

    Aria is a Galerkin finite element based program for solving coupled-physics problems described by systems of PDEs and is capable of solving nonlinear, implicit, transient and direct-to-steady state problems in two and three dimensions on parallel architectures. The suite of physics currently supported by Aria includes thermal energy transport, species transport, and electrostatics as well as generalized scalar, vector and tensor transport equations. Additionally, Aria includes support for manufacturing process flows via the incompressible Navier-Stokes equations specialized to a low Reynolds number (Re %3C 1) regime. Enhanced modeling support of manufacturing processing is made possible through use of either arbitrary Lagrangian- Eulerian (ALE) and level set based free and moving boundary tracking in conjunction with quasi-static nonlinear elastic solid mechanics for mesh control. Coupled physics problems are solved in several ways including fully-coupled Newton's method with analytic or numerical sensitivities, fully-coupled Newton- Krylov methods and a loosely-coupled nonlinear iteration about subsets of the system that are solved using combinations of the aforementioned methods. Error estimation, uniform and dynamic h-adaptivity and dynamic load balancing are some of Aria's more advanced capabilities. Aria is based upon the Sierra Framework.

  15. Object Toolkit Version 4.2 Users Manual

    Science.gov (United States)

    2014-10-31

    48 Figure 39. Geocentric Orbit Dialog Box...Z Side at (0.44, -0.44, 1.46). ............................................ 114 Figure 133. Geocentric Orbit Dialog Box...element modelers. One approach that works for many is to go directly to the Examples in Part IV and follow them step by step, using other sections of

  16. PC-ECONPACK Version 3.0 Users Manual.

    Science.gov (United States)

    1991-11-01

    for inclusi on in cost sensitivity analysis UPDer Limit of the Change (%). PC-ECONPACK varies all the stipulated expense items both in an upward...Assumptions as stated in the Assumptions text information block. This section is used to discuss why certain alternatives were selected for inclusi ,n in the

  17. NASCAP-2K Version 4.2 Users Manual

    Science.gov (United States)

    2014-10-31

    Surface Element ..........................................166 Figure 151. Definition of the Emitter “ EGun ” of the “Emitter” Example...is the emitter “ EGun .” The properties of “ EGun ” were defined in Object Toolkit to be as shown in Figure 151. The electron gun emits 0.3 Am-2 of 3 keV...is unlimited. 165 Figure 150. Aluminum Cylinder Showing Emitter Surface Element Figure 151. Definition of the Emiter “ EGun ” of the “Emitter” Example

  18. SIERRA/Aero User Manual Version 4.46.

    Energy Technology Data Exchange (ETDEWEB)

    Sierra Thermal/Fluid Team

    2017-09-01

    SIERRA/Aero is a compressible fluid dynamics program intended to solve a wide variety compressible fluid flows including transonic and hypersonic problems. This document describes the commands for assembling a fluid model for analysis with this module, henceforth referred to simply as Aero for brevity. Aero is an application developed using the SIERRA Toolkit (STK). The intent of STK is to provide a set of tools for handling common tasks that programmers encounter when developing a code for numerical simulation. For example, components of STK provide field allocation and management, and parallel input/output of field and mesh data. These services also allow the development of coupled mechanics analysis software for a massively parallel computing environment. In the definitions of the commands that follow, the term Real_Max denotes the largest floating point value that can be represented on a given computer. Int_Max is the largest such integer value.

  19. Walter User’s Manual (Version 1.0).

    Science.gov (United States)

    1987-09-01

    queries and/or commands. 1.2 - How Walter Uses the Screen As shown in Figure 1-1, Walter divides the screen of your terminal into five separate areas...our attention to queries and how to submit them to the database. 1.3.1 - Submitting Queries A query is an expression consisting of words, parentheses...dates, but also with ranges of dates, such as "oct 15 : nov 15". Waiter recognizes three kinds of dates: * Specific dates of the form [date <month> <day

  20. Generic Optimization Program User Manual Version 3.0.0

    International Nuclear Information System (INIS)

    Wetter, Michael

    2009-01-01

    GenOpt is an optimization program for the minimization of a cost function that is evaluated by an external simulation program. It has been developed for optimization problems where the cost function is computationally expensive and its derivatives are not available or may not even exist. GenOpt can be coupled to any simulation program that reads its input from text files and writes its output to text files. The independent variables can be continuous variables (possibly with lower and upper bounds), discrete variables, or both, continuous and discrete variables. Constraints on dependent variables can be implemented using penalty or barrier functions. GenOpt uses parallel computing to evaluate the simulations. GenOpt has a library with local and global multi-dimensional and one-dimensional optimization algorithms, and algorithms for doing parametric runs. An algorithm interface allows adding new minimization algorithms without knowing the details of the program structure. GenOpt is written in Java so that it is platform independent. The platform independence and the general interface make GenOpt applicable to a wide range of optimization problems. GenOpt has not been designed for linear programming problems, quadratic programming problems, and problems where the gradient of the cost function is available. For such problems, as well as for other problems, special tailored software exists that is more efficient

  1. Generic Optimization Program User Manual Version 3.0.0

    Energy Technology Data Exchange (ETDEWEB)

    Wetter, Michael

    2009-05-11

    GenOpt is an optimization program for the minimization of a cost function that is evaluated by an external simulation program. It has been developed for optimization problems where the cost function is computationally expensive and its derivatives are not available or may not even exist. GenOpt can be coupled to any simulation program that reads its input from text files and writes its output to text files. The independent variables can be continuous variables (possibly with lower and upper bounds), discrete variables, or both, continuous and discrete variables. Constraints on dependent variables can be implemented using penalty or barrier functions. GenOpt uses parallel computing to evaluate the simulations. GenOpt has a library with local and global multi-dimensional and one-dimensional optimization algorithms, and algorithms for doing parametric runs. An algorithm interface allows adding new minimization algorithms without knowing the details of the program structure. GenOpt is written in Java so that it is platform independent. The platform independence and the general interface make GenOpt applicable to a wide range of optimization problems. GenOpt has not been designed for linear programming problems, quadratic programming problems, and problems where the gradient of the cost function is available. For such problems, as well as for other problems, special tailored software exists that is more efficient.

  2. SIERRA Multimechanics Module: Aria User Manual Version 4.46.

    Energy Technology Data Exchange (ETDEWEB)

    Sierra Thermal/Fluid Team

    2017-09-01

    Aria is a Galerkin fnite element based program for solving coupled-physics problems described by systems of PDEs and is capable of solving nonlinear, implicit, transient and direct-to-steady state problems in two and three dimensions on parallel architectures. The suite of physics currently supported by Aria includes thermal energy transport, species transport, and electrostatics as well as generalized scalar, vector and tensor transport equations. Additionally, Aria includes support for manufacturing process fows via the incompressible Navier-Stokes equations specialized to a low Reynolds number ( %3C 1 ) regime. Enhanced modeling support of manufacturing processing is made possible through use of either arbitrary Lagrangian- Eulerian (ALE) and level set based free and moving boundary tracking in conjunction with quasi-static nonlinear elastic solid mechanics for mesh control. Coupled physics problems are solved in several ways including fully-coupled Newton's method with analytic or numerical sensitivities, fully-coupled Newton- Krylov methods and a loosely-coupled nonlinear iteration about subsets of the system that are solved using combinations of the aforementioned methods. Error estimation, uniform and dynamic h -adaptivity and dynamic load balancing are some of Aria's more advanced capabilities. Aria is based upon the Sierra Framework.

  3. SIERRA Multimechanics Module: Aria User Manual Version 4.44

    Energy Technology Data Exchange (ETDEWEB)

    Sierra Thermal/Fluid Team

    2017-04-01

    Aria is a Galerkin fnite element based program for solving coupled-physics problems described by systems of PDEs and is capable of solving nonlinear, implicit, transient and direct-to-steady state problems in two and three dimensions on parallel architectures. The suite of physics currently supported by Aria includes thermal energy transport, species transport, and electrostatics as well as generalized scalar, vector and tensor transport equations. Additionally, Aria includes support for manufacturing process fows via the incompressible Navier-Stokes equations specialized to a low Reynolds number ( %3C 1 ) regime. Enhanced modeling support of manufacturing processing is made possible through use of either arbitrary Lagrangian- Eulerian (ALE) and level set based free and moving boundary tracking in conjunction with quasi-static nonlinear elastic solid mechanics for mesh control. Coupled physics problems are solved in several ways including fully-coupled Newton's method with analytic or numerical sensitivities, fully-coupled Newton- Krylov methods and a loosely-coupled nonlinear iteration about subsets of the system that are solved using combinations of the aforementioned methods. Error estimation, uniform and dynamic h -adaptivity and dynamic load balancing are some of Aria's more advanced capabilities. Aria is based upon the Sierra Framework.

  4. STORM WATER MANAGEMENT MODEL USER'S MANUAL VERSION 5.0

    Science.gov (United States)

    The EPA Storm Water Management Model (SWMM) is a dynamic rainfall-runoff simulation model used for single event or long-term (continuous) simulation of runoff quantity and quality from primarily urban areas. SWMM was first developed in 1971 and has undergone several major upgrade...

  5. User's manual ACE/ONED (Version 1.0)

    International Nuclear Information System (INIS)

    Lee, Ki Bok; Lee, Jeong Chan; Song, Jae Seung; Lee, Chang Kyu; Ji, Sung Kyun; Song, Jae Woong; Kim, Yong Rae; Chang, Jong Hwa

    1996-03-01

    This report explains installation of ACE/ONED code, structure of input and output, how to prepare input and introduces some sample inputs. ACE/ONED developed by KAERI is a two-group one-dimensional diffusion theory code for nuclear design and reactor simulations. The usage of ACE/ONED encompasses core follow calculation, load-following calculation, plant power control simulation, xenon oscillation simulation, control rod maneuvering, and so on. ACE/ONED programmed of FORTRAN 77 in most part can be run on almost all kinds of computer including personal computer. 4 tabs., 4 figs., 8 refs. (Author) .new

  6. SAVEWS Jr. User’s Manual, Version 1.0

    Science.gov (United States)

    2014-04-01

    recording sessions are more susceptible to data loss, such as from a power flicker . Second, it will probably be necessary to process a file...not covered in this document. One means of mitigating false SAV detections due to debris is to set the maxplantdepth variable in the configuration

  7. National Energy Audit (NEAT) Users Manual Version 7

    Energy Technology Data Exchange (ETDEWEB)

    Gettings, M.

    2001-05-10

    Welcome to the U.S. Department of Energy's (DOE's) energy auditing tool, called ''NEAT.'' NEAT, an acronym for National Energy Audit Tool, a program for personal computers that was designed for use by local agencies in the Weatherization Assistance Program. It is an approved alternative audit that meets all auditing requirements set forth by the Program. NEAT is easy to use. It applies engineering and economic calculations to evaluate energy conservation measures for single-family, detached houses or small multifamily buildings. You can use it to rank measures for each individual house, or to establish a priority list of conservation measures for nearly identical housing types. NEAT was written for the Weatherization Assistance Program by Oak Ridge National Laboratory. Many building energy consumption algorithms are taken from Lawrence Berkeley Laboratory's Computerized Instrumented Residential Audit (CIRA), published in 1982 for the Department of Energy. Equipment retrofit conservation measures are based on published reports on various heating retrofits. Heating and cooling system replacement conservation measures are based on the energy ratings of new heating and cooling equipment. The Weatherization Program anticipates that this computer-based energy audit will offer substantial performance improvements to many states who choose to incorporate it into their programs. When conservation measures are evaluated locally according to climate, fuel cost, measure cost, and existing house conditions, the Program will be closer to its goal of assuring the maximum return for every federal dollar spent.

  8. International Reactor Physics Handbook Database and Analysis Tool (IDAT) - IDAT user manual

    International Nuclear Information System (INIS)

    2013-01-01

    The IRPhEP Database and Analysis Tool (IDAT) was first released in 2013 and is included on the DVD. This database and corresponding user interface allows easy access to handbook information. Selected information from each configuration was entered into IDAT, such as the measurements performed, benchmark values, calculated values and materials specifications of the benchmark. In many cases this is supplemented with calculated data such as neutron balance data, spectra data, k-eff nuclear data sensitivities, and spatial reaction rate plots. IDAT accomplishes two main objectives: 1. Allow users to search the handbook for experimental configurations that satisfy their input criteria. 2. Allow users to trend results and identify suitable benchmarks experiments for their application. IDAT provides the user with access to several categories of calculated data, including: - 1-group neutron balance data for each configuration with individual isotope contributions in the reactor system. - Flux and other reaction rates spectra in a 299-group energy scheme. Plotting capabilities were implemented into IDAT allowing the user to compare the spectra of selected configurations in the original fine energy structure or on any user-defined broader energy structure. - Sensitivity coefficients (percent changes of k-effective due to elementary change of basic nuclear data) for the major nuclides and nuclear processes in a 238-group energy structure. IDAT is actively being developed. Those approved to access the online version of the handbook will also have access to an online version of IDAT. As May 2013 marks the first release, IDAT may contain data entry errors and omissions. The handbook remains the primary source of reactor physics benchmark data. A copy of IDAT user's manual is attached to this document. A copy of the IRPhE Handbook can be obtained on request at http://www.oecd-nea.org/science/wprs/irphe/irphe-handbook/form.html

  9. User's manual for the Composite HTGR Analysis Program (CHAP-1)

    International Nuclear Information System (INIS)

    Gilbert, J.S.; Secker, P.A. Jr.; Vigil, J.C.; Wecksung, M.J.; Willcutt, G.J.E. Jr.

    1977-03-01

    CHAP-1 is the first release version of an HTGR overall plant simulation program with both steady-state and transient solution capabilities. It consists of a model-independent systems analysis program and a collection of linked modules, each representing one or more components of the HTGR plant. Detailed instructions on the operation of the code and detailed descriptions of the HTGR model are provided. Information is also provided to allow the user to easily incorporate additional component modules, to modify or replace existing modules, or to incorporate a completely new simulation model into the CHAP systems analysis framework

  10. AISIM (Automated Interactive Simulation Modeling System) VAX Version Training Manual.

    Science.gov (United States)

    1985-02-01

    node to which the link is to run, a-nd-(3) a user-given name of the link. To pi’ace a link called " LINKI " from NODE1 to NODE2, type CON NODE1,NODE2...example, to eliminate the connection between NODEI and NODE2 type DELETE LINKI The result on the screen would be that the link named "LINK1" would...the user should now enter the command: DEFINE PATH,NODE2 ,NODE4, LINKI ,LINK4 not only would the path from NODE2 to NODE4 be established, but the path

  11. Light water reactor fuel analysis code FEMAXI-IV(Ver.2). Detailed structure and user`s manual

    Energy Technology Data Exchange (ETDEWEB)

    Suzuki, Motoe [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment; Saitou, Hiroaki

    1997-11-01

    A light water reactor fuel behavior analysis code FEMAXI-IV(Ver.2) was developed as an improved version of FEMAXI-IV. Development of FEMAXI-IV has been already finished in 1992, though a detailed structure and input manual of the code have not been open to users yet. Here, the basic theories and structure, the models and numerical solutions applied to FEMAXI-IV(Ver.2), and the material properties adopted in the code are described in detail. In FEMAXI-IV(Ver.2), programming bugs in previous FEMAXI-IV were eliminated, renewal of the pellet thermal conductivity was performed, and a model of thermal-stress restraint on FP gas release was incorporated. For facilitation of effective and wide-ranging application of the code, methods of input/output of the code are also described in detail, and sample output is included. (author)

  12. User manual for SPLASH (Single Panel Lamp and Shroud Helper).

    Energy Technology Data Exchange (ETDEWEB)

    Larsen, Marvin Elwood

    2006-02-01

    The radiant heat test facility develops test sets providing well-characterized thermal environments, often representing fires. Many of the components and procedures have become standardized to such an extent that the development of a specialized design tool to determine optimal configurations for radiant heat experiments was appropriate. SPLASH (Single Panel Lamp and Shroud Helper) is that tool. SPLASH is implemented as a user-friendly, Windows-based program that allows a designer to describe a test setup in terms of parameters such as number of lamps, power, position, and separation distance. This document is a user manual for that software. Any incidental descriptions of theory are only for the purpose of defining the model inputs. The theory for the underlying model is described in SAND2005-2947 (Ref. [1]). SPLASH provides a graphical user interface to define lamp panel and shroud designs parametrically, solves the resulting radiation enclosure problem for up to 2500 surfaces, and provides post-processing to facilitate understanding and documentation of analyzed designs.

  13. Tree Cover Mapping Tool—Documentation and user manual

    Science.gov (United States)

    Cotillon, Suzanne E.; Mathis, Melissa L.

    2016-06-02

    The Tree Cover Mapping (TCM) tool was developed by scientists at the U.S. Geological Survey Earth Resources Observation and Science Center to allow a user to quickly map tree cover density over large areas using visual interpretation of high resolution imagery within a geographic information system interface. The TCM tool uses a systematic sample grid to produce maps of tree cover. The TCM tool allows the user to define sampling parameters to estimate tree cover within each sample unit. This mapping method generated the first on-farm tree cover maps of vast regions of Niger and Burkina Faso. The approach contributes to implementing integrated landscape management to scale up re-greening and restore degraded land in the drylands of Africa. The TCM tool is easy to operate, practical, and can be adapted to many other applications such as crop mapping, settlements mapping, or other features. This user manual provides step-by-step instructions for installing and using the tool, and creating tree cover maps. Familiarity with ArcMap tools and concepts is helpful for using the tool.

  14. Time warp operating system version 2.7 internals manual

    Science.gov (United States)

    1992-01-01

    The Time Warp Operating System (TWOS) is an implementation of the Time Warp synchronization method proposed by David Jefferson. In addition, it serves as an actual platform for running discrete event simulations. The code comprising TWOS can be divided into several different sections. TWOS typically relies on an existing operating system to furnish some very basic services. This existing operating system is referred to as the Base OS. The existing operating system varies depending on the hardware TWOS is running on. It is Unix on the Sun workstations, Chrysalis or Mach on the Butterfly, and Mercury on the Mark 3 Hypercube. The base OS could be an entirely new operating system, written to meet the special needs of TWOS, but, to this point, existing systems have been used instead. The base OS's used for TWOS on various platforms are not discussed in detail in this manual, as they are well covered in their own manuals. Appendix G discusses the interface between one such OS, Mach, and TWOS.

  15. MPACT Theory Manual, Version 2.2.0

    Energy Technology Data Exchange (ETDEWEB)

    Downar, Thomas [Univ. of Michigan, Ann Arbor, MI (United States); Collins, Benjamin S. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Gehin, Jess C. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Godfrey, Andrew T. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Jabaay, Daniel [Univ. of Michigan, Ann Arbor, MI (United States); Kelley, Blake W. [Univ. of Michigan, Ann Arbor, MI (United States); Clarno, Kevin T. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Kim, Kang [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Kochunas, Brendan [Univ. of Michigan, Ann Arbor, MI (United States); Larsen, Edward W. [Univ. of Michigan, Ann Arbor, MI (United States); Liu, Yuxuan [Univ. of Michigan, Ann Arbor, MI (United States); Liu, Zhouyu [Univ. of Michigan, Ann Arbor, MI (United States); Martin, William R. [Univ. of Michigan, Ann Arbor, MI (United States); Palmtag, Scott [Core Physics, Inc., Cary, NC (United States); Rose, Michael [Univ. of Michigan, Ann Arbor, MI (United States); Saller, Thomas [Univ. of Michigan, Ann Arbor, MI (United States); Stimpson, Shane [Univ. of Michigan, Ann Arbor, MI (United States); Trahan, Travis [Univ. of Michigan, Ann Arbor, MI (United States); Wang, J. W. [Univ. of Michigan, Ann Arbor, MI (United States); Wieselquist, William A. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Young, Mitchell [Univ. of Michigan, Ann Arbor, MI (United States); Zhu, Ang [Univ. of Michigan, Ann Arbor, MI (United States)

    2016-06-09

    This theory manual describes the three-dimensional (3-D) whole-core, pin-resolved transport calculation methodology employed in the MPACT code. To provide sub-pin level power distributions with sufficient accuracy, MPACT employs the method of characteristics (MOC) solutions in the framework of a 3-D coarse mesh finite difference (CMFD) formulation. MPACT provides a 3D MOC solution, but also a 2D/1D solution in which the 2D planar solution is provided by MOC and the axial coupling is resolved by one-dimensional (1-D) lower order (diffusion or P3) solutions. In Chapter 2 of the manual, the MOC methodology is described for calculating the regional angular and scalar fluxes from the Boltzmann transport equation. In Chapter 3, the 2D/1D methodology is described, together with the description of the CMFD iteration process involving dynamic homogenization and solution of the multigroup CMFD linear system. A description of the MPACT depletion algorithm is given in Chapter 4, followed by a discussion of the subgroup and ESSM resonance processing methods in Chapter 5. The final Chapter 6 describes a simplified thermal hydraulics model in MPACT.

  16. User's manual for the HYPGEN hyperbolic grid generator and the HGUI graphical user interface

    Science.gov (United States)

    Chan, William M.; Chiu, Ing-Tsau; Buning, Pieter G.

    1993-01-01

    The HYPGEN program is used to generate a 3-D volume grid over a user-supplied single-block surface grid. This is accomplished by solving the 3-D hyperbolic grid generation equations consisting of two orthogonality relations and one cell volume constraint. In this user manual, the required input files and parameters and output files are described. Guidelines on how to select the input parameters are given. Illustrated examples are provided showing a variety of topologies and geometries that can be treated. HYPGEN can be used in stand-alone mode as a batch program or it can be called from within a graphical user interface HGUI that runs on Silicon Graphics workstations. This user manual provides a description of the menus, buttons, sliders, and typein fields in HGUI for users to enter the parameters needed to run HYPGEN. Instructions are given on how to configure the interface to allow HYPGEN to run either locally or on a faster remote machine through the use of shell scripts on UNIX operating systems. The volume grid generated is copied back to the local machine for visualization using a built-in hook to PLOT3D.

  17. User's manual of JT-60 experimental data analysis system

    International Nuclear Information System (INIS)

    Hirayama, Takashi; Morishima, Soichi; Yoshioka, Yuji

    2010-02-01

    In the Japan Atomic Energy Agency Naka Fusion Institute, a lot of experiments have been conducted by using the large tokamak device JT-60 aiming to realize fusion power plant. In order to optimize the JT-60 experiment and to investigate complex characteristics of plasma, JT-60 experimental data analysis system was developed and used for collecting, referring and analyzing the JT-60 experimental data. Main components of the system are a data analysis server and a database server for the analyses and accumulation of the experimental data respectively. Other peripheral devices of the system are magnetic disk units, NAS (Network Attached Storage) device, and a backup tape drive. This is a user's manual of the JT-60 experimental data analysis system. (author)

  18. Image enhancement software for underwater recovery operations: User's manual

    Science.gov (United States)

    Partridge, William J.; Therrien, Charles W.

    1989-06-01

    This report describes software for performing image enhancement on live or recorded video images. The software was developed for operational use during underwater recovery operations at the Naval Undersea Warfare Engineering Station. The image processing is performed on an IBM-PC/AT compatible computer equipped with hardware to digitize and display video images. The software provides the capability to provide contrast enhancement and other similar functions in real time through hardware lookup tables, to automatically perform histogram equalization, to capture one or more frames and average them or apply one of several different processing algorithms to a captured frame. The report is in the form of a user manual for the software and includes guided tutorial and reference sections. A Digital Image Processing Primer in the appendix serves to explain the principle concepts that are used in the image processing.

  19. EPANET Multi-Species Extension Software and User's Manual ...

    Science.gov (United States)

    Software and User's Manual EPANET is used in homeland security research to model contamination threats to water systems. Historically, EPANET has been limited to tracking the dynamics of a single chemical transported through a network of pipes and storage tanks, such as a fluoride used in a tracer study or free chlorine used in a disinfection decay study. Recently, the NHSRC released a new extension to EPANET called EPANET-MSX (Multi-Species eXtension) that allows for the consideration of multiple interacting species in the bulk flow and on the pipe walls. This capability has been incorporated into both a stand-alone executable program as well as a toolkit library of functions that programmers can use to build customized applications.

  20. Users' manual for fault tree analysis code: CUT-TD

    International Nuclear Information System (INIS)

    Watanabe, Norio; Kiyota, Mikio.

    1992-06-01

    The CUT-TD code has been developed to find minimal cut sets for a given fault tree and to calculate the occurrence probability of its top event. This code uses an improved top-down algorithm which can enhance the efficiency in deriving minimal cut sets. The features in processing techniques incorporated into CUT-TD are as follows: (1) Consecutive OR gates or consecutive AND gates can be coalesced into a single gate. As a result, this processing directly produces cut sets for the redefined single gate with each gate not being developed. (2) The independent subtrees are automatically identified and their respective cut sets are separately found to enhance the efficiency in processing. (3) The minimal cut sets can be obtained for the top event of a fault tree by combining their respective minimal cut sets for several gates of the fault tree. (4) The user can reduce the computing time for finding minimal cut sets and control the size and significance of cut sets by inputting a minimum probability cut off and/or a maximum order cut off. (5) The user can select events that need not to be further developed in the process of obtaining minimal cut sets. This option can reduce the number of minimal cut sets, save the computing time and assists the user in reviewing the result. (6) Computing time is monitored by the CUT-TD code so that it can prevent the running job from abnormally ending due to excessive CPU time and produce an intermediate result. The CUT-TD code has the ability to restart the calculation with use of the intermediate result. This report provides a users' manual for the CUT-TD code. (author)

  1. Desalination Economic Evaluation Program (DEEP-3.0). User's manual

    International Nuclear Information System (INIS)

    2006-01-01

    DEEP is a Desalination Economic Evaluation Program developed by the International Atomic Energy Agency (IAEA) and made freely available for download, under a license agreement (www.iaea.org/nucleardesalination). The program is based on linked Microsoft Excel spreadsheets and can be useful for evaluating desalination strategies by calculating estimates of technical performance and costs for various alternative energy and desalination technology configurations. Desalination technology options modelled, include multi-stage flashing (MSF), multi-effect distillation (MED), reverse osmosis (RO) and hybrid options (RO-MSF, RO-MED) while energy source options include nuclear, fossil, renewables and grid electricity (stand-alone RO). Version 3 of DEEP (DEEP 3.0) features important changes from previous versions, including upgrades in thermal and membrane performance and costing models, the coupling configuration matrix and the user interface. Changes in the thermal performance model include a revision of the gain output ratio (GOR) calculation and its generalization to include thermal vapour compression effects. Since energy costs continue to represent an important fraction of seawater desalination costs, the lost shaft work model has been generalized to properly account for both backpressure and extraction systems. For RO systems, changes include improved modelling of system recovery, feed pressure and permeate salinity, taking into account temperature, feed salinity and fouling correction factors. The upgrade to the coupling technology configuration matrix includes a re-categorization of the energy sources to follow turbine design (steam vs. gas) and cogeneration features (dual-purpose vs. heat-only). In addition, cost data has also been updated to reflect current practice and the user interface has been refurbished and made user-friendlier

  2. Speakeasy-3 reference manual. Level MU. IBM OS/VS version

    International Nuclear Information System (INIS)

    Cohen, S.; Pieper, S.C.

    1977-08-01

    Speakeasy is a computer language designed to provide access to information stored in a computer. Ease of use, natural notation, and built-in capabilities for growth are important features of Speakeasy. The language is based on the concepts of arrays and matrices, and processes these as entities; the need for many of the loops necessary in other programing languages is thus eliminated. It has a large vocabulary (over 500 words) of functions and commands in the areas of array manipulation, matrix algebra including eigenanalysis, special mathematical functions, numerical integration and differentiation, statistics, graphics, and character processing. It can be used either in batch mode or interactively. This book is the primary reference manual for the Speakeasy language and presents a nearly complete description of its capabilities. The chapters deal with the use of Speakeasy as a ''super desk calculator,'' the construction and editing of Speakeasy programs, the ability to communicate with other programing languages, the construction of user-written additions to the language, and various other facets of Speakeasy. In addition, a complete listing of the Help Library, which contains brief descriptions of each of the Speakeasy functions or commands, is included. This edition applies to the Mu release of Speakeasy-3, and describes the IBM OS/VS version. 18 figures

  3. ABAREX -- A neutron spherical optical-statistical-model code -- A user`s manual

    Energy Technology Data Exchange (ETDEWEB)

    Smith, A.B. [ed.; Lawson, R.D.

    1998-06-01

    The contemporary version of the neutron spherical optical-statistical-model code ABAREX is summarized with the objective of providing detailed operational guidance for the user. The physical concepts involved are very briefly outlined. The code is described in some detail and a number of explicit examples are given. With this document one should very quickly become fluent with the use of ABAREX. While the code has operated on a number of computing systems, this version is specifically tailored for the VAX/VMS work station and/or the IBM-compatible personal computer.

  4. The Digital Heart Manual: A pilot study of an innovative cardiac rehabilitation programme developed for and with users.

    Science.gov (United States)

    Deighan, C; Michalova, L; Pagliari, C; Elliott, J; Taylor, L; Ranaldi, H

    2017-08-01

    Patients are seeking greater choice and flexibility in how they engage with self-management programmes. While digital innovations offer opportunities to deliver supportive interventions to patients undergoing cardiac rehabilitation little is known about how accessible, useful and acceptable they are for this group. This project developed a digital version of a leading evidenced cardiac rehabilitation programme, the Heart Manual (HM). The prototype was developed and evaluated iteratively in collaboration with end users. Using a mixed methods design 28 participants provided feedback using semi-structured questionnaires and telephone interviews. Rich data revealed the perceived user-friendliness of the HM digital format and its effectiveness at communicating the programme's key messages. It flagged areas requiring development, such as more flexible and intuitive navigation pathways. These suggestions informed the refinement of the resource. This evaluation offers support for the new Digital Heart Manual and confirms the value of employing a user-centred approach when developing and improving online interventions. The system is now in use and recommendations from the evaluation are being translated into quality improvements. The Digital Heart Manual is user friendly and accessible to patients and health professionals, regardless of age, presenting a suitable alternative to the paper version. Copyright © 2017 Elsevier B.V. All rights reserved.

  5. User's manual for the NEFTRAN II computer code

    International Nuclear Information System (INIS)

    Olague, N.E.; Campbell, J.E.; Leigh, C.D.; Longsine, D.E.

    1991-02-01

    This document describes the NEFTRAN II (NEtwork Flow and TRANsport in Time-Dependent Velocity Fields) computer code and is intended to provide the reader with sufficient information to use the code. NEFTRAN II was developed as part of a performance assessment methodology for storage of high-level nuclear waste in unsaturated, welded tuff. NEFTRAN II is a successor to the NEFTRAN and NWFT/DVM computer codes and contains several new capabilities. These capabilities include: (1) the ability to input pore velocities directly to the transport model and bypass the network fluid flow model, (2) the ability to transport radionuclides in time-dependent velocity fields, (3) the ability to account for the effect of time-dependent saturation changes on the retardation factor, and (4) the ability to account for time-dependent flow rates through the source regime. In addition to these changes, the input to NEFTRAN II has been modified to be more convenient for the user. This document is divided into four main sections consisting of (1) a description of all the models contained in the code, (2) a description of the program and subprograms in the code, (3) a data input guide and (4) verification and sample problems. Although NEFTRAN II is the fourth generation code, this document is a complete description of the code and reference to past user's manuals should not be necessary. 19 refs., 33 figs., 25 tabs

  6. Multi-Sector Sustainability Browser (MSSB) User Manual: A ...

    Science.gov (United States)

    EPA’s Sustainable and Healthy Communities (SHC) Research Program is developing methodologies, resources, and tools to assist community members and local decision makers in implementing policy choices that facilitate sustainable approaches in managing their resources affecting the built environment, natural environment, and human health. In order to assist communities and decision makers in implementing sustainable practices, EPA is developing computer-based systems including models, databases, web tools, and web browsers to help communities decide upon approaches that support their desired outcomes. Communities need access to resources that will allow them to achieve their sustainability objectives through intelligent decisions in four key sustainability areas: • Land Use • Buildings and Infrastructure • Transportation • Materials Management (i.e., Municipal Solid Waste [MSW] processing and disposal) The Multi-Sector Sustainability Browser (MSSB) is designed to support sustainable decision-making for communities, local and regional planners, and policy and decision makers. Document is an EPA Technical Report, which is the user manual for the Multi-Sector Sustainability Browser (MSSB) tool. The purpose of the document is to provide basic guidance on use of the tool for users

  7. User's manual for the Oak Ridge Tokamak Transport Code

    International Nuclear Information System (INIS)

    Munro, J.K.; Hogan, J.T.; Howe, H.C.; Arnurius, D.E.

    1977-02-01

    A one-dimensional tokamak transport code is described which simulates a plasma discharge using a fluid model which includes power balances for electrons and ions, conservation of mass, and Maxwell's equations. The modular structure of the code allows a user to add models of various physical processes which can modify the discharge behavior. Such physical processes treated in the version of the code described here include effects of plasma transport, neutral gas transport, impurity diffusion, and neutral beam injection. Each process can be modeled by a parameterized analytic formula or at least one detailed numerical calculation. The program logic of each module is presented, followed by detailed descriptions of each subroutine used by the module. The physics underlying the models is only briefly summarized. The transport code was written in IBM FORTRAN-IV and implemented on IBM 360/370 series computers at the Oak Ridge National Laboratory and on the CDC 7600 computers of the Magnetic Fusion Energy (MFE) Computing Center of the Lawrence Livermore Laboratory. A listing of the current reference version is provided on accompanying microfiche

  8. Physical habitat simulation system reference manual: version II

    Science.gov (United States)

    Milhous, Robert T.; Updike, Marlys A.; Schneider, Diane M.

    1989-01-01

    stream system basis. Such analysis is outside the scope of this manual, which concentrates on simulation of physical habitat based on depth, velocity, and a channel index. The results form PHABSIM can be used alone or by using a series of habitat time series programs that have been developed to generate monthly or daily habitat time series from the Weighted Usable Area versus streamflow table resulting from the habitat simulation programs and streamflow time series data. Monthly and daily streamflow time series may be obtained from USGS gages near the study site or as the output of river system management models.

  9. High School and Beyond Transcripts Survey (1982). Data File User's Manual. Contractor Report.

    Science.gov (United States)

    Jones, Calvin; And Others

    This data file user's manual documents the procedures used to collect and process high school transcripts for a large sample of the younger cohort (1980 sophomores) in the High School and Beyond survey. The manual provides the user with the technical assistance needed to use the computer file and also discusses the following: (1) sample design for…

  10. Light water reactor fuel analysis code FEMAXI-IV(Ver.2). Detailed structure and user's manual

    International Nuclear Information System (INIS)

    Suzuki, Motoe; Saitou, Hiroaki.

    1997-11-01

    A light water reactor fuel behavior analysis code FEMAXI-IV(Ver.2) was developed as an improved version of FEMAXI-IV. Development of FEMAXI-IV has been already finished in 1992, though a detailed structure and input manual of the code have not been open to users yet. Here, the basic theories and structure, the models and numerical solutions applied to FEMAXI-IV(Ver.2), and the material properties adopted in the code are described in detail. In FEMAXI-IV(Ver.2), programming bugs in previous FEMAXI-IV were eliminated, renewal of the pellet thermal conductivity was performed, and a model of thermal-stress restraint on FP gas release was incorporated. For facilitation of effective and wide-ranging application of the code, methods of input/output of the code are also described in detail, and sample output is included. (author)

  11. SHEAT for PC. A computer code for probabilistic seismic hazard analysis for personal computer, user's manual

    International Nuclear Information System (INIS)

    Yamada, Hiroyuki; Tsutsumi, Hideaki; Ebisawa, Katsumi; Suzuki, Masahide

    2002-03-01

    The SHEAT code developed at Japan Atomic Energy Research Institute is for probabilistic seismic hazard analysis which is one of the tasks needed for seismic Probabilistic Safety Assessment (PSA) of a nuclear power plant. At first, SHEAT was developed as the large sized computer version. In addition, a personal computer version was provided to improve operation efficiency and generality of this code in 2001. It is possible to perform the earthquake hazard analysis, display and the print functions with the Graphical User Interface. With the SHEAT for PC code, seismic hazard which is defined as an annual exceedance frequency of occurrence of earthquake ground motions at various levels of intensity at a given site is calculated by the following two steps as is done with the large sized computer. One is the modeling of earthquake generation around a site. Future earthquake generation (locations, magnitudes and frequencies of postulated earthquake) is modeled based on the historical earthquake records, active fault data and expert judgment. Another is the calculation of probabilistic seismic hazard at the site. An earthquake ground motion is calculated for each postulated earthquake using an attenuation model taking into account its standard deviation. Then the seismic hazard at the site is calculated by summing the frequencies of ground motions by all the earthquakes. This document is the user's manual of the SHEAT for PC code. It includes: (1) Outline of the code, which include overall concept, logical process, code structure, data file used and special characteristics of code, (2) Functions of subprogram and analytical models in them, (3) Guidance of input and output data, (4) Sample run result, and (5) Operational manual. (author)

  12. User's manual for seismic analysis code 'SONATINA-2V'

    International Nuclear Information System (INIS)

    Hanawa, Satoshi; Iyoku, Tatsuo

    2001-08-01

    The seismic analysis code, SONATINA-2V, has been developed to analyze the behavior of the HTTR core graphite components under seismic excitation. The SONATINA-2V code is a two-dimensional computer program capable of analyzing the vertical arrangement of the HTTR graphite components, such as fuel blocks, replaceable reflector blocks, permanent reflector blocks, as well as their restraint structures. In the analytical model, each block is treated as rigid body and is restrained by dowel pins which restrict relative horizontal movement but allow vertical and rocking motions between upper and lower blocks. Moreover, the SONATINA-2V code is capable of analyzing the core vibration behavior under both simultaneous excitations of vertical and horizontal directions. The SONATINA-2V code is composed of the main program, pri-processor for making the input data to SONATINA-2V and post-processor for data processing and making the graphics from analytical results. Though the SONATINA-2V code was developed in order to work in the MSP computer system of Japan Atomic Energy Research Institute (JAERI), the computer system was abolished with the technical progress of computer. Therefore, improvement of this analysis code was carried out in order to operate the code under the UNIX machine, SR8000 computer system, of the JAERI. The users manual for seismic analysis code, SONATINA-2V, including pri- and post-processor is given in the present report. (author)

  13. Development of probabilistic fracture mechanics code PASCAL and user's manual

    Energy Technology Data Exchange (ETDEWEB)

    Shibata, Katsuyuki; Onizawa, Kunio [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment; Li, Yinsheng; Kato, Daisuke [Fuji Research Institute Corporation, Tokyo (Japan)

    2001-03-01

    As a part of the aging and structural integrity research for LWR components, a new PFM (Probabilistic Fracture Mechanics) code PASCAL (PFM Analysis of Structural Components in Aging LWR) has been developed since FY1996. This code evaluates the failure probability of an aged reactor pressure vessel subjected to transient loading such as PTS (Pressurized Thermal Shock). The development of the code has been aimed to improve the accuracy and reliability of analysis by introducing new analysis methodologies and algorithms considering the recent development in the fracture mechanics methodologies and computer performance. The code has some new functions in optimized sampling and cell dividing procedure in stratified Monte Carlo simulation, elastic-plastic fracture criterion of R6 method, extension analysis models in semi-elliptical crack, evaluation of effect of thermal annealing and etc. In addition, an input data generator of temperature and stress distribution time histories was also prepared in the code. Functions and performance of the code have been confirmed based on the verification analyses and some case studies on the influence parameters. The present phase of the development will be completed in FY2000. Thus this report provides the user's manual and theoretical background of the code. (author)

  14. MACSIS User's Manual and Code Description

    Energy Technology Data Exchange (ETDEWEB)

    Hwang, Woan; Lee, Byoung Oon; Kim, Kyung Gun; Kim, Young Jin [Korea Atomic Energy Research Institute, Taejeon (Korea); Lee, Dong Uk [Hanyang Univ., Seoul (Korea)

    2000-03-01

    MACSIS is a computer program for simulating the behavior of metal fuel elements under normal operating conditions of a Liquid Metal Cooled Reactor. It computes the one-dimensional temperature distribution and the thermo-mechanical characteristics of fuel rod under the steady state operation condition, including the swelling and rod deformation. The amount of fission gas released during the irradiation of the fuel is also computed. The thermal expansion and the gas pressure inside the fuel element are then used to compute the stresses and strains in the cladding. This document is mainly intended as a user's manual for the MACSIS code. A short description of the capabilities of the code and detailed input instructions are supplied for this purpose. MACSIS is constructed of a series of modules with a single set of dimensional units used throughout to provide flexibility in model usage and ease of upgrading as models developed from future tests are finalized. Radial steady state heat transfer can be computed for 21 axial segments. The code computes all major quantities which affect in-reactor performances of fuel rod, such as, fission gas generation and retention, fission gas release, swelling, and deformation, etc. 37 refs., 24 figs., 3 tabs. (Author)

  15. TOUGH2 User's Guide Version 2

    Energy Technology Data Exchange (ETDEWEB)

    Pruess, K.; Oldenburg, C.M.; Moridis, G.J.

    1999-11-01

    TOUGH2 is a numerical simulator for nonisothermal flows of multicomponent, multiphase fluids in one, two, and three-dimensional porous and fractured media. The chief applications for which TOUGH2 is designed are in geothermal reservoir engineering, nuclear waste disposal, environmental assessment and remediation, and unsaturated and saturated zone hydrology. TOUGH2 was first released to the public in 1991; the 1991 code was updated in 1994 when a set of preconditioned conjugate gradient solvers was added to allow a more efficient solution of large problems. The current Version 2.0 features several new fluid property modules and offers enhanced process modeling capabilities, such as coupled reservoir-wellbore flow, precipitation and dissolution effects, and multiphase diffusion. Numerous improvements in previously released modules have been made and new user features have been added, such as enhanced linear equation solvers, and writing of graphics files. The T2VOC module for three-phase flows of water, air and a volatile organic chemical (VOC), and the T2DM module for hydrodynamic dispersion in 2-D flow systems have been integrated into the overall structure of the code and are included in the Version 2.0 package. Data inputs are upwardly compatible with the previous version. Coding changes were generally kept to a minimum, and were only made as needed to achieve the additional functionalities desired. TOUGH2 is written in standard FORTRAN77 and can be run on any platform, such as workstations, PCs, Macintosh, mainframe and supercomputers, for which appropriate FORTRAN compilers are available. This report is a self-contained guide to application of TOUGH2 to subsurface flow problems. It gives a technical description of the TOUGH2 code, including a discussion of the physical processes modeled, and the mathematical and numerical methods used. Illustrative sample problems are presented along with detailed instructions for preparing input data.

  16. User manual for PACTOLUS: a code for computing power costs

    International Nuclear Information System (INIS)

    Huber, H.D.; Bloomster, C.H.

    1979-02-01

    PACTOLUS is a computer code for calculating the cost of generating electricity. Through appropriate definition of the input data, PACTOLUS can calculate the cost of generating electricity from a wide variety of power plants, including nuclear, fossil, geothermal, solar, and other types of advanced energy systems. The purpose of PACTOLUS is to develop cash flows and calculate the unit busbar power cost (mills/kWh) over the entire life of a power plant. The cash flow information is calculated by two principal models: the Fuel Model and the Discounted Cash Flow Model. The Fuel Model is an engineering cost model which calculates the cash flow for the fuel cycle costs over the project lifetime based on input data defining the fuel material requirements, the unit costs of fuel materials and processes, the process lead and lag times, and the schedule of the capacity factor for the plant. For nuclear plants, the Fuel Model calculates the cash flow for the entire nuclear fuel cycle. For fossil plants, the Fuel Model calculates the cash flow for the fossil fuel purchases. The Discounted Cash Flow Model combines the fuel costs generated by the Fuel Model with input data on the capital costs, capital structure, licensing time, construction time, rates of return on capital, tax rates, operating costs, and depreciation method of the plant to calculate the cash flow for the entire lifetime of the project. The financial and tax structure for both investor-owned utilities and municipal utilities can be simulated through varying the rates of return on equity and debt, the debt-equity ratios, and tax rates. The Discounted Cash Flow Model uses the principal that the present worth of the revenues will be equal to the present worth of the expenses including the return on investment over the economic life of the project. This manual explains how to prepare the input data, execute cases, and interpret the output results with the updated version of PACTOLUS. 11 figures, 2 tables

  17. Wind-US Users Guide Version 3.0

    Science.gov (United States)

    Yoder, Dennis A.

    2016-01-01

    Wind-US is a computational platform which may be used to numerically solve various sets of equations governing physical phenomena. Currently, the code supports the solution of the Euler and Navier-Stokes equations of fluid mechanics, along with supporting equation sets governing turbulent and chemically reacting flows. Wind-US is a product of the NPARC Alliance, a partnership between the NASA Glenn Research Center (GRC) and the Arnold Engineering Development Complex (AEDC) dedicated to the establishment of a national, applications-oriented flow simulation capability. The Boeing Company has also been closely associated with the Alliance since its inception, and represents the interests of the NPARC User's Association. The "Wind-US User's Guide" describes the operation and use of Wind-US, including: a basic tutorial; the physical and numerical models that are used; the boundary conditions; monitoring convergence; the files that are read and/or written; parallel execution; and a complete list of input keywords and test options. For current information about Wind-US and the NPARC Alliance, please see the Wind-US home page at http://www.grc.nasa.gov/WWW/winddocs/ and the NPARC Alliance home page at http://www.grc.nasa.gov/WWW/wind/. This manual describes the operation and use of Wind-US, a computational platform which may be used to numerically solve various sets of equations governing physical phenomena. Wind-US represents a merger of the capabilities of four CFD codes - NASTD (a structured grid flow solver developed at McDonnell Douglas, now part of Boeing), NPARC (the original NPARC Alliance structured grid flow solver), NXAIR (an AEDC structured grid code used primarily for store separation analysis), and ICAT (an unstructured grid flow solver developed at the Rockwell Science Center and Boeing).

  18. ELIST v.8.1 : User's Manual.; TOPICAL

    International Nuclear Information System (INIS)

    Van Groningen, Blachowicz D.; Duffy Braun, M.; Clemmons, M. A.; Simunich, K. L.; Timmerman, D.; VanderZee, H.; Widing, M. A.

    2002-01-01

    This user's manual documents the capabilities and functions of the Enhanced Logistics Intratheater Support Tool (ELIST) software application. Steps for using the Expanded Time Phase Force Deployment Data (ETPFDD) Editor (ETEdit), which is included in ELIST but is also a stand-alone software application, are contained in a separate document. ELIST is a discrete event simulation tool developed for use by military planners in both the continental United States (CONUS) and outside the continental United States (OCONUS). It simulates the reception, staging, onward movement, and integration (RSOI) of military personnel and equipment from all services within, between, or among countries. ELIST not only runs a simulation, but it also provides the capability to edit asset sets, networks, and scenarios. These capabilities show how various changes can affect the outcome of a simulation. Further, ELIST incorporates topographic maps on which the network is displayed. The system also allows planners to simulate scenarios at the vehicle level. Prior to the implementation of ELIST, planners were able to simulate military deployment from the point of departure (origin) to the point of arrival in the theater (the port of debarkation). Since the development and implementation of ELIST, however, planners can simulate military deployment from the point of departure (airport or seaport), through the staging area, through the theater-staging base, to the final destination. A typical scenario might be set up to transport personnel and cargo to a location by aircraft or ship. Upon arrival at the airport or seaport, the cargo would be sent to a staging area where it would be set up and transferred to a vehicle, or in the case of petroleum, oil, and lubricants (POL), a pipeline. The vehicle then would transport the cargo to the theater-staging base where it would ''marry up'' with the main body of personnel. From this point, the cargo and the main body would be transported to the final

  19. Evaluation of the Swedish version of the Child Drawing: Hospital Manual.

    Science.gov (United States)

    Wennström, Berith; Nasic, Salmir; Hedelin, Hans; Bergh, Ingrid

    2011-05-01

    This paper is a report of psychometric testing of the Swedish version of the Child Drawing: Hospital Manual. Drawings have shown to be useful in assessing emotional status and anxiety in children because they generally speak to us more clearly and openly through their drawings than they are willing or able to verbally. The Child Drawing: Hospital Manual was translated into Swedish according to World Health Organization guidelines (a routine procedure for translation of English instruments) in order to assess anxiety by analysing the drawings of 59 children (5-11 years), of whom nine were girls and 50 boys undergoing day surgery during 2007-2009. Inter-rater reliability (five independent scorers) was high and internal consistency reliability was good (coefficient alpha =0·77). Parts A and C, as well as the total scale score of the Child Drawing: Hospital Manual, discriminated anxiety significantly between the group of children undergoing day surgery and a comparison group of school children, indicating adequate construct validity. For the Swedish version of the Child Drawing: Hospital Manual, our study demonstrates evidence for adequate construct validity in Parts A and C (and total scale score), high inter-rater reliability and acceptable internal consistency reliability. However, some improvements are needed before the instrument will be a clinically useful assessment of anxiety in children undergoing day surgery. © 2011 Blackwell Publishing Ltd.

  20. Treatment for Abused and Neglected Children. The User Manual Series.

    Science.gov (United States)

    Martin, Harold P.

    This manual brings current knowledge about the needs of abused and neglected children together with practical ideas about what can be done to meet those needs. Designed primarily for use by child protective service (CPS) workers, the manual may also be used by other professionals dealing with child abuse and neglect. Chapter 1 briefly discusses…

  1. PRISMA single crystal cold neutron spectrometer and diffractometer. User manual

    International Nuclear Information System (INIS)

    Harris, M.; Bull, M.

    1998-01-01

    PRISMA has undergone a complete rebuild since the First Edition of this manual, resulting in a rather different instrument to that of January 1995. Now that the development of the instrument has reached a quiescent stage, this new edition of the manual describes the operation of PRISMA for the foreseeable future

  2. User's guide for ABCI version 9.4 (azimuthal beam cavity interaction) and introducing the ABCI windows application package

    International Nuclear Information System (INIS)

    Chin, Yong Ho

    2005-12-01

    ABCI is a computer program which solves the Maxwell equations directly in the time domain when a bunched beam goes through an axi-symmetric structure on or off axis. An arbitrary charge distribution can be defined by the user (default=Gaussian). This document is meant to be a comprehensive user's guide to describe all features of ABCI version 9.4, including also all additions since the release of the guide for version 8.8. All appendixes from the previous two user's guides that contain different important topics are also quoted. The main advantages of ABCI lie in its high speed of execution, the minimum use of computer memory, implementation of Napoly integration method and many elaborate options of Fourier transformations. In the version 9.4, even wake potentials for a counter-rotating beam of opposite charge can be calculated instead of usual ones for a beam trailing the driving beams. Now, the Windows application version of ABCI is available as a package which includes ABCI stand-alone executable modules, the sample input files, the source codes, manuals and the Windows version of TopDrawer, TopDrawW. This package can be downloaded from the ABCI home page: http://abci.kek.jp/abci.htm. Just by drag-and-droping an input file on the icon of ABCI application, all the calculation results pop out. Neither compilation of the source code nor installation of the program to Windows is necessary. Together with the TopDrawer for Windows, all works (computation of wake fields, generation of figures and so on) can be done simply and easily on Windows alone. How to use ABCI on Windows and how to install the program to other computer systems are explained at the end of this manual. (author)

  3. Prototype road weather performance management (RWPM) tool installation instructions & user manual.

    Science.gov (United States)

    2016-07-20

    This document is the Installation Instructions and User Manual for the Road Weather Performance Management (RW-PM) Tool developed for the project on Development and Demonstration of a Prototype Road Weather Performance Management Application that Use...

  4. National Solar Radiation Database 1991-2010 Update: User's Manual

    Energy Technology Data Exchange (ETDEWEB)

    Wilcox, S. M.

    2012-08-01

    This user's manual provides information on the updated 1991-2010 National Solar Radiation Database. Included are data format descriptions, data sources, production processes, and information about data uncertainty.

  5. Computer-based guidelines for concrete pavements : HIPERPAV III : user manual

    Science.gov (United States)

    2009-10-01

    This user manual provides guidance on how to use the new High PERformance PAVing (HIPERPAV) III software program for the analysis of early-age Portland cement concrete pavement (PCCP) behavior. HIPERPAV III includes several improvements over prev...

  6. SSC-K code user's manual

    Energy Technology Data Exchange (ETDEWEB)

    Kwon, Y.M.; Lee, Y.B.; Chang, W.P.; Hahn, D

    2000-07-01

    , constitutive laws and correlations required to execute the SSC-K are described. It is noted that the user's manual will be revised later with the further development of SSC-K.

  7. A user's manual for the three-dimensional Monte Carlo transport code SPARTAN

    International Nuclear Information System (INIS)

    Bending, R.C.; Heffer, P.J.H.

    1975-09-01

    SPARTAN is a general-purpose Monte Carlo particle transport code intended for neutron or gamma transport problems in reactor physics, health physics, shielding, and safety studies. The code used a very general geometry system enabling a complex layout to be described and allows the user to obtain physics data from a number of different types of source library. Special tracking and scoring techniques are used to improve the quality of the results obtained. To enable users to run SPARTAN, brief descriptions of the facilities available in the code are given and full details of data input and job control language, as well as examples of complete calculations, are included. It is anticipated that changes may be made to SPARTAN from time to time, particularly in those parts of the code which deal with physics data processing. The load module is identified by a version number and implementation date, and updates of sections of this manual will be issued when significant changes are made to the code. (author)

  8. User manual of Visual Balan V. 1.0 Interactive code for water balances and refueling estimation

    International Nuclear Information System (INIS)

    Samper, J.; Huguet, L.; Ares, J.; Garcia, M. A.

    1999-01-01

    This document contains the Users Manual of Visual Balan V1.0, an updated version of Visual Balan V0.0 (Samper et al., 1997). Visual Balan V1.0 performs daily water balances in the soil, the unsaturated zone and the aquifer in a user-friendly environment which facilitates both the input data process and the postprocessing of results. The main inputs of the balance are rainfall and irrigation while the outputs are surface runoff, evapotranspiration, interception, inter flow and groundwater flow. The code evaluates all these components in a sequential manner by starting with rainfall and irrigation, which must be provided by the user, and continuing with interception, surface runoff, evapotranspiration, and potential recharge (water flux crossing the bottom of the soil). This potential recharge is the input to the unsaturated zone where water can flow horizontally as subsurface flow (inter flow) or vertically as percolation into the aquifer. (Author)

  9. The Intelligent Monitoring System: Generic Database Interface (GDI). User Manual. Revision

    Science.gov (United States)

    1994-01-03

    Summary of Lo=catos Nan* Decufptin Directory Location User Manual FrameMaker ’ source organized inlo, a book UBSW~ftbendb~doclim/user-manual named gdibk A...functions. LNSRCf1bgenrdb/srC I. Framemaker is a docment publishing tool fium Fame Technology Cororation Baseline: 21.1 3-1 anoAW ftnua ?bewd uw on 3.2

  10. Vault Safety and Inventory System users manual, PRIME 2350. Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    Downey, N.J.

    1994-12-14

    This revision is issued to request review of the attached document: VSIS User Manual, PRIME 2350, which provides user information for the operation of the VSIS (Vault Safety and Inventory System). It describes operational aspects of Prime 2350 minicomputer and vault data acquisition equipment. It also describes the User`s Main Menu and menu functions, including REPORTS. Also, system procedures for the Prime 2350 minicomputer are covered.

  11. User`s Guide for the NREL Force and Loads Analysis Program. Version 2.2

    Energy Technology Data Exchange (ETDEWEB)

    Wright, A D

    1992-08-01

    The following report gives the reader an overview of and instructions on the proper use of the National Renewable Energy Laboratory Force and Loads Analysis Program (FLAP, version 2.2). It is intended as a tool for prediction of rotor and blade loads and response for two- or three-bladed rigid hub wind turbines. The effects of turbulence are accounted for. The objectives of the report are to give an overview of the code and also show the methods of data input and correct code execution steps in order to model an example two-bladed rigid hub turbine. A large portion of the discussion (Sections 6.0, 7.0, and 8.0) is devoted to the subject of inputting and running the code for wind turbulence effects. The ability to include turbulent wind effects is perhaps the biggest change in the code since the release of FLAP version 2.01 in 1988. This report is intended to be a user`s guide. It does not contain a theoretical discussion on equations of motion, assumptions, underlying theory, etc. It is intended to be used in conjunction with Wright, Buhl, and Thresher (1988).

  12. Systems Analysis Programs for Hands-on Integrated Reliability Evaluations (SAPHIRE), Version 5.0: Integrated Reliability and Risk Analysis System (IRRAS) reference manual. Volume 2

    International Nuclear Information System (INIS)

    Russell, K.D.; Kvarfordt, K.J.; Skinner, N.L.; Wood, S.T.; Rasmuson, D.M.

    1994-07-01

    The Systems Analysis Programs for Hands-on Integrated Reliability Evaluations (SAPHIRE) refers to a set of several microcomputer programs that were developed to create and analyze probabilistic risk assessments (PRAs), primarily for nuclear power plants. The Integrated Reliability and Risk Analysis System (IRRAS) is a state-of-the-art, microcomputer-based probabilistic risk assessment (PRA) model development and analysis tool to address key nuclear plant safety issues. IRRAS is an integrated software tool that gives the use the ability to create and analyze fault trees and accident sequences using a microcomputer. This program provides functions that range from graphical fault tree construction to cut set generation and quantification to report generation. Version 1.0 of the IRRAS program was released in February of 1987. Since then, many user comments and enhancements have been incorporated into the program providing a much more powerful and user-friendly system. This version has been designated IRRAS 5.0 and is the subject of this Reference Manual. Version 5.0 of IRRAS provides the same capabilities as earlier versions and ads the ability to perform location transformations, seismic analysis, and provides enhancements to the user interface as well as improved algorithm performance. Additionally, version 5.0 contains new alphanumeric fault tree and event used for event tree rules, recovery rules, and end state partitioning

  13. Sampling large landscapes with small-scale stratification-User's Manual

    Science.gov (United States)

    Bart, Jonathan

    2011-01-01

    This manual explains procedures for partitioning a large landscape into plots, assigning the plots to strata, and selecting plots in each stratum to be surveyed. These steps are referred to as the "sampling large landscapes (SLL) process." We assume that users of the manual have a moderate knowledge of ArcGIS and Microsoft ® Excel. The manual is written for a single user but in many cases, some steps will be carried out by a biologist designing the survey and some steps will be carried out by a quantitative assistant. Thus, the manual essentially may be passed back and forth between these users. The SLL process primarily has been used to survey birds, and we refer to birds as subjects of the counts. The process, however, could be used to count any objects. ®

  14. LLCEDATA and LLCECALC for Windows version 1.0, Volume 2: Technical manual

    Energy Technology Data Exchange (ETDEWEB)

    McFadden, J.G.

    1998-09-04

    LLCEDATA and LLCECALC for Windows are user-friendly computer software programs that work together to determine the proper waste designation, handling, and disposition requirements for Long Length Contaminated Equipment (LLCE). LLCEDATA reads from a variety of databases to produce an equipment data file (EDF) that represents a snapshot of both the LLCE and the tank from which it originates. LLCECALC reads the EDF and the gamma assay (AV2) file that is produced by the Flexible Receiver Gamma Energy Analysis System. LLCECALC performs corrections to the AV2 file as it is being read and characterizes the LLCE Both programs produce a variety of reports, including a characterization report and a status report. The status report documents each action taken by the user, LLCEDA TA, and LLCECALC. Documentation for LLCEDA TA and LLCECALC for Windows is available in three volumes. Volume 1 is a user`s manual, which is intended as a quick reference for both LLCEDATA and LLCECALC. Volume 2 is a technical manual, which documents LLCEDATA and LLCECALCs methodology, structure, and format, provides sample calculations; discusses system limitations; and provides recommendations to the LLCE process. Volume 3 is a software verification and validation document LLCEDATA and LLCECALC for Windows are sponsored by the U.S.Department of Energy. They were developed and are maintained by Engineering, Waste Management Federal Services, Inc., Northwest Operations. Copies of the software and documentation are available by contacting Engineering, Waste Management Federal Services, Inc., Northwest Operations, Richland, Washington.

  15. QRev—Software for computation and quality assurance of acoustic doppler current profiler moving-boat streamflow measurements—User’s manual for version 2.8

    Science.gov (United States)

    Mueller, David S.

    2016-05-12

    The software program, QRev computes the discharge from moving-boat acoustic Doppler current profiler measurements using data collected with any of the Teledyne RD Instrument or SonTek bottom tracking acoustic Doppler current profilers. The computation of discharge is independent of the manufacturer of the acoustic Doppler current profiler because QRev applies consistent algorithms independent of the data source. In addition, QRev automates filtering and quality checking of the collected data and provides feedback to the user of potential quality issues with the measurement. Various statistics and characteristics of the measurement, in addition to a simple uncertainty assessment are provided to the user to assist them in properly rating the measurement. QRev saves an extensible markup language file that can be imported into databases or electronic field notes software. The user interacts with QRev through a tablet-friendly graphical user interface. This report is the manual for version 2.8 of QRev.

  16. Simplified Procedures for Eutrophication Assessment and Prediction: User Manual

    Science.gov (United States)

    1996-09-01

    1975), for use in the Lake Erie Wastewater Management Study and is described by Verhoff, Yaksich, and Melfi (1980) and Westerdahl et al. (1981). This...manual," Technical Re- port E-81-9, U.S. Army Engineer Waterways Experiment Station, Vicksburg, MS. Westerdahl , H. E., Ford, W. B., Harris, J., and

  17. User manual of FRAPCON-I computer code

    International Nuclear Information System (INIS)

    Chia, C.T.

    1985-11-01

    The manual for using the FRAPCON-I code implanted by Reactor Department of Brazilian-CNEN to convert IBM FORTRAN in FORTRAN 77 of Honeywell Bull computer is presented. The FRAPCON-I code describes the behaviour of fuel rods of PWR type reactors at stationary state during long periods of burnup. (M.C.K.)

  18. HORECA. Hoger onderwijs reactor elementary core analysis system. User's manual

    International Nuclear Information System (INIS)

    Battum, E. van; Serov, I.V.

    1993-07-01

    HORECA is developed at IRI Delft for quick analysis of power distribution, burnup and safety for the HOR. It can be used for the manual search of a better loading of the reactor. HORECA is based on the Penn State Fuel Management Package and uses the MCRAC code included in this package as a calculation engine. (orig./HP)

  19. Functional Behavioral Assessment: An Interactive Training Module. User's Manual & Facilitator's Guide. Second Edition.

    Science.gov (United States)

    Liaupsin, Carl J.; Scott, Terry M.; Nelson, C. Michael

    This user's manual and facilitator's guide is intended for use with an accompanying interactive CD-ROM to provide a complete training program in conducting functional behavioral assessments (FBAs) as required under the 1997 reauthorization of the Individuals with Disabilities Education Act. Chapter 1 provides general information for users, such as…

  20. DAKOTA JAGUAR 2.1 user's Manual.

    Energy Technology Data Exchange (ETDEWEB)

    Adams, Brian M.; Lefantzi, Sophia; Chan, Ethan; Ruthruff, Joseph R.

    2011-06-01

    JAGUAR (JAva GUi for Applied Research) is a Java software tool providing an advanced text editor and graphical user interface (GUI) to manipulate DAKOTA (Design Analysis Kit for Optimization and Terascale Applications) input specifications. This document focuses on the features necessary for a user to use JAGUAR.

  1. TRENDS: A flight test relational database user's guide and reference manual

    Science.gov (United States)

    Bondi, M. J.; Bjorkman, W. S.; Cross, J. L.

    1994-01-01

    This report is designed to be a user's guide and reference manual for users intending to access rotocraft test data via TRENDS, the relational database system which was developed as a tool for the aeronautical engineer with no programming background. This report has been written to assist novice and experienced TRENDS users. TRENDS is a complete system for retrieving, searching, and analyzing both numerical and narrative data, and for displaying time history and statistical data in graphical and numerical formats. This manual provides a 'guided tour' and a 'user's guide' for the new and intermediate-skilled users. Examples for the use of each menu item within TRENDS is provided in the Menu Reference section of the manual, including full coverage for TIMEHIST, one of the key tools. This manual is written around the XV-15 Tilt Rotor database, but does include an appendix on the UH-60 Blackhawk database. This user's guide and reference manual establishes a referrable source for the research community and augments NASA TM-101025, TRENDS: The Aeronautical Post-Test, Database Management System, Jan. 1990, written by the same authors.

  2. National Synchrotron Light Source user's manual: Guide to the VUV and x-ray beamlines

    International Nuclear Information System (INIS)

    Gmuer, N.F.

    1993-04-01

    The success of the National Synchrotron Light Source is based, in large part, on the size of the user community and the diversity of the scientific and technical disciplines represented by these users. As evidence of this success, the VUV Ring has just celebrated its 10th anniversary and the X-ray Ring will do the same in 1995. In order to enhance this success, the NSLS User's Manual: Guide to the VUV and X-Ray Beamlines - Fifth Edition, is being published. This Manual presents to the scientific community-at-large the current and projected architecture, capabilities and research programs of the various VUV and X-ray beamlines. Also detailed is the research and computer equipment a General User can expect to find and use at each beamline when working at the NSLS. The Manual is updated periodically in order to keep pace with the constant changes on these beamlines

  3. Vault Safety and Inventory System users manual, PRIME 2350. Revision 1

    International Nuclear Information System (INIS)

    Downey, N.J.

    1994-01-01

    This revision is issued to request review of the attached document: VSIS User Manual, PRIME 2350, which provides user information for the operation of the VSIS (Vault Safety and Inventory System). It describes operational aspects of Prime 2350 minicomputer and vault data acquisition equipment. It also describes the User's Main Menu and menu functions, including REPORTS. Also, system procedures for the Prime 2350 minicomputer are covered

  4. Transportation Routing Analysis Geographic Information System (TRAGIS) User's Manual

    Energy Technology Data Exchange (ETDEWEB)

    Johnson, PE

    2003-09-18

    The Transportation Routing Analysis Geographic Information System (TRAGIS) model is used to calculate highway, rail, or waterway routes within the United States. TRAGIS is a client-server application with the user interface and map data files residing on the user's personal computer and the routing engine and network data files on a network server. The user's manual provides documentation on installation and the use of the many features of the model.

  5. A User's Manual for the NRN Shield Design Method

    Energy Technology Data Exchange (ETDEWEB)

    Hjaerne, Leif [ed.; Aalto, E; Fraeki, R; Leimdoerfer, M; Lindblom, K; Linde, S; Malen, K; Nyman, K

    1964-06-15

    This report describes a code system for bulk shield design written for a Ferranti Mercury computer and is intended as a manual for those using the programme. The idea of an 'almost direct' flux, as in the removal theory serves as a basis for further development of the theory. An important aspiration has been to minimize the manual work of administering the codes. The codes concerned are: NECO, computing necessary group constants from primary data, REFUSE and REBOX (infinite plane or cylindrical, and box geometry, respectively), computing removal flux, NEDI a one-dimensional (plane, spherical, cylindrical) diffusion multigroup code, and SALOME a Monte Carlo code computing the gamma flux. Output tapes are constructed for direct use as input tapes, when required, for a following code.

  6. A User's Manual for the NRN Shield Design Method

    International Nuclear Information System (INIS)

    Hjaerne, Leif; Aalto, E.; Fraeki, R.; Leimdoerfer, M.; Lindblom, K.; Linde, S.; Malen, K.; Nyman, K.

    1964-06-01

    This report describes a code system for bulk shield design written for a Ferranti Mercury computer and is intended as a manual for those using the programme. The idea of an 'almost direct' flux, as in the removal theory serves as a basis for further development of the theory. An important aspiration has been to minimize the manual work of administering the codes. The codes concerned are: NECO, computing necessary group constants from primary data, REFUSE and REBOX (infinite plane or cylindrical, and box geometry, respectively), computing removal flux, NEDI a one-dimensional (plane, spherical, cylindrical) diffusion multigroup code, and SALOME a Monte Carlo code computing the gamma flux. Output tapes are constructed for direct use as input tapes, when required, for a following code

  7. User manual for Blossom statistical package for R

    Science.gov (United States)

    Talbert, Marian; Cade, Brian S.

    2005-01-01

    Blossom is an R package with functions for making statistical comparisons with distance-function based permutation tests developed by P.W. Mielke, Jr. and colleagues at Colorado State University (Mielke and Berry, 2001) and for testing parameters estimated in linear models with permutation procedures developed by B. S. Cade and colleagues at the Fort Collins Science Center, U.S. Geological Survey. This manual is intended to provide identical documentation of the statistical methods and interpretations as the manual by Cade and Richards (2005) does for the original Fortran program, but with changes made with respect to command inputs and outputs to reflect the new implementation as a package for R (R Development Core Team, 2012). This implementation in R has allowed for numerous improvements not supported by the Cade and Richards (2005) Fortran implementation, including use of categorical predictor variables in most routines.

  8. High-level neutron coincidence counter (HLNCC): users' manual

    International Nuclear Information System (INIS)

    Krick, M.S.; Menlove, H.O.

    1979-06-01

    This manual describes the portable High-Level Neutron Coincidence Counter (HLNCC) developed at the Los Alamos Scientific Laboratory (LASL) for the assay of plutonium, particularly by inspectors of the International Atomic Energy Agency (IAEA). The counter is designed for the measurement of the effective 240 Pu mass in plutonium samples which may have a high plutonium content. The following topics are discussed: principle of operation, description of the system, operating procedures, and applications

  9. I need to know! Timely accessing of perioperative user manuals.

    Science.gov (United States)

    Landreneau, Raphael

    2010-12-01

    Ready access to equipment or product information is essential for the safe operation of the many items that a perioperative nurse is asked to use, troubleshoot, or maintain. One institution's solution for making manufacturer information available in the practice setting was to create a facility intranet site dedicated to OR equipment manuals. This site provides information access to perioperative nurses and support staff members and, ultimately, helps improve patient care. Published by Elsevier Inc. All rights reserved.

  10. 3D-CDTI User Manual v2.1

    Science.gov (United States)

    Johnson, Walter; Battiste, Vernol

    2016-01-01

    The 3D-Cockpit Display of Traffic Information (3D-CDTI) is a flight deck tool that presents aircrew with: proximal traffic aircraft location, their current status and flight plan data; strategic conflict detection and alerting; automated conflict resolution strategies; the facility to graphically plan manual route changes; time-based, in-trail spacing on approach. The CDTI is manipulated via a touchpad on the flight deck, and by mouse when presented as part of a desktop flight simulator.

  11. User's manual for the CORTES GRAPHICS PACKAGE GRFPAK

    International Nuclear Information System (INIS)

    1977-01-01

    This report provides necessary user information to implement and use a graphics package for the CORTES finite-element computer programs. Complete input instructions are provided. Sample input and output are given

  12. A user input manual for single fuel rod behaviour analysis code FEMAXI-III

    International Nuclear Information System (INIS)

    Saito, Hiroaki; Yanagisawa, Kazuaki; Fujita, Misao.

    1983-03-01

    Principal objectives of Safety related research in connection with lighr water reactor fuel rods under normal operating condition are mainly addressed 1) to assess fuel integrity under steady state condition and 2) to generate initial condition under hypothetical accident. These assessments have to be relied principally upon steady state fuel behaviour computing code that is able to calculate fuel conditions to tbe occurred in a various manner. To achieve these objectives, efforts have been made to develope analytical computer code that calculates in-reactor fuel rod behaviour in best estimate manner. The computer code developed for the prediction of the long-term burnup response of single fuel rod under light water reactor condition is the third in a series of code versions:FEMAMI-III. The code calculates temperature, rod internal gas pressure, fission gas release and pellet-cladding interaction related rod deformation as a function of time-dependent fuel rod power and coolant boundary conditions. This document serves as a user input manual for the code FEMAMI-III which has opened to the public in year of 1982. A general description of the code input and output are included together with typical examples of input data. A detailed description of structures, analytical submodels and solution schemes in the code shall be given in the separate document to be published. (author)

  13. User's manual for the ARMLID (Argonne metallic lithium/isotopic dilution) tritium assay system

    International Nuclear Information System (INIS)

    Porges, K.G.; Bretscher, M.M.; Bennett, E.F.; DiIorio, G.; Mattas, R.F.; Lewandowski, E.F.

    1992-08-01

    The Argonne Metallic Lithium - Isotopic Dilution (ARMLID) system described in this report, originally developed at ANL for other purposes, was recently redeployed to measure the tritium production rate (TPR) in a series of US/Japanese collaborative fusion blanket integral experiments, involving large assemblies of fusion breeder blanket materials that were irradiated with a fusion neutron source at FNS/JAERI, Japan. Whereas previous uses of the ARMUD scheme involved just a few samples, its application infusion blanket TPR mapping called for large sample numbers per experiment, implying a commensurate scale of sample fabrication and encapsulation, on one hand, and tritium extraction and counting on the other hand. To shorten the time required for these various tasks, yet still yield reliable and accurate results, both the sample fabrication - encapsulation facility and the tritium extraction system had to be extensively revised from original versions that were designed for accuracy, but not necessarily for speed. The present report describes overall revisions in sufficient detail to serve as a User's Manual for this facility, and/or suggest how a new system might be put together. Either possibility may develop in the near future, in support of ITER design studies. Preliminary and partial descriptions of various aspects and features of the system were presented orally, in the course of annual ANL/JAERI/UCLA ''workshops'', over the last 34 years, as well as elsewhere

  14. Xyce Parallel Electronic Simulator Users Guide Version 6.2.

    Energy Technology Data Exchange (ETDEWEB)

    Keiter, Eric R.; Mei, Ting; Russo, Thomas V.; Schiek, Richard Louis; Sholander, Peter E.; Thornquist, Heidi K.; Verley, Jason C.; Baur, David Gregory

    2014-09-01

    This manual describes the use of the Xyce Parallel Electronic Simulator. Xyce has been de- signed as a SPICE-compatible, high-performance analog circuit simulator, and has been written to support the simulation needs of the Sandia National Laboratories electrical designers. This development has focused on improving capability over the current state-of-the-art in the following areas: Capability to solve extremely large circuit problems by supporting large-scale parallel com- puting platforms (up to thousands of processors). This includes support for most popular parallel and serial computers. A differential-algebraic-equation (DAE) formulation, which better isolates the device model package from solver algorithms. This allows one to develop new types of analysis without requiring the implementation of analysis-specific device models. Device models that are specifically tailored to meet Sandia's needs, including some radiation- aware devices (for Sandia users only). Object-oriented code design and implementation using modern coding practices. Xyce is a parallel code in the most general sense of the phrase -- a message passing parallel implementation -- which allows it to run efficiently a wide range of computing platforms. These include serial, shared-memory and distributed-memory parallel platforms. Attention has been paid to the specific nature of circuit-simulation problems to ensure that optimal parallel efficiency is achieved as the number of processors grows. Trademarks The information herein is subject to change without notice. Copyright c 2002-2014 Sandia Corporation. All rights reserved. Xyce TM Electronic Simulator and Xyce TM are trademarks of Sandia Corporation. Portions of the Xyce TM code are: Copyright c 2002, The Regents of the University of California. Produced at the Lawrence Livermore National Laboratory. Written by Alan Hindmarsh, Allan Taylor, Radu Serban. UCRL-CODE-2002-59 All rights reserved. Orcad, Orcad Capture, PSpice and Probe are

  15. Xyce Parallel Electronic Simulator Users Guide Version 6.4

    Energy Technology Data Exchange (ETDEWEB)

    Keiter, Eric R. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Mei, Ting [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Russo, Thomas V. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Schiek, Richard [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Sholander, Peter E. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Thornquist, Heidi K. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Verley, Jason [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Baur, David Gregory [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2015-12-01

    This manual describes the use of the Xyce Parallel Electronic Simulator. Xyce has been de- signed as a SPICE-compatible, high-performance analog circuit simulator, and has been written to support the simulation needs of the Sandia National Laboratories electrical designers. This development has focused on improving capability over the current state-of-the-art in the following areas: Capability to solve extremely large circuit problems by supporting large-scale parallel com- puting platforms (up to thousands of processors). This includes support for most popular parallel and serial computers. A differential-algebraic-equation (DAE) formulation, which better isolates the device model package from solver algorithms. This allows one to develop new types of analysis without requiring the implementation of analysis-specific device models. Device models that are specifically tailored to meet Sandia's needs, including some radiation- aware devices (for Sandia users only). Object-oriented code design and implementation using modern coding practices. Xyce is a parallel code in the most general sense of the phrase -- a message passing parallel implementation -- which allows it to run efficiently a wide range of computing platforms. These include serial, shared-memory and distributed-memory parallel platforms. Attention has been paid to the specific nature of circuit-simulation problems to ensure that optimal parallel efficiency is achieved as the number of processors grows. Trademarks The information herein is subject to change without notice. Copyright c 2002-2015 Sandia Corporation. All rights reserved. Xyce TM Electronic Simulator and Xyce TM are trademarks of Sandia Corporation. Portions of the Xyce TM code are: Copyright c 2002, The Regents of the University of California. Produced at the Lawrence Livermore National Laboratory. Written by Alan Hindmarsh, Allan Taylor, Radu Serban. UCRL-CODE-2002-59 All rights reserved. Orcad, Orcad Capture, PSpice and Probe are

  16. EXFOR Manual. Center-to-Center Exchange Format. Version 89-1

    International Nuclear Information System (INIS)

    McLane, V.

    1989-09-01

    EXFOR is the agreed exchange format for the transmission of nuclear reaction data between national and international nuclear data centers for the benefit of nuclear data users in all countries. EXFOR is a database with several million data records containing the world's experimental nuclear reaction data induced by neutrons, photons or charged particles. Data retrievals can be obtained from the IAEA Nuclear Data Section (NDS) or from one of the co-operating data centers whose names and addresses can be found inside the manual. Their contributions and co-operative efforts are gratefully acknowledged. (author). Refs

  17. INES: The International Nuclear Event Scale user's manual

    International Nuclear Information System (INIS)

    1992-09-01

    The revised and extended addition of the International Nuclear Event Scale is presented. The manual is comprised of four parts. Part 1 contains a summary of the basis of the scale and of the procedure to be used for rating events. Part 2 contains the detailed guidance required to rate events in terms of off-site and on-site impact. These two parts are applicable to all nuclear facilities. Parts 3 and 4 contain the detailed guidance required to rate events in terms of defence in depth for reactors and other facilities, respectively. 5 figs, 2 tabs

  18. A user's manual for managing database system of tensile property

    International Nuclear Information System (INIS)

    Ryu, Woo Seok; Park, S. J.; Kim, D. H.; Jun, I.

    2003-06-01

    This manual is written for the management and maintenance of the tensile database system for managing the tensile property test data. The data base constructed the data produced from tensile property test can increase the application of test results. Also, we can get easily the basic data from database when we prepare the new experiment and can produce better result by compare the previous data. To develop the database we must analyze and design carefully application and after that, we can offer the best quality to customers various requirements. The tensile database system was developed by internet method using Java, PL/SQL, JSP(Java Server Pages) tool

  19. User Manuals for a Primary Care Electronic Medical Record System: A Mixed Methods Study of User- and Vendor-Generated Documents.

    Science.gov (United States)

    Shachak, Aviv; Dow, Rustam; Barnsley, Jan; Tu, Karen; Domb, Sharon; Jadad, Alejandro R; Lemieux-Charles, Louise

    2013-06-04

    Tutorials and user manuals are important forms of impersonal support for using software applications including electronic medical records (EMRs). Differences between user- and vendor documentation may indicate support needs, which are not sufficiently addressed by the official documentation, and reveal new elements that may inform the design of tutorials and user manuals. What are the differences between user-generated tutorials and manuals for an EMR and the official user manual from the software vendor? Effective design of tutorials and user manuals requires careful packaging of information, balance between declarative and procedural texts, an action and task-oriented approach, support for error recognition and recovery, and effective use of visual elements. No previous research compared these elements between formal and informal documents. We conducted an mixed methods study. Seven tutorials and two manuals for an EMR were collected from three family health teams and compared with the official user manual from the software vendor. Documents were qualitatively analyzed using a framework analysis approach in relation to the principles of technical documentation described above. Subsets of the data were quantitatively analyzed using cross-tabulation to compare the types of error information and visual cues in screen captures between user- and vendor-generated manuals. The user-developed tutorials and manuals differed from the vendor-developed manual in that they contained mostly procedural and not declarative information; were customized to the specific workflow, user roles, and patient characteristics; contained more error information related to work processes than to software usage; and used explicit visual cues on screen captures to help users identify window elements. These findings imply that to support EMR implementation, tutorials and manuals need to be customized and adapted to specific organizational contexts and workflows. The main limitation of the study

  20. User Manuals for a Primary Care Electronic Medical Record System: A Mixed Methods Study of User- and Vendor-Generated Documents

    Science.gov (United States)

    Dow, Rustam; Barnsley, Jan; Tu, Karen; Domb, Sharon; Jadad, Alejandro R.; Lemieux-Charles, Louise

    2015-01-01

    Research problem Tutorials and user manuals are important forms of impersonal support for using software applications including electronic medical records (EMRs). Differences between user- and vendor documentation may indicate support needs, which are not sufficiently addressed by the official documentation, and reveal new elements that may inform the design of tutorials and user manuals. Research question What are the differences between user-generated tutorials and manuals for an EMR and the official user manual from the software vendor? Literature review Effective design of tutorials and user manuals requires careful packaging of information, balance between declarative and procedural texts, an action and task-oriented approach, support for error recognition and recovery, and effective use of visual elements. No previous research compared these elements between formal and informal documents. Methodology We conducted an mixed methods study. Seven tutorials and two manuals for an EMR were collected from three family health teams and compared with the official user manual from the software vendor. Documents were qualitatively analyzed using a framework analysis approach in relation to the principles of technical documentation described above. Subsets of the data were quantitatively analyzed using cross-tabulation to compare the types of error information and visual cues in screen captures between user- and vendor-generated manuals. Results and discussion The user-developed tutorials and manuals differed from the vendor-developed manual in that they contained mostly procedural and not declarative information; were customized to the specific workflow, user roles, and patient characteristics; contained more error information related to work processes than to software usage; and used explicit visual cues on screen captures to help users identify window elements. These findings imply that to support EMR implementation, tutorials and manuals need to be customized and

  1. User's manual of a support system for human reliability analysis

    International Nuclear Information System (INIS)

    Yokobayashi, Masao; Tamura, Kazuo.

    1995-10-01

    Many kinds of human reliability analysis (HRA) methods have been developed. However, users are required to be skillful so as to use them, and also required complicated works such as drawing event tree (ET) and calculation of uncertainty bounds. Moreover, each method is not so complete that only one method of them is not enough to evaluate human reliability. Therefore, a personal computer (PC) based support system for HRA has been developed to execute HRA practically and efficiently. The system consists of two methods, namely, simple method and detailed one. The former uses ASEP that is a simplified THERP-technique, and combined method of OAT and HRA-ET/DeBDA is used for the latter. Users can select a suitable method for their purpose. Human error probability (HEP) data were collected and a database of them was built to use for the support system. This paper describes outline of the HRA methods, support functions and user's guide of the system. (author)

  2. GENII: The Hanford Environmental Radiation Dosimetry Software System: Volume 2, Users' manual: Hanford Environmental Dosimetry Upgrade Project

    International Nuclear Information System (INIS)

    Napier, B.A.; Peloquin, R.A.; Strenge, D.L.; Ramsdell, J.V.

    1988-11-01

    The Hanford Environmental Dosimetry Upgrade Project was undertaken to incorporate the internal dosimetry models recommended by the International Commission on Radiological Protection (ICRP) in updated versions of the environmental pathway analysis models used at Hanford. The resulting second generation of Hanford environmental dosimetry computer codes is compiled in the Hanford Environmental Dosimetry System (Generation II, or GENII). The purpose of this coupled system of computer codes is to analyze environmental contamination of, air, water, or soil. This is accomplished by calculating radiation doses to individuals or populations. GENII is described in three volumes of documentation. This second volume is a Users' Manual, providing code structure, users' instructions, required system configurations, and QA-related topics. The first volume describes the theoretical considerations of the system. The third volume is a Code Maintenance Manual for the user who requires knowledge of code detail. It includes logic diagrams, global dictionary, worksheets, example hand calculations, and listings of the code and its associated data libraries. 27 refs., 17 figs., 23 tabs

  3. DAKOTA JAGUAR 3.0 user's manual.

    Energy Technology Data Exchange (ETDEWEB)

    Adams, Brian M.; Bauman, Lara E; Chan, Ethan; Lefantzi, Sophia; Ruthruff, Joseph.

    2013-05-01

    JAGUAR (JAva GUi for Applied Research) is a Java software tool providing an advanced text editor and graphical user interface (GUI) to manipulate DAKOTA (Design Analysis Kit for Optimization and Terascale Applications) input specifications. This document focuses on the features necessary to use JAGUAR.

  4. SRIM User’s Manual Release 2.0

    Science.gov (United States)

    1986-03-01

    scale factor :512 Complex image file : test.ci Complex image maximum magnitude : 0.142081E+01 User scified scaling factor 0.512000E+03 Comands : [F...larger (in space dimensions) blocks being used to represent the image. This is similar to grain size in photographic film . If a fine grain image is

  5. User's manual for the FLORA equilibrium and stability code

    International Nuclear Information System (INIS)

    Freis, R.P.; Cohen, B.I.

    1985-01-01

    This document provides a user's guide to the content and use of the two-dimensional axisymmetric equilibrium and stability code FLORA. FLORA addresses the low-frequency MHD stability of long-thin axisymmetric tandem mirror systems with finite pressure and finite-larmor-radius effects. FLORA solves an initial-value problem for interchange, rotational, and ballooning stability

  6. Non-RF Chain of Custody Item Monitor (CoCIM) User Manual.

    Energy Technology Data Exchange (ETDEWEB)

    Brotz, Jay Kristoffer [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Wade, James Rokwel [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Schwartz, Steven Robert [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2017-06-01

    This User Manual contains a description of the wired and infrared (IR) variants of the Chain of Custody Item Monitor (CoCIM), the Coordinator for reading stored messages, and the inspector Message Viewer user interface (UI) software, as well as instructions for use. This manual does not include descriptions or use instructions for the radio frequency (RF) variant of the CoCIM. The intended audience is planners and participants in treaty verification exercises where chain of custody (CoC) elements are required.

  7. User's Manual for SPECTROM-41: a Finite-Element Heat Transfer Program

    International Nuclear Information System (INIS)

    Svalstad, D.K.

    1983-06-01

    This User's Manual addresses SPECTROM-41: A Finite Element Heat Transfer Computer Program. The user is introduced to the program's capabilities and operation, with required user input outlined in detail. Example problems are included to illustrate the use of the various program features, and included to illustrate the use of the various program features, and analytical solutions are presented for four of the examples to provide a measure of program accuracy. Past and ongoing comparative benchmark analyses are highlighted to provide the user with an indication of how SPECTROM-41 predictions compare with other available heat transfer programs

  8. INTERLINE, a railroad routing model: program description and user's manual

    International Nuclear Information System (INIS)

    Peterson, B.E.

    1985-11-01

    INTERLINE is an interactive computer program that finds likely routes for shipments over the US railroad system. It is based on a shortest path algorithm modified both to reflect the nature of railroad company operations and to accommodate computer resource limitations in dealing with a large transportation network. The first section of the report discusses the nature of railroad operations and routing practices in the United States, including the tendency to concentrate traffic on a limited number of mainlines, the competition for traffic by different companies operating in the same corridors, and the tendency of originating carriers to retain traffic on their systems before transferring it to terminating carriers. The theoretical foundation and operation of shortest path algorithms are described, as well as the techniques used to simulate actual operating practices within this framework. The second section is a user's guide that describes the program operation and data structures, program features, and user access. 11 refs., 11 figs

  9. Naval Aviation Integrated Logistics: Technical users guide version 1. 0

    Energy Technology Data Exchange (ETDEWEB)

    DeLozier, R.C.; Holder, D.A.

    1987-06-01

    This document summarizes the operational and analytical functions of version 1.0 of the Naval Aviation Integrated Logistic (NAIL) package. NAIL, a logistics management and analysis system, creates standardized reports and performs several categories of statistical operations in support of NAVAIR logistic analytic functions.

  10. NASA Lewis steady-state heat pipe code users manual

    International Nuclear Information System (INIS)

    Tower, L.K.

    1992-06-01

    The NASA Lewis heat pipe code has been developed to predict the performance of heat pipes in the steady state. The code can be used as a design tool on a personal computer or, with a suitable calling routine, as a subroutine for a mainframe radiator code. A variety of wick structures, including a user input option, can be used. Heat pipes with multiple evaporators, condensers, and adiabatic sections in series and with wick structures that differ among sections can be modeled. Several working fluids can be chosen, including potassium, sodium, and lithium, for which the monomer-dimer equilibrium is considered. The code incorporates a vapor flow algorithm that treats compressibility and axially varying heat input. This code facilitates the determination of heat pipe operating temperatures and heat pipe limits that may be encountered at the specified heat input and environment temperature. Data are input to the computer through a user-interactive input subroutine. Output, such as liquid and vapor pressures and temperatures, is printed at equally spaced axial positions along the pipe as determined by the user

  11. e+e- event generator EPOCS user's manual

    International Nuclear Information System (INIS)

    Kato, Kiyoshi; Munehisa, Tomo.

    1987-07-01

    EPOCS(Electron POsitron Collision Simulator) is a Monte-Carlo event generator for high energy e + e - annihilation. This program generates events based on the standard model, i.e., quantum chromodynamics (QCD) and electro-weak theory. It works at the center-of-mass energy below W + W - production, i.e., in the energy region of TRISTAN, SLC and LEP. For these high energy machines one of the important subjects is the exploration for the top quark. The production and hadronization of the top quark is included in EPOCS. Besides the top quark, we expect 'new' physics in this high energy region. EPOCS has enough flexibility for users to cope with a new idea. Users can register a new particle, modify the built-in particle data, define new primary interactions and so on. The event generator has a number of parameters, both physical parameters and control parameters. Users can control most of these parameters in EPOCS at will. (author)

  12. A valiant little terminal: A VLT user's manual

    International Nuclear Information System (INIS)

    Weinstein, A.

    1992-08-01

    VLT came to be used at SLAC (Stanford Linear Accelerator Center), because SLAC wanted to assess the Amiga's usefulness as a color graphics terminal and T E X workstation. Before the project could really begin, the people at SLAC needed a terminal emulator which could successfully talk to the IBM 3081 (now the IBM ES9000-580) and all the VAXes on the site. Moreover, it had to compete in quality with the Ann Arbor Ambassador GXL terminals which were already in use at the laboratory. Unfortunately, at the time there was no commercial program which fit the bill. Luckily, Willy Langeveld had been independently hacking up a public domain VT100 emulator written by Dave Wecker et al. and the result, VLT, suited SLAC's purpose. Over the years, as the program was debugged and rewritten, the original code disappeared, so that now, in the present version of VLT, none of the original VT100 code remains

  13. Micromechanical combined stress analysis: MICSTRAN, a user manual

    Science.gov (United States)

    Naik, R. A.

    1992-01-01

    Composite materials are currently being used in aerospace and other applications. The ability to tailor the composite properties by the appropriate selection of its constituents, the fiber and matrix, is a major advantage of composite materials. The Micromechanical Combined Stress Analysis (MICSTRAN) code provides the materials engineer with a user-friendly personal computer (PC) based tool to calculate overall composite properties given the constituent fiber and matrix properties. To assess the ability of the composite to carry structural loads, the materials engineer also needs to calculate the internal stresses in the composite material. MICSTRAN is a simple tool to calculate such internal stresses with a composite ply under combined thermomechanical loading. It assumes that the fibers have a circular cross-section and are arranged either in a repeating square or diamond array pattern within a ply. It uses a classical elasticity solution technique that has been demonstrated to calculate accurate stress results. Input to the program consists of transversely isotropic fiber properties and isotropic matrix properties such as moduli, Poisson's ratios, coefficients of thermal expansion, and volume fraction. Output consists of overall thermoelastic constants and stresses. Stresses can be computed under the combined action of thermal, transverse, longitudinal, transverse shear, and longitudinal shear loadings. Stress output can be requested along the fiber-matrix interface, the model boundaries, circular arcs, or at user-specified points located anywhere in the model. The MICSTRAN program is Windows compatible and takes advantage of the Microsoft Windows graphical user interface which facilitates multitasking and extends memory access far beyond the limits imposed by the DOS operating system.

  14. BWR plant dynamic analysis code BWRDYN user's manual

    International Nuclear Information System (INIS)

    Yokobayashi, Masao; Yoshida, Kazuo; Fujiki, Kazuo

    1989-06-01

    Computer code BWRDYN has been developed for thermal-hydraulic analysis of a BWR plant. It can analyze the various types of transient caused by not only small but also large disturbances such as operating mode changes and/or system malfunctions. The verification of main analytical models of the BWRDYN code has been performed with measured data of actual BWR plant. Furthermore, the installation of BOP (Balance of Plant) model has made it possible to analyze the effect of BOP on reactor system. This report describes on analytical models and instructions for user of the BWRDYN code. (author)

  15. User manual for the KfK code PCROSS

    International Nuclear Information System (INIS)

    Ravndal, S.; Oblozinsky, P.; Kelzenberg, S.; Cierjacks, S.

    1991-08-01

    The PCROSS code calculates the so-called 'pseudo' cross sections for sequential (x,n) reactions and merges them together with 'collapsed' cross sections for neutron induced reactions into one file of cross sections. The file is tailored to provide an input for the FISPACT inventory code that calculates the activation and related radiological quantities of material irradiated in a neutron flux. The present report describes the structure of the KfK code PCROSS, outlines the role of subroutines, and provides necessary information for a practical user of the code. (orig.) [de

  16. HIGHWAY, a transportation routing model: program description and users' manual

    International Nuclear Information System (INIS)

    Joy, D.S.; Johnson, P.E.; Gibson, S.M.

    1982-12-01

    A computerized transportation routing model has been developed at the Oak Ridge National Laboratory to be used for predicting likely routes for shipping radioactive materials. The HIGHWAY data base is a computerized road atlas containing descriptions of the entire interstate highway system, the federal highway system, and most of the principal state roads. In addition to its prediction of the most likely commercial route, options incorporated in the HIGHWAY model can allow for maximum use of interstate highways or routes that will bypass urbanized areas containing populations > 100,000. The user may also interactively modify the data base to predict routes that bypass any particular state, city, town, or specific highway segment

  17. Flexible Receiver Radiation Detection System (FRRDS) Users Manual

    International Nuclear Information System (INIS)

    Troyer, G.L.

    1996-01-01

    The Flexible Receiver Radiation Detection System (FRRDS) comprises a control computer, a remote data acquisition subsystem, and three hyperpure germanium gamma radiation detectors. The scope of this document is the description of various steps for the orderly start-up, use, and shutdown of the FRRDS. Only those items necessary for these oprations are included. This document is a companion to WHC-SD-W151-UM-002, 'Operating Instructions for the 42 Inch Flexible Receiver,' WHC-SD-W151-UM-003, 'Operating Instructions for the 4-6 Inch Flexible Receiver,' and the vendor supplied system users guide (Ref. 6)

  18. Radioactive Materials Packaging (RAMPAC) Radioactive Materials Incident Report (RMIR). RAMTEMP users manual

    International Nuclear Information System (INIS)

    Tyron-Hopko, A.K.; Driscoll, K.L.

    1985-10-01

    The purpose of this document is to familiarize the potential user with RadioActive Materials PACkaging (RAMPAC), Radioactive Materials Incident Report (RMIR), and RAMTEMP databases. RAMTEMP is a minor image of RAMPAC. This reference document will enable the user to access and obtain reports from databases while in an interactive mode. This manual will be revised as necessary to reflect enhancements made to the system

  19. AutoBayes Program Synthesis System Users Manual

    Science.gov (United States)

    Schumann, Johann; Jafari, Hamed; Pressburger, Tom; Denney, Ewen; Buntine, Wray; Fischer, Bernd

    2008-01-01

    Program synthesis is the systematic, automatic construction of efficient executable code from high-level declarative specifications. AutoBayes is a fully automatic program synthesis system for the statistical data analysis domain; in particular, it solves parameter estimation problems. It has seen many successful applications at NASA and is currently being used, for example, to analyze simulation results for Orion. The input to AutoBayes is a concise description of a data analysis problem composed of a parameterized statistical model and a goal that is a probability term involving parameters and input data. The output is optimized and fully documented C/C++ code computing the values for those parameters that maximize the probability term. AutoBayes can solve many subproblems symbolically rather than having to rely on numeric approximation algorithms, thus yielding effective, efficient, and compact code. Statistical analysis is faster and more reliable, because effort can be focused on model development and validation rather than manual development of solution algorithms and code.

  20. DeCART v1.2 User's Manual

    International Nuclear Information System (INIS)

    Cho, J. Y.; Kim, K. S.; Kim, H. Y.; Lee, C. C.; Zee, S. Q; Joo, H. G.

    2007-07-01

    DeCART (Deterministic Core Analysis based on Ray Tracing) is a whole core neutron transport code capable of direct subpin level flux calculation at power generating conditions. It does not require a priori homogenization nor group condensation needed in conventional reactor physics calculations. The depletion and transient calculation capabilities are also available. This manual serves as a self-sufficient guide to use the code. First of all, the various features of the code are explained which encompass various modeling options as well as the basic calculation functionalities. The instructions for running the code are also given with a description of the output files generated. Next, the underlying concepts and principles of preparing a DeCART model for a problem under consideration are presented. Each part of the input needed to specify the geometry, material composition, thermal operating condition, program execution control parameters are explained with examples. The descriptions of all the input cards are then followed. Finally, various sample model inputs ranging from a simple 2D pin cell to a realistic 3D core problem, steady-state to transient problems, and from rectangular to hexagonal core problems are presented

  1. DeCART v1.1 user's manual

    International Nuclear Information System (INIS)

    Cho, J. Y.; Kim, K. S.; Kim, H. Y.; Lee, C. C.; Zee, S. Q.; Joo, H. G.

    2005-03-01

    DeCART (Deterministic Core Analysis based on Ray Tracing) is a whole core neutron transport code capable of direct subpin level flux calculation at power generating conditions. It does not require a priori homogenization nor group condensation needed in conventional reactor physics calculations. The depletion and transient calculation capabilities are also available. This manual serves as a self-sufficient guide to use the code. First of all, the various features of the code are explained which encompass various modeling options as well as the basic calculation functionalities. The instructions for running the code are also given with a description of the output files generated. Next, the underlying concepts and principles of preparing a DeCART model for a problem under consideration are presented. Each part of the input needed to specify the geometry, material composition, thermal operating condition, program execution control parameters are explained with examples. The descriptions of all the input cards are then followed. Finally, various sample model inputs ranging from a simple 2D pin cell to a realistic 3D core problem, steady-state to transient problems, are presented

  2. CONPAS 1.0 (CONtainment Performance Analysis System). User's manual

    International Nuclear Information System (INIS)

    Ahn, Kwang Il; Jin, Young Ho

    1996-04-01

    CONPAS (CONtainment Performance Analysis System) is a verified computer code package to integrate the numerical, graphical, and results-operation aspects of Level 2 probabilistic safety assessments (PSA) for nuclear power plants automatically under a PC window environment. Compared with the existing DOS-based computer codes for Level 2 PSA, the most important merit of the window-based computer code is that user can easily describe and quantify the accident progression models, and manipulate the resultant outputs in a variety of ways. As a main logic for accident progression analysis, CONPAS employs a concept of the small containment phenomenological event tree (CPET) helpful to trace out visually individual accident progressions and of the large supporting event tree (LSET) for its detailed quantification. For the integrated analysis of Level 2 PSA, the code utilizes four distinct, but closely related modules; (1) ET Editor for construction of several event tree models describing the accident progressions, (2) Computer for quantification of the constructed event trees and graphical display of the resultant outputs, (3) Text Editor for preparation of input decks for quanification and utilization of calculational results, and (4) Mechanistic Code Plotter for utilization of results obtained from severe accident analysis codes. Compared with other existing computer codes for Level 2 PSA, the CONPAS code provides several advanced features: computational aspects including systematic uncertainty analysis, importance analysis, sensitivity analysis and data interpretation, reporting aspects including tabling and graphic as well as user-friend interface. 10 refs. (Author) .new

  3. Turbsim User's Guide: Version 1.50

    Energy Technology Data Exchange (ETDEWEB)

    Jonkman, B. J.

    2009-09-01

    This report is a user's guide for the TurbSim code. TurbSim stochastic inflow turbulence code is a wind turbine design code that simulates a full-field flow containing coherent turbulence associated with nocturnal boundary layer flows.

  4. User manual for PACTOLUS: a code for computing power costs.

    Energy Technology Data Exchange (ETDEWEB)

    Huber, H.D.; Bloomster, C.H.

    1979-02-01

    PACTOLUS is a computer code for calculating the cost of generating electricity. Through appropriate definition of the input data, PACTOLUS can calculate the cost of generating electricity from a wide variety of power plants, including nuclear, fossil, geothermal, solar, and other types of advanced energy systems. The purpose of PACTOLUS is to develop cash flows and calculate the unit busbar power cost (mills/kWh) over the entire life of a power plant. The cash flow information is calculated by two principal models: the Fuel Model and the Discounted Cash Flow Model. The Fuel Model is an engineering cost model which calculates the cash flow for the fuel cycle costs over the project lifetime based on input data defining the fuel material requirements, the unit costs of fuel materials and processes, the process lead and lag times, and the schedule of the capacity factor for the plant. For nuclear plants, the Fuel Model calculates the cash flow for the entire nuclear fuel cycle. For fossil plants, the Fuel Model calculates the cash flow for the fossil fuel purchases. The Discounted Cash Flow Model combines the fuel costs generated by the Fuel Model with input data on the capital costs, capital structure, licensing time, construction time, rates of return on capital, tax rates, operating costs, and depreciation method of the plant to calculate the cash flow for the entire lifetime of the project. The financial and tax structure for both investor-owned utilities and municipal utilities can be simulated through varying the rates of return on equity and debt, the debt-equity ratios, and tax rates. The Discounted Cash Flow Model uses the principal that the present worth of the revenues will be equal to the present worth of the expenses including the return on investment over the economic life of the project. This manual explains how to prepare the input data, execute cases, and interpret the output results. (RWR)

  5. SAFEPAQ-II. User manual[Nuclear data

    Energy Technology Data Exchange (ETDEWEB)

    Forrest, R.A

    2001-03-01

    SAFEPAQ-II is the new software tool that has been developed to enable efficient production of the EAF nuclear data libraries that are required as input to the FISPACT activation code. It forms part of the European Activation System (EASY), and replaces SAFEPAQ and SYMPAL that were used previously. It enables all the nuclear data to be stored in relational databases (Access) and by using an interactive user interface allows the data to be viewed, modified, validated and then produced in the required EAF format as text files. It is written in Visual Basic and runs under the Windows NT4 and 98 operating systems. The Windows operating system has the great advantage of portability and SAFEPAQ-II has been successfully installed at two external sites for use by UKAEA's international collaborators. It has been used in the production of the EAF-2001 data libraries. (author)

  6. User's manual for Ecolego Toolbox and the Discretization Block

    International Nuclear Information System (INIS)

    Broed, Robert; Shulan Xu

    2008-03-01

    The CLIMB modelling team (Catchment LInked Models of radiological effects in the Biosphere) was instituted in 2004 to provide SSI with an independent modelling capability when reviewing SKB's assessment of long-term safety for a geological repository. Modelling in CLIMB covers all aspects of performance assessment (PA) from near-field releases to radiological consequences in the surface environment. Software used to implement assessment models has been developed within the project. The software comprises a toolbox based on the commercial packages Matlab and Simulink used to solve compartment based differential equation systems, but with an added user friendly graphical interface. This report documents the new simulation toolbox and a newly developed Discretisation Block, which is a powerful tool for solving problems involving a network of compartments in two dimensions

  7. URSULA2 computer program. Volume 3. User's manual. Final report

    International Nuclear Information System (INIS)

    Singhal, A.K.

    1980-01-01

    This report is intended to provide documentation for the users of the URSULA2 code so that they can appreciate its important features such as: code structure, flow chart, grid notations, coding style, usage of secondary storage and its interconnection with the input preparation program (Reference H3201/4). Subroutines and subprograms have been divided into four functional groups. The functions of all subroutines have been explained with particular emphasis on the control subroutine (MAIN) and the data input subroutine (BLOCK DATA). Computations for the flow situations similar to the reference case can be performed simply by making alterations in BLOCK DATA. Separate guides for the preparation of input data and for the interpretation of program output have been provided. Furthermore, two appendices; one for the URSULA2 listing and the second for the glossary of FORTRAN variables, are included to make this report self-sufficient

  8. The TESS [Tandem Experiment Simulation Studies] computer code user's manual

    International Nuclear Information System (INIS)

    Procassini, R.J.

    1990-01-01

    TESS (Tandem Experiment Simulation Studies) is a one-dimensional, bounded particle-in-cell (PIC) simulation code designed to investigate the confinement and transport of plasma in a magnetic mirror device, including tandem mirror configurations. Mirror plasmas may be modeled in a system which includes an applied magnetic field and/or a self-consistent or applied electrostatic potential. The PIC code TESS is similar to the PIC code DIPSI (Direct Implicit Plasma Surface Interactions) which is designed to study plasma transport to and interaction with a solid surface. The codes TESS and DIPSI are direct descendants of the PIC code ES1 that was created by A. B. Langdon. This document provides the user with a brief description of the methods used in the code and a tutorial on the use of the code. 10 refs., 2 tabs

  9. User's manual for the radioactive decay and accumulation code RADAC

    International Nuclear Information System (INIS)

    Salmon, R.; Loghry, S.L.; Ashline, R.C.

    1995-11-01

    The RADAC computer code calculates radioactive decay and accumulation of decayed products using an algorithm based on the direct use of the Bateman equations and referred to here as the yield factor method. This report explains the yield factor method, gives an overview of the various modules in the RADAC code system, and describes the decay and accumulation code in detail. The RADAC code has capacity for two waste types and can accommodate up to 60 years of annual waste inputs. Decay times as high as 1 million years can be calculated. The user supplies the undecayed composition and radioactivity of the waste placed in storage each year. The code calculates the decayed composition, radioactivity, and thermal power of the accumulated waste at the end of each year and gives the results in terms of grams and curies of individual radionuclides. Calculations can be made for up to 19 waste storage sites in a single run. For each site and each waste type, calculations can be made by 1-year steps up to 60 years, by 10-year steps to 160 years, and by 6 discrete steps to 1 million years. Detailed outputs can be printed for each waste site and each time step by individual radionuclides. Summarized outputs are also available. Excluding data-preparation time, RADAC requires about 2 min to run 19 waste sites with two types of transuranic waste at each site, using a 486 DX computer with a clock speed of 33 MHz. Because RADAC uses a preselected set of decay times and does not make in-reactor calculations, it should not be viewed as a substitute for ORIGEN2. RADAC is intended for use in applications in which accumulations at the decay times provided by the code are sufficient for the user's purposes

  10. Viscous wing theory development. Volume 2: GRUMWING computer program user's manual

    Science.gov (United States)

    Chow, R. R.; Ogilvie, P. L.

    1986-01-01

    This report is a user's manual which describes the operation of the computer program, GRUMWING. The program computes the viscous transonic flow over three-dimensional wings using a boundary layer type viscid-inviscid interaction approach. The inviscid solution is obtained by an approximate factorization (AFZ)method for the full potential equation. The boundary layer solution is based on integral entrainment methods.

  11. RisoeScan 1.0 - User manual and toolset for retrospective validation

    Energy Technology Data Exchange (ETDEWEB)

    Helt-Hansen, J

    2004-12-01

    The RisoeScan software is used for dose measurements with radiochromic films that color visibly. This report consists of two documents for use with the RisoeScan software. The User Manual tells how to use the program and the Toolset for Retrospective Validation describes how to perform a retrospective validation of the software. (au)

  12. The Gift Code User Manual. Volume I. Introduction and Input Requirements

    Science.gov (United States)

    1975-07-01

    REPORT & PERIOD COVERED ‘TII~ GIFT CODE USER MANUAL; VOLUME 1. INTRODUCTION AND INPUT REQUIREMENTS FINAL 6. PERFORMING ORG. REPORT NUMBER ?. AuTHOR(#) 8...reverua side if neceaeary and identify by block number] (k St) The GIFT code is a FORTRANcomputerprogram. The basic input to the GIFT ode is data called

  13. Greater-than-Class-C Low-Level Waste Data Base user's manual

    International Nuclear Information System (INIS)

    1992-07-01

    The Greater-than-Class-C Low-level Waste (GTCC LLW) Data Base characterizes GTCC LLW using low, base, and high cases for three different scenarios: unpackaged, packaged, and concentration averages. The GTCC LLW Data Base can be used to project future volumes and radionuclide activities. This manual provides instructions for users of the GTCC LLW Data Base

  14. User's manual for the computer-aided plant transient data compilation

    International Nuclear Information System (INIS)

    Langenbuch, S.; Gill, R.; Lerchl, G.; Schwaiger, R.; Voggenberger, T.

    1984-01-01

    The objective of this project is the compilation of data for nuclear power plants needed for transient analyses. The concept has been already described. This user's manual gives a detailed description of all functions of the dialogue system that supports data acquisition and retrieval. (orig.) [de

  15. The computer code Eurdyn - 1 M. (Release 1) Part 2: User's Manual

    International Nuclear Information System (INIS)

    Donea, J.; Giuliani, S.

    1979-01-01

    This report is the user's manual for the computer code Eurdyn-1 M developed at the J.R.C. Ispra for use in containment and fuel subassembly analyses for fast reactor safety studies. The input data are defined and a test problem is presented to illustrate both the input and the output of results

  16. RisøScan 1.0 - User manual and toolset for retrospective validation

    DEFF Research Database (Denmark)

    Helt-Hansen, Jakob

    2004-01-01

    The RisøScan software is used for dose measurements with radiochromic films that color visibly. This report consists of two documents for use with the RisøScan software. The User Manual tells how to use the program and the Toolset for RetrospectiveValidation describes how to perform a retrospective...

  17. Technical Report and Data File User's Manual for the 1992 National Adult Literacy Survey.

    Science.gov (United States)

    Kirsch, Irwin; Yamamoto, Kentaro; Norris, Norma; Rock, Donald; Jungeblut, Ann; O'Reilly, Patricia; Berlin, Martha; Mohadjer, Leyla; Waksberg, Joseph; Goksel, Huseyin; Burke, John; Rieger, Susan; Green, James; Klein, Merle; Campbell, Anne; Jenkins, Lynn; Kolstad, Andrew; Mosenthal, Peter; Baldi, Stephane

    Chapter 1 of this report and user's manual describes design and implementation of the 1992 National Adult Literacy Survey (NALS). Chapter 2 reviews stages of sampling for national and state survey components; presents weighted and unweighted response rates for the household component; and describes non-incentive and prison sample designs. Chapter…

  18. BASINs 4.0 Climate Assessment Tool (CAT): Supporting Documentation and User's Manual (Final Report)

    Science.gov (United States)

    EPA announced the availability of the report, BASINS 4.0 Climate Assessment Tool (CAT): Supporting Documentation and User's Manual. This report was prepared by the EPA's Global Change Research Program (GCRP), an assessment-oriented program, that sits within the Office of R...

  19. Corrections Officer Candidate Information Booklet and User's Manual. Standards and Training for Corrections Program.

    Science.gov (United States)

    California State Board of Corrections, Sacramento.

    This package consists of an information booklet for job candidates preparing to take California's Corrections Officer Examination and a user's manual intended for those who will administer the examination. The candidate information booklet provides background information about the development of the Corrections Officer Examination, describes its…

  20. Probation Officer Candidate Information Booklet and User's Manual. Standards and Training for Corrections Program.

    Science.gov (United States)

    California State Board of Corrections, Sacramento.

    This package consists of an information booklet for job candidates preparing to take California's Probation Officer Examination and a user's manual intended for those who will administer the examination. The candidate information booklet provides background information about the development and validation of the Probation Officer Examination,…

  1. Manually Classifying User Search Queries on an Academic Library Web Site

    Science.gov (United States)

    Chapman, Suzanne; Desai, Shevon; Hagedorn, Kat; Varnum, Ken; Mishra, Sonali; Piacentine, Julie

    2013-01-01

    The University of Michigan Library wanted to learn more about the kinds of searches its users were conducting through the "one search" search box on the Library Web site. Library staff conducted two investigations. A preliminary investigation in 2011 involved the manual review of the 100 most frequently occurring queries conducted…

  2. Versions in the lifecycle of academic papers user requirements and guidelins fo digital repositories

    CERN Multimedia

    CERN. Geneva

    2005-01-01

    An academic research paper evolves through various stages during its lifecycle, for example from early conference presentation through working paper to final published refereed journal article. Different versions can co-exist in publicly available electronic form. Finding out researchers’ attitudes towards storing, labelling and making accessible these different versions, both of their own and of their peers’ work is at the heart of the VERSIONS Project, funded by the JISC under the Digital Repositories Programme. The project addresses the issues and uncertainties relating to versions of academic papers in digital repositories. By including a user requirements study, the project will clarify the needs of researchers and other stakeholders for deposit, storage and accessibility of different versions in the lifecycle of a digital resource. In addition to looking at user needs, the project will analyse researchers’ current practice in terms of retention of author copies of their own material. This investig...

  3. DATE V1 - Data Aquisition Test Environment Users Manual

    CERN Document Server

    Grandegger, W; CERN. Geneva

    1996-01-01

    The Data Aquisition presented here has been developed for maximum portability and generality. If you are lucky you will have tailored the system to your experimental set-up in less than a day and start taking data. It should run any UNIX system and some non-UNIX system and has already been tested on the following systems: Linux (IBM PC and compatible) OSF (Alpha workstations and Medulla VME board) HP-UX (workstation + 743 VME board) HP-RT AIX OS91) LynxOS (tested on a 68040 and a PowerPC) 1) The system was originally developed under UNIX. Only due to popular request of people who wanted to reuse old hardware it was ported to OS9. This is, however, not the recommended hardware and future improvements of the system are not going to be refitted to OS9. Currently we distribute only the OS9 and HP-UX binary versions, but you get the code and can compile it on any of the above systems and with some luck on others.

  4. NETPATH-WIN: an interactive user version of the mass-balance model, NETPATH

    Science.gov (United States)

    El-Kadi, A. I.; Plummer, Niel; Aggarwal, P.

    2011-01-01

    NETPATH-WIN is an interactive user version of NETPATH, an inverse geochemical modeling code used to find mass-balance reaction models that are consistent with the observed chemical and isotopic composition of waters from aquatic systems. NETPATH-WIN was constructed to migrate NETPATH applications into the Microsoft WINDOWS® environment. The new version facilitates model utilization by eliminating difficulties in data preparation and results analysis of the DOS version of NETPATH, while preserving all of the capabilities of the original version. Through example applications, the note describes some of the features of NETPATH-WIN as applied to adjustment of radiocarbon data for geochemical reactions in groundwater systems.

  5. Distributed Observer Network (DON), Version 3.0, User's Guide

    Science.gov (United States)

    Mazzone, Rebecca A.; Conroy, Michael P.

    2015-01-01

    The Distributed Observer Network (DON) is a data presentation tool developed by the National Aeronautics and Space Administration (NASA) to distribute and publish simulation results. Leveraging the display capabilities inherent in modern gaming technology, DON places users in a fully navigable 3-D environment containing graphical models and allows the users to observe how those models evolve and interact over time in a given scenario. Each scenario is driven with data that has been generated by authoritative NASA simulation tools and exported in accordance with a published data interface specification. This decoupling of the data from the source tool enables DON to faithfully display a simulator's results and ensure that every simulation stakeholder will view the exact same information every time.

  6. User's manual for the Graphical Constituent Loading Analysis System (GCLAS)

    Science.gov (United States)

    Koltun, G.F.; Eberle, Michael; Gray, J.R.; Glysson, G.D.

    2006-01-01

    This manual describes the Graphical Constituent Loading Analysis System (GCLAS), an interactive cross-platform program for computing the mass (load) and average concentration of a constituent that is transported in stream water over a period of time. GCLAS computes loads as a function of an equal-interval streamflow time series and an equal- or unequal-interval time series of constituent concentrations. The constituent-concentration time series may be composed of measured concentrations or a combination of measured and estimated concentrations. GCLAS is not intended for use in situations where concentration data (or an appropriate surrogate) are collected infrequently or where an appreciable amount of the concentration values are censored. It is assumed that the constituent-concentration time series used by GCLAS adequately represents the true time-varying concentration. Commonly, measured constituent concentrations are collected at a frequency that is less than ideal (from a load-computation standpoint), so estimated concentrations must be inserted in the time series to better approximate the expected chemograph. GCLAS provides tools to facilitate estimation and entry of instantaneous concentrations for that purpose. Water-quality samples collected for load computation frequently are collected in a single vertical or at single point in a stream cross section. Several factors, some of which may vary as a function of time and (or) streamflow, can affect whether the sample concentrations are representative of the mean concentration in the cross section. GCLAS provides tools to aid the analyst in assessing whether concentrations in samples collected in a single vertical or at single point in a stream cross section exhibit systematic bias with respect to the mean concentrations. In cases where bias is evident, the analyst can construct coefficient relations in GCLAS to reduce or eliminate the observed bias. GCLAS can export load and concentration data in formats

  7. ADVISOR Users Conference Proceedings 2000 - Final Electronic version

    Energy Technology Data Exchange (ETDEWEB)

    NREL

    2000-09-26

    This is a compilation of papers presented at the ADVISOR (ADvanced Vehicle SimulatOR) Users Conference held in Costa Mesa, California, August 24-25, 2000. Major topics of the conference included modeling and simulation; partnering with the auto industry; co-simulation: partnering with the software industry in optimization and thermal modeling and geometric and mechanical modeling; forward-looking simulations coupled with ADVISOR; new concepts from universities; validation, vehicle development and applications.

  8. AIDA Asia. Artificial Insemination Database Application. User manual. 1

    International Nuclear Information System (INIS)

    Garcia Podesta, Mario

    2002-01-01

    Artificial Insemination Database Application (AIDA-Asia) is a computer application to store and analyze information from AI Services (farms, females, inseminated, semen, estrus characteristics, inseminator and pregnancy diagnosis data). The need for such an application arose during a consultancy undertaken by the author for the International Atomic Energy Agency (IAEA, Vienna) under the framework of its Regional Co-operative Agreement for Asia and the Pacific (RCA) which is implementing a project on 'Improving Animal Productivity and Reproductive Efficiency' (RAS/5/035). The detailed specifications for the application were determined through a Task Force Meeting of National Consultants from five RCA Member States, organized by the IAEA and held in Sri Lanka in April 2001. The application has been developed in MS Access 2000 and Visual Basic for Applications (VBA) 6.0. However, it can run as a stand-alone application through its own executable files. It is based on screen forms for data entry or editing of information and command buttons. The structure of the data, the design of the application and VBA codes cannot be seen and cannot be modified by users. However, the designated administrator of AIDA-Asia in each country can customize it

  9. Code manual for MACCS2: Volume 1, user's guide

    International Nuclear Information System (INIS)

    Chanin, D.I.; Young, M.L.

    1997-03-01

    This report describes the use of the MACCS2 code. The document is primarily a user's guide, though some model description information is included. MACCS2 represents a major enhancement of its predecessor MACCS, the MELCOR Accident Consequence Code System. MACCS, distributed by government code centers since 1990, was developed to evaluate the impacts of severe accidents at nuclear power plants on the surrounding public. The principal phenomena considered are atmospheric transport and deposition under time-variant meteorology, short- and long-term mitigative actions and exposure pathways, deterministic and stochastic health effects, and economic costs. No other U.S. code that is publicly available at present offers all these capabilities. MACCS2 was developed as a general-purpose tool applicable to diverse reactor and nonreactor facilities licensed by the Nuclear Regulatory Commission or operated by the Department of Energy or the Department of Defense. The MACCS2 package includes three primary enhancements: (1) a more flexible emergency-response model, (2) an expanded library of radionuclides, and (3) a semidynamic food-chain model. Other improvements are in the areas of phenomenological modeling and new output options. Initial installation of the code, written in FORTRAN 77, requires a 486 or higher IBM-compatible PC with 8 MB of RAM

  10. National Synchrotron Light Source users manual: Guide to the VUV and x-ray beam lines

    International Nuclear Information System (INIS)

    Gmuer, N.F.; White-DePace, S.M.

    1987-08-01

    The success of the National Synchrotron Light Source in the years to come will be based, in large part, on the size of the users community and the diversity of the scientific disciplines represented by these users. In order to promote this philosophy, this National Synchrotron Light Source (NSLS) Users Manual: Guide to the VUV and X-Ray Beam Lines, has been published. This manual serves a number of purposes. In an effort to attract new research, it will present to the scientific community-at-large the current and projected architecture and capabilities of the various VUV and x-ray beam lines and storage rings. We anticipate that this publication will be updated periodically in order to keep pace with the constant changes at the NSLS

  11. Quantitative X ray analysis system. User's manual and guide to X ray fluorescence technique

    International Nuclear Information System (INIS)

    2009-01-01

    This guide covers trimmed and re-arranged version 3.6 of the Quantitative X ray Analysis System (QXAS) software package that includes the most frequently used methods of quantitative analysis. QXAS is a comprehensive quantitative analysis package that has been developed by the IAEA through research and technical contracts. Additional development has also been carried out in the IAEA Laboratories in Seibersdorf where QXAS was extensively tested. New in this version of the manual are the descriptions of the Voigt-profile peak fitting, the backscatter fundamental parameters' and emission-transmission methods of chemical composition analysis, an expanded chapter on the X ray fluorescence physics, and completely revised and increased number of practical examples of utilization of the QXAS software package. The analytical data accompanying this manual were collected in the IAEA Seibersdorf Laboratories in the years 2006/2007

  12. SMART Structures User's Guide - Version 3.0

    Science.gov (United States)

    Spangler, Jan L.

    1996-01-01

    Version 3.0 of the Solid Modeling Aerospace Research Tool (SMART Structures) is used to generate structural models for conceptual and preliminary-level aerospace designs. Features include the generation of structural elements for wings and fuselages, the integration of wing and fuselage structural assemblies, and the integration of fuselage and tail structural assemblies. The highly interactive nature of this software allows the structural engineer to move quickly from a geometry that defines a vehicle's external shape to one that has both external components and internal components which may include ribs, spars, longerons, variable depth ringframes, a floor, a keel, and fuel tanks. The geometry that is output is consistent with FEA requirements and includes integrated wing and empennage carry-through and frame attachments. This report provides a comprehensive description of SMART Structures and how to use it.

  13. Wind-US Users Guide Version 4.0

    Science.gov (United States)

    Yoder, Dennis A.

    2016-01-01

    Wind-US is a computational platform which may be used to numerically solve various sets of equations governing physical phenomena. Currently, the code supports the solution of the Euler and Navier-Stokes equations of fluid mechanics, along with supporting equation sets governing turbulent and chemically reacting flows. Wind-US is a product of the NPARC Alliance, a partnership between the NASA Glenn Research Center (GRC) and the Arnold Engineering Development Complex (AEDC) dedicated to the establishment of a national, applications-oriented flow simulation capability. The Boeing Company has also been closely associated with the Alliance since its inception, and represents the interests of the NPARC User's Association. The "Wind-US User's Guide" describes the operation and use of Wind-US, including: a basic tutorial; the physical and numerical models that are used; the boundary conditions; monitoring convergence; the files that are read and/or written; parallel execution; and a complete list of input keywords and test options. For current information about Wind-US and the NPARC Alliance, please see the Wind-US home page at http://www.grc.nasa.gov/WWW/winddocs/ and the NPARC Alliance home page at http://www.grc.nasa.gov/WWW/wind/.

  14. Systems Analysis Programs for Hands-on Integrated Reliability Evaluations (SAPHIRE), Version 5.0. Volume 5, Systems Analysis and Risk Assessment (SARA) tutorial manual

    International Nuclear Information System (INIS)

    Sattison, M.B.; Russell, K.D.; Skinner, N.L.

    1994-07-01

    The Systems Analysis Programs for Hands-on Integrated Reliability Evaluations (SAPHIRE) refers to a set of several microcomputer programs that were developed to create and analyze probabilistic risk assessments (PRAs) primarily for nuclear power plants. This volume is the tutorial manual for the Systems Analysis and Risk Assessment (SARA) System Version 5.0, a microcomputer-based system used to analyze the safety issues of a open-quotes familyclose quotes [i.e., a power plant, a manufacturing facility, any facility on which a probabilistic risk assessment (PRA) might be performed]. A series of lessons is provided that guides the user through some basic steps common to most analyses performed with SARA. The example problems presented in the lessons build on one another, and in combination, lead the user through all aspects of SARA sensitivity analysis capabilities

  15. Guidelines for the verification and validation of expert system software and conventional software: User`s manual. Volume 7

    Energy Technology Data Exchange (ETDEWEB)

    Mirsky, S.M.; Hayes, J.E.; Miller, L.A. [Science Applications International Corp., McLean, VA (United States)

    1995-03-01

    This report provides a step-by-step guide, or user manual, for personnel responsible for the planning and execution of the verification and validation (V&V), and developmental testing, of expert systems, conventional software systems, and various other types of artificial intelligence systems. While the guide was developed primarily for applications in the utility industry, it applies well to all industries. The user manual has three sections. In Section 1 the user assesses the stringency of V&V needed for the system under consideration, identifies the development stage the system is in, and identifies the component(s) of the system to be tested next. These three pieces of information determine which Guideline Package of V&V methods is most appropriate for those conditions. The V&V Guideline Packages are provided in Section 2. Each package consists of an ordered set of V&V techniques to be applied to the system, guides on choosing the review/evaluation team, measurement criteria, and references to a book or report which describes the application of the method. Section 3 presents details of 11 of the most important (or least well-explained in the literature) methods to assist the user in applying these techniques accurately.

  16. Light Water Reactor Generic Safety Issues Database (LWRGSIDB). User's manual

    International Nuclear Information System (INIS)

    1999-01-01

    resolved in other plants and which can be used in reassessing the safety of individual operating plants. The IAEA-TECDOC-1044, Generic Safety Issues for Nuclear Power Plants with Light Water Reactors and Measures Taken for Their Resolution (September 1998), is a compilation of such safety issues which is based on broad international experience. This compilation is one element within the framework of IAEA activities to assist Member States in reassessing the safety of operating nuclear power plants. It is a compilation not only of the generic safety issues identified in nuclear power plants but also, in almost all cases, the measures taken to resolve these issues. The safety issues, which are generic in nature with regard to light water reactors (LWRs), and the measures taken for their resolution, are intended for use as a reference in the reassessment of the safety of operating plants.The information contained in the main body of the TECDOC has been used to establish a database. This database has search, query and report functions. This information is thus available in an electronic form which can be selectively queried and with which reports can be produced according to the requirements of the user. The database also enables the IAEA to update the data periodically on the basis of information made available by Member States

  17. Integrated Fuel-Coolant Interaction (IFCI 7.0) Code User's Manual

    Energy Technology Data Exchange (ETDEWEB)

    Young, Michael F.

    1999-05-01

    The integrated fuel-coolant interaction (IFCI) computer code is being developed at Sandia National Laboratories to investigate the fuel-coolant interaction (FCI) problem at large scale using a two-dimensional, three-field hydrodynamic framework and physically based models. IFCI will be capable of treating all major FCI processes in an integrated manner. This document is a description of IFCI 7.0. The user's manual describes the hydrodynamic method and physical models used in IFCI 7.0. Appendix A is an input manual provided for the creation of working decks.

  18. Integrated Fuel-Coolant Interaction (IFCI 7.0) Code User's Manual

    International Nuclear Information System (INIS)

    Young, Michael F.

    1999-01-01

    The integrated fuel-coolant interaction (IFCI) computer code is being developed at Sandia National Laboratories to investigate the fuel-coolant interaction (FCI) problem at large scale using a two-dimensional, three-field hydrodynamic framework and physically based models. IFCI will be capable of treating all major FCI processes in an integrated manner. This document is a description of IFCI 7.0. The user's manual describes the hydrodynamic method and physical models used in IFCI 7.0. Appendix A is an input manual provided for the creation of working decks

  19. DMPonline Version 4.0: User-Led Innovation

    Directory of Open Access Journals (Sweden)

    Magdalena Getler

    2014-07-01

    Full Text Available DMPonline is a web-based tool to help researchers and research support staff produce data management and sharing plans. Between October and December 2012, we examined DMPonline in unprecedented detail. The results of this evaluation led to some major changes. We have shortened the DCC Checklist for a Data Management Plan and revised how this is used in the tool. We have also amended the data model for DMPonline, improved workflows and redesigned the user interface. This paper reports on the evaluation, outlining the methods used, the results gathered and how they have been acted upon. We conducted usability testing on v.3 of DMPonline and the v.4 beta prior to release. The results from these two rounds of usability testing are compared to validate the changes made. We also put forward future plans for a more iterative development approach and greater community input.

  20. User's manual for ASTERIX-2: A two-dimensional modular code system for the steady state and xenon transient analysis of a pebble bed high temperature reactor

    International Nuclear Information System (INIS)

    Wu, T.; Cowan, C.L.; Lauer, A.; Schwiegk, H.J.

    1982-03-01

    The ASTERIX modular code package was developed at KFA Laboratory-Juelich for the steady state and xenon transient analysis of a pebble bed high temperature reactor. The code package was implemented on the Stanford Linear Accelerator Center Computer in August, 1980, and a user's manual for the current version of the code, identified as ASTERIX-2, was prepared as a cooperative effort by KFA Laboratory and GE-ARSD. The material in the manual includes the requirements for accessing the program, a description of the major subroutines, a listing of the input options, and a listing of the input data for a sample problem. The material is provided in sufficient detail for the user to carry out a wide range of analysis from steady state operations to the xenon induced power transients in which the local xenon, temperature, buckling and control feedback effects have been incorporated in the problem solution. (orig.)